WorldWideScience

Sample records for nuclear em area

  1. Development of parallel GPU based algorithms for problems in nuclear area; Desenvolvimento de algoritmos paralelos baseados em GPU para solucao de problemas na area nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Adino Americo Heimlich

    2009-07-01

    Graphics Processing Units (GPU) are high performance co-processors intended, originally, to improve the use and quality of computer graphics applications. Since researchers and practitioners realized the potential of using GPU for general purpose, their application has been extended to other fields out of computer graphics scope. The main objective of this work is to evaluate the impact of using GPU in two typical problems of Nuclear area. The neutron transport simulation using Monte Carlo method and solve heat equation in a bi-dimensional domain by finite differences method. To achieve this, we develop parallel algorithms for GPU and CPU in the two problems described above. The comparison showed that the GPU-based approach is faster than the CPU in a computer with two quad core processors, without precision loss. (author)

  2. ABACC's nuclear accounting area

    International Nuclear Information System (INIS)

    Nicolas, Ruben O.

    2001-01-01

    The functions and activities of the Brazilian-Argentine Agency for the Accounting and Control of Nuclear Materials (ABACC) accounting area is outlined together with a detailed description of the nuclear accounting system used by the bilateral organization

  3. Adaptation of the dynamic model for radiological assessment of nuclear accident in rural area under conditions of tropical climate; Adaptacao do modelo dinamico para avaliacao radiologica de acidente nuclear em area rural nas condicoes de clima tropical

    Energy Technology Data Exchange (ETDEWEB)

    Vinhas, Denise Martins

    2004-07-01

    Following an accidental release of radionuclides to the atmosphere that leads to the contamination of large areas, a detailed and fast methodology to assess the prognosis of public exposure is needed, in order to estimate radiological consequences and propose and optimize decisions related to the protection of the public. The model ECOSYS has been chosen to integrate the SIEM, the Integrated Emergency System developed by IRD/CNEN, to assess the doses at the short, medium and long term to the public after an accidental contamination of rural areas. The objective of this work is to perform the adaptation of the model ECOSYS to be used in Brazil to assess public exposure and support decision processes regarding the implementation of protective measures but also to guide the need for studies and research aiming to improve the adequacy of estimates to the actual Brazilian situation. The area select for reference to this work consists on the 50 km radius area surrounding the Brazilian nuclear power plants, located at Angra dos Reis County, in the state of Rio de Janeiro. The methodology included the definition of criteria to select agricultural cultures and animals to be simulated, taking into account both the availability of the production at the selected area and the relevance of the food to the population regional diet. Radionuclides included in this study were {sup 137}Cs, {sup 90} Sr and {sup 131} I. A large survey has been performed to gather data related to both agricultural practices and behavior of radionuclides in the selected agricultural-systems. The results of simulation indicated the relevance of the knowledge of local aspects on the estimated doses. Important factors included the kind of products produced, seasonality, agricultural practices, animals feed practices, kind of soil, and ingestion habits of the population. (author)

  4. Technical standards in nuclear area

    International Nuclear Information System (INIS)

    Grimberg, M.

    1978-01-01

    The technical standardization in nuclear area is discussed. Also, the competence of CNEN in standardization pursuit is analysed. Moreover, the process of working up of technical standards is explained; in addition, some kinds of technical standards are discussed. (author) [pt

  5. Performance evaluation of the conventional Brazilian industries radiation protection in the small industrial gauges and industrial radiography areas; Sistema de avaliacao de desempenho em radioprotecao das industrias convencionais brasileiras nas areas de medidores nucleares e radiografia industrial

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Joyra Amaral dos

    1999-08-01

    This works evaluates by punctuation the performance in conventional Brazilian industries radiation protection area which make use of small industrial gauges and industrial radiography. It proposes, procedures for industry self-evaluation, besides a new radiation protection plans pattern for the small industrial gauges area. The data source where inspection reports of Dosimetry Radiation Protection Institute/Nuclear Energy Commission conventional Brazilian industries' radiation protection plans, beyond visitation to the inspection place. The performance evaluation has been realized both in the administrative and operational aspects of the industries. About of 60% of the industries have a satisfactory register control which does not happen to the operational control. The performance evaluation advantage is that industries may self-evaluate, foreseeing Dosimetry Radiation Protection Institute's regulation inspections, correcting its irregularities, automatically improving its services. The number of industries which have obtained satisfactory performance in both areas is below 70%, both in administrative and operational aspects. Such number can be considered a low one as it is radiation protection. The procedures propose in this work aim to improve such a situation. (author)

  6. Nuclear power plants in populated areas

    International Nuclear Information System (INIS)

    Wachsmann, F.

    1973-01-01

    The article first deals with the permanently increasing demand for electical power. Considering the ever growing energy demand which can no longer be covered by conventional power plants, it has become necessary to set up nuclear power plants of larger range. The author presents in a survey the basic function of nuclear power plants as well as the resulting risks and safety measures. The author concludes that according to present knowledge there is no more need to erect nuclear power plants outside densely populated urban areas but there is now the possibility of erecting nuclear power plants in densely populated areas. (orig./LH) [de

  7. Nuclear Materials Focus Area Fiscal Year 2002 Mid Year Review

    Energy Technology Data Exchange (ETDEWEB)

    Thiel, Elizabeth Chilcote

    2002-05-01

    The Nuclear Materials Focus Area (NMFA) held its annual mid-year review on February 12 and 14, 2002, in Santa Fe, New Mexico. The purpose of this review was to examine both the technical aspects and the programmatic aspects of its technology development program. The focus area activities were reviewed by a panel consisting of personnel representing the end users of the technologies, and technical experts in nuclear materials. This year's review was somewhat different than in the past, as the stress was on how well the various projects being managed through the NMFA aligned with the two thrust areas and nine key goals and priorities recently issued by the Deputy Assistant Secretary for DOE's Office of Environmental Management (EM).

  8. Nuclear Materials Focus Area Fiscal Year 2002 Mid Year Review

    Energy Technology Data Exchange (ETDEWEB)

    Thiel, E.C.; Fuhrman, P.W.

    2002-05-30

    The Nuclear Materials Focus Area (NMFA) held its annual mid-year review on February 12 and 14, 2002, in Santa Fe, New Mexico. The purpose of this review was to examine both the technical aspects and the programmatic aspects of its technology development program. The focus area activities were reviewed by a panel consisting of personnel representing the end users of the technologies, and technical experts in nuclear materials. This year's review was somewhat different than in the past, as the stress was on how well the various projects being managed through the NMFA aligned with the two thrust areas and nine key goals and priorities recently issued by the Deputy Assistant Secretary for DOE's Office of Environmental Management (EM).

  9. Nuclear criticality safety: 300 Area

    International Nuclear Information System (INIS)

    1991-01-01

    This Standard applies to the receipt, processing, storage, and shipment of fissionable material in the 300 Area and in any other facility under the control of the Reactor Materials Project Management Team (PMT). The objective is to establish practices and process conditions for the storage and handling of fissionable material that prevent the accidental assembly of a critical mass and that comply with DOE Orders as well as accepted industry practice

  10. Vital areas at nuclear power plants

    International Nuclear Information System (INIS)

    Cameron, D.F.

    1985-01-01

    Vital area analysis of nuclear power plants has been performed for the Nuclear Regulatory Commission by the Los Alamos National Laboratory from the late 1970's through the present. The Los Alamos Vital Area Study uses a fault-tree modeling technique to identify vital areas and equipment at nuclear power plants to determine their vulnerability. This technique has been applied to all operating plants and approximately one-half of those under construction in the US. All saboteur-induced loss-of-coolant accidents and transients and the systems needed to mitigate them are considered. As a result of this effort, security programs at nuclear power plants now include vulnerability studies that identify targets in a systematic manner, and thus unnecessary protection has been minimized. 1 ref., 8 figs., 1 tab

  11. Insucessos em empreendimentos nucleares devido a falhas em processos de Comunicação Pública

    OpenAIRE

    Ferreira,Vinícius V. M.; Soares,Wellington A.

    2012-01-01

    A energia nuclear é um tema amplamente discutido em todo o mundo. O acidente nuclear de Chernobyl e o acidente radiológico de Goiânia contribuíram decisivamente para que a sociedade brasileira tivesse uma imagem negativa sobre o tema. A operação da usina de Angra 3, atualmente em obras, está vinculada à construção de um repositório para armazenar os rejeitos radioativos, o que provavelmente será explorado pelos opositores do setor nuclear. Um dos grandes desafios dos profissionais envolvidos ...

  12. Regional Suppression of <em>Bactrocera> Fruit Flies (Diptera: Tephritidae in the Pacific through Biological Control and Prospects for Future Introductions into Other Areas of the World

    Directory of Open Access Journals (Sweden)

    Roger I. Vargas

    2012-08-01

    Full Text Available <em>Bactrocera> fruit fly species are economically important throughout the Pacific. The USDA, ARS U.S. Pacific Basin Agricultural Research Center has been a world leader in promoting biological control of <em>Bactrocera> spp. that includes classical, augmentative, conservation and IPM approaches. In Hawaii, establishment of <em>Bactrocera> <em>cucurbitae> (Coquillett in 1895 resulted in the introduction of the most successful parasitoid, <em>Psyttalia> <em>fletcheri> (Silvestri; similarly, establishment of <em>Bactrocera> <em>dorsalis> (Hendel in 1945 resulted in the introduction of 32 natural enemies of which <em>Fopius> <em>arisanus> (Sonan, <em>Diachasmimorpha> <em>longicaudata> (Ashmead and <em>Fopius> <em>vandenboschi> (Fullaway were most successful. Hawaii has also been a source of parasitoids for fruit fly control throughout the Pacific region including Australia, Pacific Island Nations, Central and South America, not only for <em>Bactrocera> spp. but also for <em>Ceratitis> and <em>Anastrepha> spp. Most recently, in 2002, <em>F.> <em>arisanus> was introduced into French Polynesia where <em>B.> <em>dorsalis> had invaded in 1996. Establishment of <em>D.> <em>longicaudata> into the new world has been important to augmentative biological control releases against <em>Anastrepha> spp. With the rapid expansion of airline travel and global trade there has been an alarming spread of <em>Bactrocera> spp. into new areas of the world (<em>i.e.>, South America and Africa. Results of studies in Hawaii and French Polynesia, support parasitoid introductions into South America and Africa, where <em>B.> <em>carambolae> and <em>B.> <em>invadens>, respectively, have become established. In addition, <em>P.> <em>fletcheri> is a candidate for biological control of <em>B.> <em>cucurbitae> in Africa. We review past and more

  13. Technological development in the nuclear area: nuclear power production

    International Nuclear Information System (INIS)

    Lima, Jose Mendonca de.

    1991-01-01

    The factors and obstacles that influence the progress and regress of nuclear power presently are evaluated. The international policies of the industrial conglomerates and the hegemonic countries in the nuclear area are described. In the particular case of Brazil, it was tried to identify the obstacles which must be removed so that the country can reach development in this field. 35 refs., 9 figs., 9 tabs

  14. Areas control of a nuclear medicine service

    International Nuclear Information System (INIS)

    Silva, Islane C.S.; Silva, Iasmim M.S.; Júnior, Cláudio L.R.; Silva, Isvânia S.; Gonzalez, Kethyllém M.; Melo, Francisca A.; Lima, Fernando R.A.

    2017-01-01

    The measurement of the exposure rate of the sectors of a nuclear medicine service (NMS), with the purpose of establishing safety to the service workers and the public, classifying the areas according to the monitoring is presented. Following the studies on the classifications of the areas of a Nuclear Medicine service provided by the category regulatory standard, 3.05 CNEN-NN, measures were taken in all sectors of the NMS in order to classify the areas in: Free, controlled and supervised according to with the exposure level. As a measurement instrument, a Geiger-Muller counter of the digital type was used. The results obtained show a correlation with the Brazilian norm satisfactorily, referring to the exposure rate of the studied SMN sectors

  15. Local AREA networks in advanced nuclear reactors

    International Nuclear Information System (INIS)

    Bicknell, J.; Keats, A.B.

    1984-01-01

    The report assesses Local Area Network Communications with a view to their application in advanced nuclear reactor control and protection systems. Attention is focussed on commercially available techniques and systems for achieving the high reliability and availability required. A basis for evaluating network characteristics in terms of broadband or baseband type, medium, topology, node structure and access method is established. The reliability and availability of networks is then discussed. Several commercial networks are briefly assessed and a distinction made between general purpose networks and those suitable for process control. The communications requirements of nuclear reactor control and protection systems are compared with the facilities provided by current technology

  16. Environmental indicators for the nuclear area

    Energy Technology Data Exchange (ETDEWEB)

    Alves, Cezar Braga; Mattiolo, Sandra Regina, E-mail: cezar.braga@ctmsp.mar.mil.br [Centro Tecnologico da Marinha em Sao Paujo (CTMSP), Sao Paulo, SP (Brazil)

    2013-07-01

    Environmental indicators are tools utilized for measuring the industrial environmental performance and are globally used to provide the company and other stakeholders with information concerning its effectiveness and sustainability. Furthermore, the environmental indicators are an important methodological tool used for monitoring the effectiveness of Environmental Management System goals, as well as its compliance with the established environmental policies. Currently, major companies have reported their environmental indicators based on specialized guides, such as the CDP (Carbon Disclosure Project) and the GRI (Global Reporting Initiative), enumerating the most important indicators for the company activities. However, the GRI as other bibliographies of this subject does not include specific indicators for the nuclear area, leaving a significant gap to be considered for the measurement of environmental performance of this industry. Therefore, it becomes relevant to raise the following questions. May the nuclear sector use the same indicators of the non-nuclear industry? Are these indicators effective in demonstrating environmental commitment? In this work, a discussion of the indicators for the nuclear area and the CTMSP will take place. (author)

  17. Environmental indicators for the nuclear area

    International Nuclear Information System (INIS)

    Alves, Cezar Braga; Mattiolo, Sandra Regina

    2013-01-01

    Environmental indicators are tools utilized for measuring the industrial environmental performance and are globally used to provide the company and other stakeholders with information concerning its effectiveness and sustainability. Furthermore, the environmental indicators are an important methodological tool used for monitoring the effectiveness of Environmental Management System goals, as well as its compliance with the established environmental policies. Currently, major companies have reported their environmental indicators based on specialized guides, such as the CDP (Carbon Disclosure Project) and the GRI (Global Reporting Initiative), enumerating the most important indicators for the company activities. However, the GRI as other bibliographies of this subject does not include specific indicators for the nuclear area, leaving a significant gap to be considered for the measurement of environmental performance of this industry. Therefore, it becomes relevant to raise the following questions. May the nuclear sector use the same indicators of the non-nuclear industry? Are these indicators effective in demonstrating environmental commitment? In this work, a discussion of the indicators for the nuclear area and the CTMSP will take place. (author)

  18. Nuclear power for under-developed areas

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-07-15

    In evaluating the needs of the less developed countries for nuclear power and in determining how and to what extent these needs can be met, the fundamental questions to be decided are: (a) to what extent can the total power needs of these countries be met by conventional (thermal and hydro) means, (b) in which sectors would it be immediately possible - from both technical and economic points of view - to generate power from nuclear energy, and (c) in which areas would it be imperative to resort to nuclear power in the immediate future. The IAEA Second General Conference recommended a survey of the nuclear power needs of the less developed countries, a study on a continuing basis of the technology and economics of small and medium power reactors suited to these countries, dissemination of the information obtained and assistance in training personnel in the technology and economic utilization of such nuclear stations. And on the basis of this recommendation, the Agency has initiated an integrated two-year programme of work for examining the possibilities of utilizing nuclear power in under-developed countries. In carrying out this programme, the Agency is seeking potentially promising cases in which nuclear energy can yield necessarily limited but early benefits. That would help an assessment of the technical and economic possibilities of small and medium reactors in specific situations. It would also enable under-developed countries to compare and ascertain whether nuclear energy can provide an early solution to some of their pressing power problems. The first three phases of IAEA's work programme are: (i) studies on the technical suitability of reactors with a power level of up to 50 mw; (ii) economic studies in regard to reactor systems, including a systematic analysis of power costs; and (iii) selection of characteristic situations that appear to favour utilization of nuclear power. A survey of special interest in this connexion will be carried out by an Agency

  19. Nuclear power for under-developed areas

    International Nuclear Information System (INIS)

    1959-01-01

    In evaluating the needs of the less developed countries for nuclear power and in determining how and to what extent these needs can be met, the fundamental questions to be decided are: (a) to what extent can the total power needs of these countries be met by conventional (thermal and hydro) means, (b) in which sectors would it be immediately possible - from both technical and economic points of view - to generate power from nuclear energy, and (c) in which areas would it be imperative to resort to nuclear power in the immediate future. The IAEA Second General Conference recommended a survey of the nuclear power needs of the less developed countries, a study on a continuing basis of the technology and economics of small and medium power reactors suited to these countries, dissemination of the information obtained and assistance in training personnel in the technology and economic utilization of such nuclear stations. And on the basis of this recommendation, the Agency has initiated an integrated two-year programme of work for examining the possibilities of utilizing nuclear power in under-developed countries. In carrying out this programme, the Agency is seeking potentially promising cases in which nuclear energy can yield necessarily limited but early benefits. That would help an assessment of the technical and economic possibilities of small and medium reactors in specific situations. It would also enable under-developed countries to compare and ascertain whether nuclear energy can provide an early solution to some of their pressing power problems. The first three phases of IAEA's work programme are: (i) studies on the technical suitability of reactors with a power level of up to 50 mw; (ii) economic studies in regard to reactor systems, including a systematic analysis of power costs; and (iii) selection of characteristic situations that appear to favour utilization of nuclear power. A survey of special interest in this connexion will be carried out by an Agency

  20. Study of application of protective measures for the public and remediation of contaminated areas in case of nuclear and / or radiological accidents in Brazil; Estudo da aplicacao de medidas de protecao para o publico e de remediacao de areas contaminadas em caso de acidentes nucleares e/ou radiologicos no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo Neves Gomes da

    2011-07-01

    Since the radiological accident in Goiania in 1987, the IRD (Institute of Radiological Protection and Dosimetry - IRD / CNEN) has been developing tools to support decision-making processes after a nuclear or radiological accident which leads to an environmental contamination and to an exposure of individuals the public These processes include the establishment of a supporting multicriteria model, which involves the application of protective and remediation measures of contaminated areas in tropical environments. In this study, it was performed an evaluation of the efficiency of these measures in order to determine the consequences of their implementation, based on results obtained from the code SIEM (Emergency Integrated System), which constitutes an environmental mode1 developed at IRD to simulate this type of accident. In order to perform this evaluation, it was first developed a database containing descriptions of various protection/remediation measures, which could be applied nationwide. Afterwards, some basic scenarios were established, considering the environmental, housing and food characteristics of the population of the vicinity of the nuclear power plants in Angra dos Reis (state of Rio de Janeiro). Thus, the accident simulations were carried out separately containing releases of {sup 137}Cs, {sup 90}Sr and 131 I. The results showed that the dose reduction varies according to the extent and the timing of the remediation measure applied. Although it is possible to establish some basic guidelines, generic solutions are not recommended, since the resulting doses are highly dependent on the actual situation. Any decision-making process should be made case by case, according to the actual conditions of the affected area and to the occupation characteristics and use of the affected areas, considering the characteristics of the source term of contamination, the time of the year in which the accident occurs, the local agricultural practices and food habits of

  1. Determination of leakage areas in nuclear piping

    International Nuclear Information System (INIS)

    Keim, E.

    1997-01-01

    For the design and operation of nuclear power plants the Leak-Before-Break (LBB) behavior of a piping component has to be shown. This means that the length of a crack resulting in a leak is smaller than the critical crack length and that the leak is safely detectable by a suitable monitoring system. The LBB-concept of Siemens/KWU is based on computer codes for the evaluation of critical crack lengths, crack openings, leakage areas and leakage rates, developed by Siemens/KWU. In the experience with the leak rate program is described while this paper deals with the computation of crack openings and leakage areas of longitudinal and circumferential cracks by means of fracture mechanics. The leakage areas are determined by the integration of the crack openings along the crack front, considering plasticity and geometrical effects. They are evaluated with respect to minimum values for the design of leak detection systems, and maximum values for controlling jet and reaction forces. By means of fracture mechanics LBB for subcritical cracks has to be shown and the calculation of leakage areas is the basis for quantitatively determining the discharge rate of leaking subcritical through-wall cracks. The analytical approach and its validation will be presented for two examples of complex structures. The first one is a pipe branch containing a circumferential crack and the second one is a pipe bend with a longitudinal crack

  2. Determination of leakage areas in nuclear piping

    Energy Technology Data Exchange (ETDEWEB)

    Keim, E. [Siemens/KWU, Erlangen (Germany)

    1997-04-01

    For the design and operation of nuclear power plants the Leak-Before-Break (LBB) behavior of a piping component has to be shown. This means that the length of a crack resulting in a leak is smaller than the critical crack length and that the leak is safely detectable by a suitable monitoring system. The LBB-concept of Siemens/KWU is based on computer codes for the evaluation of critical crack lengths, crack openings, leakage areas and leakage rates, developed by Siemens/KWU. In the experience with the leak rate program is described while this paper deals with the computation of crack openings and leakage areas of longitudinal and circumferential cracks by means of fracture mechanics. The leakage areas are determined by the integration of the crack openings along the crack front, considering plasticity and geometrical effects. They are evaluated with respect to minimum values for the design of leak detection systems, and maximum values for controlling jet and reaction forces. By means of fracture mechanics LBB for subcritical cracks has to be shown and the calculation of leakage areas is the basis for quantitatively determining the discharge rate of leaking subcritical through-wall cracks. The analytical approach and its validation will be presented for two examples of complex structures. The first one is a pipe branch containing a circumferential crack and the second one is a pipe bend with a longitudinal crack.

  3. Synergy in the areas of NPP nuclear safety and nuclear security

    International Nuclear Information System (INIS)

    Dybach, A.M.; Kuzmyak, I.Ya.; Kukhotskij, A.V.

    2013-01-01

    The paper considers the question of synergy between nuclear safety and nuclear security. Special attention is paid to identifying interface of the two areas of safety and definition of common principles for nuclear security and nuclear safety measures. The principles of defense in depth, safety culture and graded approach are analyzed in detail.Specific features characteristic of nuclear safety and security are outlined

  4. Lippe-Ems GmbH nuclear power stations. Annual report 1992

    International Nuclear Information System (INIS)

    1993-01-01

    The Nuclear power company Lippe-Ems GmbH (KLE) runs the Emsland Nuclear Power Station (KKE) in Lingen (Ems) with a 1300 MW pressurized Water reactor. Partners of KLE are VEW and Elektromark. This 1992 annual report reveals numerous financial data of the operator (balance sheet, profit and loss account.) (orig./UA) [de

  5. Localization of nuclear retained mRNAs in <em>Saccharomyces cerevisiaeem>

    DEFF Research Database (Denmark)

    Thomsen, Rune; Libri, Domenico; Boulay, Jocelyne

    2003-01-01

    site of transcription, and known S. cerevisiae nuclear structures such as the nucleolus and the nucleolar body. Our results show that retained SSA4 RNA localizes to an area in close proximity to the SSA4 locus. On deletion of Rrp6p and release from the genomic locus, heat shock mRNAs produced...

  6. Brief introduction of nuclear power plant emergency system EmInfoSys

    International Nuclear Information System (INIS)

    Xiao Yuhua; Zhao Zhigang

    2014-01-01

    Nuclear safety is the lifeline of nuclear energy and nuclear technology, nuclear accident emergency response is the last line of nuclear security defense, and is one of the important measures to ensure the healthy development of the nuclear energy safety. The establishment of complete function, sensitive reaction and efficient emergency management system for operation of nuclear and radiation accidents is an important task of nuclear security. From 2001 China Techenergy Co., Ltd. participated in the Qinshan, Tianwan, Ministry of Environmental Protection, Haiyang, Taishan, Fangchenggang, Sanmen, etc. nuclear emergency projects, and the nuclear emergency EmInfoSys (emergency management information system) platform was developed with independent intellectual property rights. A brief introduction about EmInfoSys system was performed in this paper. (authors)

  7. Reproducibility of mean nuclear volume and correlation with mean nuclear area in breast cancer

    DEFF Research Database (Denmark)

    Baak, J P; Ladekarl, M; Sørensen, Flemming Brandt

    1994-01-01

    reproducible and strongly correlated with nuclear vv assessed in the TOTAL. In invasive breast cancer assessments in the whole tumor section can be used if delineation of the measurement area cannot be done easily. In small areas with a limited number of nuclei (eg, microinvasive parts) MNA can be easier......Previous studies have shown that quantitative, histopathologic features obtained from a carefully selected area in the tumor section ("selective" approach) have a strong prognostic value in breast cancer. On the other hand, it was found that mean nuclear volume estimation in the whole area...... as to their intraobserver and interobserver reproducibility in 22 invasive breast cancer cases. The mean nuclear volume (nuclear vv) was assessed both in the most atypical area (AREA) (selected on morphologic criteria) and in the whole tumor section (TOTAL). Furthermore, the correlation with mean nuclear (profile) area...

  8. Identification of Vital Areas at Nuclear Facilities. Technical Guidance

    International Nuclear Information System (INIS)

    2012-01-01

    nuclear installations against sabotage are contained in IAEA Nuclear Security Series No. 13, Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5). After the attacks of 11 September 2001, the perception of the potential terrorist threat to nuclear installations changed significantly, and the IAEA initiated an effort to develop a series of guidance publications on the security of nuclear and radioactive material and facilities. This publication presents a structured approach to identifying the areas that contain equipment, systems, and components to be protected against sabotage. It specifically provides detailed guidance with regard to the identification of vital areas, that is, the areas to be protected in high consequence facilities. However, the process described is applicable to the identification of areas that should be protected at any nuclear facility. The method builds upon safety analyses to develop sabotage logic models for sabotage scenarios that could cause unacceptable radiological consequences. The sabotage actions represented in the logic models are linked to the areas from which they can be accomplished. The logic models are then analysed to determine areas that should be protected to prevent these unacceptable radiological consequences.

  9. A Program to Stabilize Nuclear Materials as Managed by the Plutonium Focus Area

    International Nuclear Information System (INIS)

    Kenley, B.; Scott, B.; Seidel, B.; Knecht, D.; Southworth, F.; Osborne, K.; Chipman, N.; Creque, T.

    1999-01-01

    This paper describes the program to stabilize nuclear materials, consistent with the Department of Energy Office of Environmental Management (EM) plan, Accelerating Cleanup: Paths to Closure. The program is managed by the Plutonium Stabilization and Disposition Focus Area, which defines and manages technology development programs to stabilize nuclear materials and assure their subsequent safe storage and final disposition. The scope of the Plutonium Stabilization and Disposition Focus Area (PFA) activities includes non-weapons plutonium materials, special isotopes, and other fissile materials. The PFA provides solutions to site-specific and complex wide technology issues associated with plutonium remediation, stabilization, and preparation for disposition. Our paper describes an important programmatic function of the Department of Energy nuclear materials stabilization program, including the tie-in of policy to research needs and funding for the nuclear materials disposition area. The PFA uses a rigorous systems engineering determination of technology needs and gaps, under the guidance of a Technical Advisory Panel, consisting of complex-wide experts. The Research and Development planning provides an example for other waste areas and should be of interest to Research and Development managers. The materials disposition maps developed by the PFA and described in this paper provide an evaluation of research needs, data gaps and subsequent guidance for the development of technologies for nuclear materials disposition. This paper also addresses the PFA prioritization methodology and its ability to forecast actual time to implementation

  10. Reclamation of nuclear contaminated urban areas

    International Nuclear Information System (INIS)

    Roed, J.; Andersson, Kasper; Sandalls, J.

    1991-01-01

    From a knowledge of the distribution and levels of gamma-ray emitting radionuclides on urban surfaces, the dose rate at various locations in an urban complex can be calculated. The information produced provides a quantitative guide of where decontamination would be of greatest benefit in terms of dose reduction. The efficiency and cost of practicable reclamation and decontamination procedures has been considered and, combined with dose rate calculations before and after treatment, a strategy for reclamation of various urban contamination scenarios has been developed. The study has shown that decontamination of green areas and streets is relatively highly cost-effective in terms of dose reduction and would rank highly in a list of priorities. Roofs are shown to make a significant contribution to dose rate but decontamination of roofs is difficult and not highly cost-effective. Decontamination of walls would rank lowly in a list of priorities, since they represent large areas carrying very little contamination. (3 refs., 4 tabs.)

  11. A new nuclear safety programme for areas adjacent to Finland

    International Nuclear Information System (INIS)

    Varjoranta, T.

    1997-01-01

    The projects aimed at improving nuclear and radiation safety in areas adjacent to Finland have been compiled into one programme. The purpose of the programme is to promote activities that minimise accident risks at nuclear power plants and that improve preparedness for situations involving a risk. Nuclear materials are also to be kept under strict control. In the last few years, nuclear and radiation safety has clearly improved in areas adjacent to Finland. But work is still needed to reduce the remaining risks. The Finnish support programme comprises two very definite functions. On one hand, the programme acts as a catalyst for projects launched by the Russians themselves or by the Western partners together, and strives to pave the way for international financing projects. On the other hand, assistance is given as direct support for certain hand-picked projects. (orig.)

  12. Siemens technology transfer and cooperation in the nuclear fuel area

    International Nuclear Information System (INIS)

    Holley, H.-P.; Fuchs, J. H.; Rothenbuecher, R. A.

    1997-01-01

    Siemens is a full-range supplier in the area of nuclear power generation with broad experience and activities in the field of nuclear fuel. Siemens has developed advanced fuel technology for all types fuel assemblies used throughout the world and has significant experience worldwide in technology transfer in the field of nuclear fuel. Technology transfer and cooperation has ranged between the provision of mechanical design advice for a specific fuel design and the erection of complete fabrication plants for commercial operation in 3 countries. In the following the wide range of Siemens' technology transfer activities for both fuel design and fuel fabrication technologies are shown

  13. Large area nuclear particle detectors using ET materials

    International Nuclear Information System (INIS)

    1987-08-01

    The purpose of this SBIR Phase 1 feasibility effort was to demonstrate the usefulness of Quantex electron-trapping (ET) materials for spatial detection of nuclear particles over large areas. This demonstration entailed evaluating the prompt visible scintillation as nuclear particles impinged on films of ET materials, and subsequently detecting the nuclear particle impingement information pattern stored in the ET material, by means of the visible-wavelength luminescence produced by near-infrared interrogation. Readily useful levels of scintillation and luminescence outputs are demonstrated

  14. A geographic information system and multi criteria analysis method for site selection of spent nuclear fuel disposal; Metodologia baseada em sistemas de informacao geografica e analise multicriterio para a selecao de areas para a construcao de um repositorio para o combustivel nuclear usado

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Vivian Borges

    2009-07-01

    This thesis aims to develop a site selection methodology for the construction of final repository for the spent nuclear fuel disposal, by using geographic information systems (GIS) and multi-criteria decision analysis. Decision making processes of this kind are often complex, given the great number of space parameters to consider and also the typically conflicting opinions of the diverse stake holders. By using GIS, data from different space parameters can be quickly and reliably stored, treated and analyzed. Multi-criteria techniques allow for the incorporation of different stake holders' opinions. These tools, when jointly used, allow for the decision process to be more transparent, quick and reliable. The method developed was applied to the particular case of the state of Rio de Janeiro. Weights obtained from an expert panel and also by using the Hierarchical Analysis Method and cartographic data were combined in the GIS. The application showed that it is possible not only to select and classify areas as to their aptness for the proposed objective, but also to exclude those clearly inadequate areas, thus optimizing the selection process by reducing the search space and consequently minimizing costs and the time spent in the search. (author)

  15. Diet of the Red fox (<em>Vulpes vulpesem> in the Sibillini area (Central Apennines / Dieta della Volpe (<em>Vulpes vulpesem> nell'area dei Monti Sibillini (Appennino centrale

    Directory of Open Access Journals (Sweden)

    Paolo Boldreghini

    1991-07-01

    Full Text Available Abstract The Authors analyse the contents of 401 stomachs of foxes <em>Vulpes vulpesem> (135 of which were empty collected during the period 1971-74 in a mixed agriculture-pasture-woodland area. The frequency of occurrence of the following food categories was found: 1. Small Vertebrates (mainly rodents 72.6%; 2. Medium-sized Vertebrates (prevalently hares, domestic rabbits and domestic fowl 13.5%; 3. Invertebrates (mainly Orthoptera 7.9%; 4. Fruits: 24.8%; 5. Garbage and carrions 62.0%; 6. Grass and leaves 38.7%; 7. Unidentified material 5.6%. Small Vertebrates, Garbage and carrions, and Fruits showed highly significant seasonal variation. Garbage was found to be eaten more frequently than in any other European country. Riassunto Viene analizzato il contenuto di 401 stomaci di Volpe <em>Vulpes vulpesem> (di cui 135 vuoti raccolti nel periodo 1971-74 nelle province di Ascoli Piceno e Macerata. Le categorie alimentari più frequenti sono i piccoli Vertebrati (Roditori in prevalenza, i rifiuti e carogne, e i frutti; solo queste categorie mostrano variazioni stagionali significative. I1 consumo di carogne e rifiuti è più elevato rispetto a quello registrato in altri paesi europei.

  16. Seasonal changes of trophic niche overlap in the stone marten (<em>Martes foinaem> and the red fox (<em>Vulpes vulpesem> in a mountainous area of the Northern Apennines (N-Italy

    Directory of Open Access Journals (Sweden)

    Anna Brangi

    1995-12-01

    Full Text Available Abstract Between 1989 and 1991, 284 scats of stone marten (<em>Martes foinaem> and 642 scats of red fox (<em>Vulpes vulpesem> were collected in a 280 km² mountainous area in the northern Apennines. The scats were analyzed to identify differences between the two species' diets. The prey were grouped in 6 food categories: Fruits, Other Vegetables, Small Mammals, Other Vertebrates, Invertebrates and Garbage. Annual trophic niche was wider in the Red fox (0.62 than in the stone marten (0.53. We also found a large overlap between the two species with some small differences: Other Vertebrates, Small Mammals and Other Vegetables were more used by the Red fox, while Fruits were more used by the stone marten. Riassunto Variazioni stagionali della sovrapposizione di nicchia trofica della faina (<em>Martes foinaem> e della volpe (<em>Vulpes vulpesem> in un'area montana degli Appennini settentrionali - Tra il 1989 e il 1991 sono state raccolte 284 feci di faina (<em>Martes foinaem> e 642 feci di volpe (<em>Vulpes vulpesem> in un'area montuosa di 280 km² situata nell'Appennino settentrionale. Le feci sono state analizzate per evidenziare le eventuali differenze nella dieta delle due specie. Le singole prede sono state raggruppate in 6 categorie alimentari: Frutta, Altri Vegetali, Micromammiferi, Altri Vertebrati, Invertebrati, Rifiuti. L'ampiezza annuale della dieta è risultata maggiore nella Volpe (0,62 che non nella Faina (0,53. È stata trovata inoltre una larga sovrapposizione tra le due specie con alcune differenze nell'uso degli Altri Vertebrati, dei Micromammiferi e degli Altri Vegetali che è maggiore nella Volpe e della Frutta, maggiore nella Faina.

  17. Public perception of the nuclear area in Brazil

    International Nuclear Information System (INIS)

    Imeida, R.A. de; Lourdes Moreira, M. de

    2013-01-01

    In Brazil electricity production is proving increasingly important, the Brazilian government has recently launched the National Energy Plan, PNE-2030 which aims, among other objectives, to conclude construction of the Angra 3 plant and to deploy new nuclear power plants in the Northeast region. The Brazilian government wants to assess how the public has perceived its energy policy and what the public thinks about the nuclear issue. A public opinion survey was performed and sampling resulted in 127 respondents who were stratified by gender, age and educational level. The survey results show that although most respondents have post-graduate degrees, 64.6% are not aware of, or had never heard of PNE-2030. While 72 respondents consider nuclear energy as an alternative source of clean energy, 84 respondents did not know where the next Brazilian nuclear power plant will be built. The nuclear regulator, CNEN, is seen by 45.7% of respondents as the body that has most credibility to talk about the safety of nuclear power plants and the media most used to obtain information about the nuclear area were newspapers and discussion forums, with 52 and 50 votes respectively. These results prove the need to implement communication plans with clear and concise goals for different segments of society, since the degree of understanding differs within each segment

  18. Difusão de spins nucleares em meios porosos - uma abordagem computacional da RMN

    OpenAIRE

    Éverton Lucas-Oliveira

    2015-01-01

    A Ressonância Magnética Nuclear (RMN) é uma importante técnica empregada nas principais áreas de conhecimento, tais como, Física, Química e Medicina. Importantes trabalhos da RMN aplicada ao estudo da dinâmica de moléculas em fluidos presentes em meios porosos permitiram que esta técnica ganhasse também notoriedade na indústria do petróleo. O presente projeto é fundamentado em alguns destes trabalhos seminais, reproduzindo, através de modelos físico-computacionais, os principais efeitos físic...

  19. Y2K experiences in the nuclear material control area

    International Nuclear Information System (INIS)

    Yagi, T.; Suzuki, T.

    1999-01-01

    Though the Y2K problem was treated by each organization, it became systematic in Japan when Advanced Information and Telecommunication Society Promotion Head-quarters was established recognizing the importance and urgency of the issue. The summary of the action and some experiences concerning Y2K issues in the nuclear materials control area are presented

  20. Study of stress in nuclear area workers: silent enemy

    International Nuclear Information System (INIS)

    Martins, Maria da Penha Sanches; Vanni, Silvia Regina; Andrade, Delvonei Alves de; Sabundjian, Gaiane

    2011-01-01

    The nuclear accidents occurred in Three Mile Island, Chernobyl and Fukushima were influenced by human factors. The objective of this paper is to study about the factors that influence the level of stress of the nuclear area workers. The paper is based on theoretical assumptions on occupational stress and its manifestations. The methodology used is based on questionnaires and interviews, obtained from Martins' work published in 2008 about the study of human factors focused on research reactor operators IEA-R1, of the Instituto de Pesquisas Energeticas e Nucleares (IPEN). In that study were analyzed the accidents occurred by human failure. The results presented in this paper showed some improvements in the reactors operators' work, and health. Operational reliability and facilities safety also improved. (author)

  1. Study of stress in nuclear area workers: silent enemy

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Maria da Penha Sanches; Vanni, Silvia Regina [Centro Tecnologico da Marinha (CTMSP-SP), SP (Brazil); Andrade, Delvonei Alves de; Sabundjian, Gaiane, E-mail: delvonei@ipen.b, E-mail: gdjian@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    The nuclear accidents occurred in Three Mile Island, Chernobyl and Fukushima were influenced by human factors. The objective of this paper is to study about the factors that influence the level of stress of the nuclear area workers. The paper is based on theoretical assumptions on occupational stress and its manifestations. The methodology used is based on questionnaires and interviews, obtained from Martins' work published in 2008 about the study of human factors focused on research reactor operators IEA-R1, of the Instituto de Pesquisas Energeticas e Nucleares (IPEN). In that study were analyzed the accidents occurred by human failure. The results presented in this paper showed some improvements in the reactors operators' work, and health. Operational reliability and facilities safety also improved. (author)

  2. ENSAR, a Nuclear Science Project for European Research Area

    NARCIS (Netherlands)

    Turzó, Ketel; Lewitowicz, Marek; Harakeh, Muhsin N.

    2015-01-01

    During the period from September 2010 to December 2014, the European project European Nuclear Science and Applications Research (ENSAR) coordinated research activities of the Nuclear Physics community performing research in three major subfields: Nuclear Structure, Nuclear Astrophysics, and Nuclear

  3. Large area avalanche MRS-photodiodes for nuclear spectroscopy

    Energy Technology Data Exchange (ETDEWEB)

    Ermalitski, F A; Zalesski, V B

    1996-12-31

    Problems of application of avalanche photodiodes (APD) in readout systems of nuclear spectrometers are considered. APD`s with a large sensitive area of a diameter 1-5 mm and a high multiplication coefficient 200-1000 are created. MPS-photodiodes provide for the energy resolution 80% at temperature 231 K for detecting gamma-quanta with energy 662 keV. 4 refs.

  4. Wide-area monitoring to detect undeclared nuclear facilities

    International Nuclear Information System (INIS)

    Wogman, N.

    1994-09-01

    The International Atomic Energy Agency (IAEA) is committed to strengthening and streamlining the overall effectiveness of the IAEA safeguards system. The IAEA is investigating the use of environmental monitoring techniques to strengthen its capability to detect undeclared nuclear activities. The IAEA's Program 93+2 Initiative has been established to develop, test, and assess strengthening techniques and measures. Some of the techniques have been validated and are being implemented during routine safeguards inspections. The effectiveness of other techniques is being studied as a part of extensive field trials conducted at nuclear facilities of various Member States during 1993 and 1994. Proposals based on the results of these investigations and recommendations for new safeguards activities are expected to be presented to the March 1995 Board of Governors Meeting. The techniques in use or under study during IAEA field trials address various types of environmental monitoring applications as outlined under Program 93+2's Task 3, Environmental Monitoring Techniques for Safeguards Applications, namely, the use of short-range monitoring during inspections and visits to investigate sites of possible undeclared activities. With the exception of wide-area water sampling in Iraq, the use of long-range monitoring, in the absence of any indication of undeclared nuclear activities, remains largely unexamined by the IAEA. The efficacy of long-range monitoring depends on the availability of mobile signature isotopes or compounds and on the ability to distinguish the nuclear signatures from background signals and attributing them to a source. The scope of this paper is to provide technical information to the International Atomic Energy Agency (IAEA) on possible wide-area survey techniques for the detection of undeclared nuclear activities. The primary focus is the detection of effluents from reprocessing activities

  5. Analysis of cognitive structure of nuclear energy focusing on inhabiting areas, genders, and knowledge

    International Nuclear Information System (INIS)

    Kimura, Hiroshi; Suzuki, Atsuyuki; Furuta, Kazuo

    2003-01-01

    The purpose of this research is to clarify people's cognitive structure of nuclear energy, and to analyze how the cognitive structure varies with inhabiting areas, genders, and knowledge of nuclear energy. For this purpose, we carried out questionnaire survey of perception of nuclear energy in the urban areas and nuclear power plants (NPP) siting areas. After collecting data, we defined 8 categories in terms of respondents' inhabiting areas, genders, and knowledge, and applied factor analysis to each category's data. Consequently, we found 4 cognitive factors of nuclear: 'trust in the authorities', 'utility of nuclear power generation', 'benefit for NPP siting areas', and 'risk perception about nuclear technology', regardless of the respondents' inhabiting areas, genders, and knowledge. In addition, when the respondents assess many perceptions of nuclear energy, respondents living in urban areas tend to regard 'trust in the authorities' as important, while respondents living in NPP siting areas tend to take into consideration of risk perception about nuclear technology'. (author)

  6. Fattori influenzanti la distribuzione del Daino (<em>Dama damaem> in un'area dell'Appennino settentrionale

    Directory of Open Access Journals (Sweden)

    Enrico Merli

    2003-10-01

    Full Text Available Abstract Factors affecting the distribution of fallow deer (<em>Dama damaem> in an area of the northern Apennines (Italy A wild population of fallow deer (<em>Dama damaem>, originated in the Seventies from accidental release, has been monitored from 1996 to 2000 in the hilly and mountainous habitat of the Pavia county (Northern Apennines. Sightings and signs of presence on 34 transects (total length of 163.2 km were collected twice a year in spring. The distribution of the species in the study area (732 km² was defined on the basis of a grid of 215 4-km² sample units. The species occupied the 28% and 22% of the study area respectively in 1997 and 2000. The relative abundance of the population, estimated as mean of sightings-signs/km varied from 0.50 (S.E. = 0.27 in 1997 to 0.03 (S.E. = 0.03 in 1998. Discriminant Function and Logistic Regression Analysis were performed to investigate the influence of 23 habitat variables on the distribution of fallow deers in 1997. Both statistical techniques identified the length of the edge between woods and crops as the main variable affecting fallow deer distribution. The analysis also pointed out that the area potentially suitable for the species raised up to 388 km² (53.0% of the study area. Riassunto Una popolazione di Daino presente nella zona collinare e montana della provincia di Pavia (732 km², originatasi da una fuga di animali da un allevamento negli anni 70, è stata monitorata dal 1996 al 2000. Per la definizione della distribuzione è stato predisposto un sistema di 34 transetti (163,2 km in totale percorsi 2 volte l'anno, in primavera, annotando e mappando tutti i segni di presenza e le osservazioni dirette della specie. L'area di studio è quindi stata suddivisa in maglie quadrate di 400 ha ciascuna (Unità di Campionamento, a cui è stata associata, per ogni anno la presenza o l'assenza della specie. La superficie interessata dalla

  7. Catawba Nuclear Station and surrounding area, Lake Wylie, South Carolina

    International Nuclear Information System (INIS)

    Fritzsche, A.E.

    1984-10-01

    An aerial gamma survey was conducted over the Catawba Nuclear Station, located near Lake Wylie, South Carolina, during the period 31 May through 7 June 1984. The survey covered a 260-square-kilometer (100-square-mile) area centered on the Station. A contour map of the terrestrial gamma exposure rate plus cosmic exposure rate at the 1-meter level was prepared and overlaid on an aerial photograph and a USGS topographic map of the area. The terrestrial plus cosmic gamma exposure rate ranged from 3.7 microroentgens per hour (μR/h), the cosmic level over Lake Wylie, to 17.4 μR/h just east of the Catawba River below the dam site. A search of the gamma data showed no man-made gamma emitters in the survey area. Soil samples and ion chamber measurements were obtained at four locations on the ground to support the aerial data. 8 references, 4 figures, 3 tables

  8. Smoke production from multiple nuclear explosions in nonurban areas

    International Nuclear Information System (INIS)

    Small, R.D.; Bush, B.W.

    1985-01-01

    The amount of smoke that may be produced by wildland or rural fires as a consequence of a large-scale nuclear exchange is estimated. The calculation is based on a compilation of rural military facilities, identified from a wide variety of unclassified sources, together with data on their geographic positions, surrounding vegetation (fuel), and weather conditions. The ignition area (corrected for fuel moisture) and the amount of fire spread are used to calculate the smoke production. The results show a substantially lower estimated smoke production (from wildland fires) than in earlier nuclear winter studies. The amount varies seasonally and at its peak is less by an order of magnitude than the estimated threshold level necessary for a major attenuation of solar radiation. 32 references, 6 figures, 2 tables

  9. Local-area networks in nuclear physics (survey)

    International Nuclear Information System (INIS)

    Foteev, V.A.

    1987-01-01

    The design fundamentals, comparative characteristics, and possibilities of local-area networks as applied to physics experiments are examined. The example of Ethernet is used to explain the operation of local networks, and the results of a study of their functional characteristics are presented. Examples of operational local networks in nuclear physics research and atomic engineering are given: the Japan Research Institute of Atomic Energy, the University of California, and Los Alamos National Laboratory; atomic power plant control in Japan; DECnet and Fastbus; network developments at the Siberian Branch of the Academy of Sciences of the USSR and at the Laboratory of Neutron Physics of the Joint Institute for Nuclear Research; and others. It is shown that local networks are important means that considerably increase productivity in data processing

  10. Radioecological investigations of the Bilibino Nuclear Power Station area

    Energy Technology Data Exchange (ETDEWEB)

    Emelyanova, L.; Neretin, L. [Moscow State Univ. (Russian Federation). Geographical Faculty]|[Russian Academy of Sciences, Moscow (Russian Federation). P.P. Shirshov Inst. of Oceanology

    1995-12-31

    The landscape structure of the territory and the current radioactive state of ecosystems in the vicinity of Bilibino Nuclear Power Station (Western Chukotka Peninsula) within the area of its potential influence on the environment were studied in 1989--1990. Accumulation of strontium-90 and cesium-137 radionuclides in several key biological members of the ecosystems has been analyzed. Maximal weighted content of cesium-137 was revealed in mountain pine cones (Pinus pumila) -- 9,200 Bq/kg.d.w., cowberry fruits have demonstrated considerable contamination by strontium and cesium isotopes. The purification of first two components of food chain ``lichen-reindeer-man`` was pointed out in the investigated area. Besides the chemical characteristics, visual biological anomalies of biocomponents nearby the Bilibino NPS ecosystems are observed. On the basis of field radioecological investigations and future work, programs were developed for the conditions of the Bilibino Nuclear Power Station area. This experience could be applied to the researches of radioactive contamination in ecosystems of other northern territories.

  11. Robot for Investigations and Assessments of Nuclear Areas

    International Nuclear Information System (INIS)

    Kanaan, Daniel; Dogny, Stephane

    2015-01-01

    RIANA is a remote controlled Robot dedicated for Investigations and Assessments of Nuclear Areas. The development of RIANA is motivated by the need to have at disposal a proven robot, tested in hot cells; a robot capable of remotely investigate and characterise the inside of nuclear facilities in order to collect efficiently all the required data in the shortest possible time. It is based on a wireless medium sized remote carrier that may carry a wide variety of interchangeable modules, sensors and tools. It is easily customised to match specific requirements and quickly configured depending on the mission and the operator's preferences. RIANA integrates localisation and navigation systems. The robot will be able to generate / update a 2D map of its surrounding and exploring areas. The position of the robot is given accurately on the map. Furthermore, the robot will be able to autonomously calculate, define and follow a trajectory between 2 points taking into account its environment and obstacles. The robot is configurable to manage obstacles and restrict access to forbidden areas. RIANA allows an advanced control of modules, sensors and tools; all collected data (radiological and measured data) are displayed in real time in different format (chart, on the generated map...) and stored in a single place so that may be exported in a convenient format for data processing. This modular design gives RIANA the flexibility to perform multiple investigation missions where humans cannot work such as: visual inspections, dynamic localization and 2D mapping, characterizations and nuclear measurements of floor and walls, non destructive testing, samples collection: solid and liquid. The benefits of using RIANA are: - reducing the personnel exposures by limiting the manual intervention time, - minimizing the time and reducing the cost of investigation operations, - providing critical inputs to set up and optimize cleanup and dismantling operations. (authors)

  12. Robot for Investigations and Assessments of Nuclear Areas

    Energy Technology Data Exchange (ETDEWEB)

    Kanaan, Daniel; Dogny, Stephane [AREVA D and S/DT, 30206 Bagnols sur Ceze (France)

    2015-07-01

    RIANA is a remote controlled Robot dedicated for Investigations and Assessments of Nuclear Areas. The development of RIANA is motivated by the need to have at disposal a proven robot, tested in hot cells; a robot capable of remotely investigate and characterise the inside of nuclear facilities in order to collect efficiently all the required data in the shortest possible time. It is based on a wireless medium sized remote carrier that may carry a wide variety of interchangeable modules, sensors and tools. It is easily customised to match specific requirements and quickly configured depending on the mission and the operator's preferences. RIANA integrates localisation and navigation systems. The robot will be able to generate / update a 2D map of its surrounding and exploring areas. The position of the robot is given accurately on the map. Furthermore, the robot will be able to autonomously calculate, define and follow a trajectory between 2 points taking into account its environment and obstacles. The robot is configurable to manage obstacles and restrict access to forbidden areas. RIANA allows an advanced control of modules, sensors and tools; all collected data (radiological and measured data) are displayed in real time in different format (chart, on the generated map...) and stored in a single place so that may be exported in a convenient format for data processing. This modular design gives RIANA the flexibility to perform multiple investigation missions where humans cannot work such as: visual inspections, dynamic localization and 2D mapping, characterizations and nuclear measurements of floor and walls, non destructive testing, samples collection: solid and liquid. The benefits of using RIANA are: - reducing the personnel exposures by limiting the manual intervention time, - minimizing the time and reducing the cost of investigation operations, - providing critical inputs to set up and optimize cleanup and dismantling operations. (authors)

  13. Perry Nuclear Power Plant Area/Equipment Temperature Monitoring Program

    International Nuclear Information System (INIS)

    McGuire, L.L.

    1991-01-01

    The Perry Nuclear Power Plant Area/Equipment Temperature Monitoring Program serves two purposes. The first is to track temperature trends during normal plant operation in areas where suspected deviations from established environmental profiles exist. This includes the use of Resistance Temperature Detectors, Recorders, and Temperature Dots for evaluation of equipment qualified life for comparison with tested parameters and the established Environmental Design Profile. It also may be used to determine the location and duration of steam leaks for effect on equipment qualified life. The second purpose of this program is to aid HVAC design engineers in determining the source of heat outside anticipated design parameters. Resistance Temperature Detectors, Recorders, and Temperature Dots are also used for this application but the results may include design changes to eliminate the excess heat or provide qualified equipment (cable) to withstand the elevated temperature, splitting of environmental zones to capture accurate temperature parameters, or continued environmental monitoring for evaluation of equipment located in hot spots

  14. Classification of areas considering equivalent doses due to radon, indoors in the Institute of Chemical, Biological, Radiological and Nuclear Defense (IDQBRN); Classificação de áreas considerando as doses equivalentes devido a radônio, em ambientes fechados no Instituto de Defesa Química, Biológica, Radiológica e Nuclear (IDQBRN)

    Energy Technology Data Exchange (ETDEWEB)

    Arbach, Mayara N.; Soares, Alexandre B., E-mail: mayaraarbach@gmail.com, E-mail: alexandrebaso@globo.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Alves, Rex N.; Cardoso, Domingos D’ O.; Júnior, Walter José. G., E-mail: rexnazare@ime.eb.br, E-mail: domin@ime.eb.br, E-mail: walter_guimaraes@ime.eb.br [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The human being is subject to several sources of natural radiation, mainly radon, belonging to the radioactive decay chain of uranium and thorium. At the study site, approximately 3.3 tons of uranium with natural concentration are stored. This fact, which generated the concern about the occupational dose levels of the IOE's of the facility, because its effective dose will have the increase due to the equivalent dose from the exposure to radon. The measurements took place: in the uranium deposit; in an adjoining room and at the control point. According to the norm CNEN - NN 3.01 and considering the existing radon concentrations in the three environments it was concluded that: the uranium deposit room is considered a controlled area; the control point a free area and the contiguous room, a supervised area.

  15. The planning of areas near nuclear power stations

    International Nuclear Information System (INIS)

    1977-01-01

    During the past five years national physical planning has been initiated by the Swedish Parliament. Guidelines have been given to the communities how to consider national interests when drawing up local planning and how to produce maps and descriptions of the planning. For the planning of the areas near the nuclear power stations the municipalities have certain guidelines from The Nuclear Power Inspectorate and The National Institute of Radiation Protection. It is advised to keep a low population density near the power plants, to avoid the type of harbour or industry which could have disturbing effects on the power plant and also to avoid to concentrate people, who are difficult to move from the area in case of an accident (i.e., homes for old people, maternity homes and prisons). The plants on the East Coast, Forsmark and Oskarshamn, are located in wooded areas with a very low population density. On the West Coast, near Ringhals and Barsebaeck, the population density is higher, and there is one village with about 2,000 inhabitants, situated at a distance of two (2) km from the Ringhals power plant. The Control Boards are now reluctant to concentrate more people in this village, where schools and shops were earlier planned for 3,000 inhabitants. The building activity near power plants is regulated by law. New buildings are prohibited within a distance of two (2) km from the plants. Some exeptions can be granted by the County Administrative Board after guidance from the Central Board. In a zone reaching 10 kilometers from the power plants there are no regulations by law about new buildings, except the earlier mentioned guidelines from the Central Boards to maintain a low population. (L.E.)

  16. Spotlight census of the red fox (<em>Vulpes vulpesem> and the domestic cat (<em>Felis catusem> in three sample areas of the Marches region (Central Italy / Censimento notturno di Volpe (<em>Vulpes vulpesem> e di Gatto domestico (<em>Felis catusem> in tre aree campione delle Marche

    Directory of Open Access Journals (Sweden)

    Massimo Pandolfi

    1991-07-01

    Full Text Available Abstract In order to evaluate the density of the red fox and of the domestic cat, 55 transects were made from 1986 to 1989 using spotlight census method in three sample areas. The mean density of foxes agreed substantially with its biological cycle and the hightes values (2.01 foxes/km² in spring and 4.3 foxes/km² in winter were recorded in the study area with the better natural characteristics. Foxes selected the shrub woodland (macchia all year round, the inhabited area in spring. The domestic cat was widely spread and abundant, and selected especially inhabited areas where the density varied from 4.27 cats/km² (in winter to 12.42 cat/km² (in spring. Riassunto Dal 1986 al 1989, con il metodo dei percorsi notturni con fari, sono stati effettuati complessivamente 55 conteggi in tre aree campione per valutare la densità della Volpe (<em>Vulpes vulpesem> e del Gatto domestico (<em>Felis catusem> nonché le loro preferenze ambientali limitatamente ad una zona campione. Per la Volpe le densità medie rilevate sono sostanzialmente in accordo con il ciclo biologico della specie e quelle più elevate (2,O1 volpi/km² in primavera e 4,3 volpi/km² in inverno sono state registrate nella zona campione con maggior presenza di boschi ed aree incolte. La Volpe seleziona le zone con vegetazione "di macchia" in ogni periodo dell'anno, e le aree abitate in primavera. Per il Gatto domestico le densità rilevate evidenziano la presenza di una diffusa ed abbondante popolazione. La specie mostra una spiccata preferenza per le aree abitate dove raggiunge densità di 4,27 individui/km² e 12,42 individui/km² in inverno e primavera rispettivamente.

  17. Drilling in areas subject to environmental protection; A perfuracao em area de protecao ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Mendonca, Ricardo Teixeira; Guimaraes, Antimio Santos [PETROBRAS, XX (Brazil). Distrito de Perfuracao do Nordeste. Div. Tecnica; Santana, Manoel Messias de [PETROBRAS, XX (Brazil). Regiao de Producao do Nordeste. Setor de Seguranca Industrial

    1990-12-31

    This paper presents the practices developed for pollution control in areas subject to environmental protection. This well drilling operation was carried out in the Municipality of Marechal Deodoro, in the State of Alagoas, in locality named Massagueira. We stress the preventive methods for liquid and solid effluent generation and the use of Closed Fluid System or Anti-Dike System. (author) 3 figs.

  18. Issues related to EM management of DOE spent nuclear fuel

    International Nuclear Information System (INIS)

    Abbott, D.G.; Abashian, M.S.; Chakraborti, S.; Roberson, K.; Meloin, J.M.

    1993-07-01

    This document is a summary of the important issues involved in managing spent nuclear fuel (SNF) owned by the Department of Energy (DOE). Issues related to civilian SNF activities are not discussed. DOE-owned SNF is stored primarily at the Hanford Site, Idaho National Engineering Laboratory (INEL), Savannah River Site (SRS), Oak Ridge National Laboratory (ORNL), and West Valley Demonstration Project. Smaller quantities of SNF are stored at Brookhaven National Laboratory, Sandia National Laboratories, and Los Alamos National Laboratory (LANL). There is a wide variety of fuel types, including both low and high enrichment fuels from weapons production, DOE reactors, research and development programs, naval programs, and universities. Most fuel is stored in pools associated with reactor or reprocessing facilities. Smaller quantities are in dry storage. Physical conditions of the fuel range from excellent to poor or severely damaged. An issue is defined as an important question that must be answered or decision that must be made on a topic or subject relevant to achieving the complimentary objectives of (a) storing SNF in compliance with applicable regulations and orders until it can be disposed, and (b) safely disposing of DOE's SNF. The purpose of this document is to define the issues; no recommendations are made on resolutions. As DOE's national SNF management program is implemented, a system of issues identification, documentation, tracking, and resolution will be implemented. This document is an initial effort at issues identification. The first section of this document is an overview of issues that are common to several or all DOE facilities that manage SNF. The common issues are organized according to specific aspects of spent fuel management. This is followed by discussions of management issues that apply specifically to individual DOE facilities. The last section provides literature references

  19. Investigation for the ecology in areas nearby a nuclear facility

    International Nuclear Information System (INIS)

    Qin Suyun; Zhou Caiyun; Zhou Zirong; Chen Wenying; Zhen Zhijiang

    1995-03-01

    Studies were undertaken for the general ecological environment around the evaporating ponds and Gobi desert areas receiving the low and very low level radioactive waste water from a nuclear facility and for the transport of radionuclides in food chains were undertaken. On basis of obtained results the following conclusions were made: (1) In consequence of controlled releases of low level radioactive waste water, a steady specific ecosystem had formed. (2) Concentration of radionuclides in sediments, soils, terrestrial and aquatic wild plants and animals, agricultural products irrigated with very low level radioactive waste water, and tissues of sheep pastured in very low level radioactive water drainage areas, were higher significantly than that of non-contaminated areas. (3) Radioactive waste water discharging might result in potential exposure to members of residents. The critical radionuclide was 137 Cs, and the critical pathway was ingesting polluted waterfowls of evaporating pond. On basis of very conservative assessing the maximum intake of 137 Cs of individual of local resident was 1.0 x 10 4 Bq·a -1 corresponding to 50% of ALI of individual of population. Maximum amount of redistribution of radioactive material as a result of carrying by migrating birds under extreme conditions might be about 10 7 Bq·a -1 . (16 refs., 9 tabs., 1 fig.)

  20. Investigation for the ecology in areas nearby a nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Suyun, Qin; Caiyun, Zhou; Zirong, Zhou; Wenying, Chen; Zhijiang, Zhen [Ministry of Nuclear Industry, Taiyuan, SX (China). Inst. of Radiation Protection

    1995-03-01

    Studies were undertaken for the general ecological environment around the evaporating ponds and Gobi desert areas receiving the low and very low level radioactive waste water from a nuclear facility and for the transport of radionuclides in food chains were undertaken. On basis of obtained results the following conclusions were made: (1) In consequence of controlled releases of low level radioactive waste water, a steady specific ecosystem had formed. (2) Concentration of radionuclides in sediments, soils, terrestrial and aquatic wild plants and animals, agricultural products irrigated with very low level radioactive waste water, and tissues of sheep pastured in very low level radioactive water drainage areas, were higher significantly than that of non-contaminated areas. (3) Radioactive waste water discharging might result in potential exposure to members of residents. The critical radionuclide was {sup 137}Cs, and the critical pathway was ingesting polluted waterfowls of evaporating pond. On basis of very conservative assessing the maximum intake of {sup 137}Cs of individual of local resident was 1.0 x 10{sup 4} Bq{center_dot}a{sup -1} corresponding to 50% of ALI of individual of population. Maximum amount of redistribution of radioactive material as a result of carrying by migrating birds under extreme conditions might be about 10{sup 7} Bq{center_dot}a{sup -1}. (16 refs., 9 tabs., 1 fig.).

  1. Fault diagnosis method for area gamma monitors in Nuclear Facilities

    International Nuclear Information System (INIS)

    Srinivas Reddy, P.; Amudhu Ramesh Kumar, R.; Geo Mathews, M.; Amarendra, G.

    2016-01-01

    Area Gamma Monitors (AGM) using Geiger-Muller (GM) counter are deployed in nuclear facilities for detection of gamma radiation. The AGMs display the dose rate locally and in Data Acquisition System (DAS) at central monitoring station. It also provides local visual and audio alarms in case of dose rate exceeding alarm set point. Regular surveillance checking, testing and calibration of AGMs are mandatory as per safety guidelines. This paper describes quick testing the AGMs without using radioactive source. The four point High Voltages (HV) and Discriminator Bias (DB) voltage characteristics are used to diagnose the state of health of GM counter. The profiles of HV and DB voltage are applied during testing of the AGMs

  2. On the optimum area-balanced filters for nuclear spectroscopy

    International Nuclear Information System (INIS)

    Ripamonti, G.; Pullia, A.

    1996-01-01

    The minimum noise area-balanced (A-B) filters for nuclear spectroscopy are disentangled in the sum of two optimized individual filters. The former is the unipolar finite cusp filter, used for pulse amplitude estimation but affected by baseline shift errors, the latter is a specific filter used for baseline estimation. Each of them is optimized so as to give the minimum noise in the estimation of the pulse amplitude or of its baseline level. It is shown that double optimisation produces an overall optimum filter exhibiting a total noise V 2 n equal to the sum of the noises V 2 n1 and V 2 n2 exhibited by each filter individually. This is a consequence of the orthogonality of the individual filter weight-functions in a function space where the norm is defined as √(V 2 n ). (orig.)

  3. Social perception and public information in the nuclear area

    International Nuclear Information System (INIS)

    Oltra, Christian

    2007-01-01

    The investigation in perception of the risk, the studies on perception of the nuclear risk in Spain and Public Information and the social acceptance of nuclear energy in Spain are discussed in this paper

  4. ALTM system in Amazonian forest areas; Sistema ALTM em areas da Floresta Amazonica

    Energy Technology Data Exchange (ETDEWEB)

    Sallem Filho, Silas; Bonatto, Amarildo [Esteio Engenharia e Aerolevantamentos S.A., Curitiba, PR (Brazil)

    2005-07-01

    Airborne Laser Scanning provides faster and more accurate Digital Elevation Model and Digital Terrain Model tasks compared to conventional photogrammetry. The system generates Laser pulses towards the terrain, perpendicular to the flight line, scanning the terrain surface and recording the distances from the sensor to the ground for each pulse. The main characteristics of the system is the measurement of the first and the last return for each pulse, allowing the objects identification that are above the ground as, for example, vegetation. With this capability it is possible the determination of volumes and biomass estimate, besides the virtual removal of vegetation covering. The Digital Terrain Models are used for Digital Ortho photos rectification and to obtain contour lines for topography maps. The correct points classification according the elevation, allows the representation of the terrain with larger amount of points than the stereo plotting, in areas densely vegetated where the operator esteems the height of the vegetable covering to interpret the terrain. Some additional products, as hypsometric images and intensity images helps in the identification of features on pipeline projects as well as the obtaining of the obstacles height. (author)

  5. Lessons from other areas of medical imaging - nuclear medicine

    International Nuclear Information System (INIS)

    McCready, V.R.

    1981-01-01

    Ultrasound and nuclear medicine are similar in that they both have been developed for clinical use in the past decade. Unlike X-ray techniques the success or failure of ultrasound and nuclear medicine depend more upon both the operator and the method of display. Since both ultrasound and nuclear medicine use relatively complicated methods of gathering and displaying information some of the lessons learnt during the development of nuclear medicine can be equally applied to ultrasound techniques. (Auth.)

  6. Chemical Composition of Essential Oils of <em>Litsea cubebaem> Harvested from Its Distribution Areas in China

    Directory of Open Access Journals (Sweden)

    Qinqin Cui

    2012-06-01

    Full Text Available <em>Litsea cubebaem> (Lour. Pers. is a promising industrial crop with fruits rich in essential oils. The chemical composition of essential oils of <em>L. cubebaem> (EOLC were determined for fruits harvested from eight regions in China. The overall essential oil content, obtained by hydrodistillation and analyzed by gas chromatography–mass spectrometry (GC-MS, ranged from 3.04% to 4.56%. In total, 59 compounds were identified, the dominant components being monoterpenes (94.4–98.4%, represented mainly by neral and geranial (78.7–87.4%. D-Limonene was unexpectedly a lesser constituent (0.7–5.3% in fruits, which differed from previous reports (6.0–14.6%. Several components were only detected in certain regions and compounds such as <em>o>-cymene and eremophilene have never before been reported in EOLC. These results demonstrate significant regional variation in the chemical composition of EOLC. This investigation provides important information with regard to the bioactivity, breeding work and industrial applications of <em>L. cubebaem>.

  7. Fire and EMS Districts, These layers show the geographic area of each Fire and EMS responder contained in the County of Polk, Wisconsin., Published in 2006, 1:2400 (1in=200ft) scale, Polk County Government.

    Data.gov (United States)

    NSGIC Local Govt | GIS Inventory — Fire and EMS Districts dataset current as of 2006. These layers show the geographic area of each Fire and EMS responder contained in the County of Polk, Wisconsin..

  8. Assessment of soil contamination in area surrounding Tuwaitha nuclear facilities

    International Nuclear Information System (INIS)

    Al-Taii, A.A.F.; AI-Jobori, S.H.; Al-Maadhidi, J.F.

    2012-01-01

    The wide spread looting of the Tuwaitha Nuclear Facilities as well as damaging of some buildings in 2003, had offered possibilities of contamination of soil environment inside the Site. The objective of the present work was to investigate soil contamination to help in future decontamination programs. A total of 25 soil surface samples (including one reference sample) covered different locations in the Site were collected in March 2011. High purity Ge detector was used for gamma spectrometry of soil samples. Data of total and spectral gamma for U series, Th series, 40 K and 137 Cs are presented. Slight variations were observed in specific activity of the U series 214 Bi or 214 Pb and 226 Ra among measured soil samples where the range was 10.3-12.7 for 214 Bi as compared with 12.2-33.4 Bq/kg for 226 Ra. Values of both 214 Bi and 226 Ra are in the range of reference sample specific activity indicating that no evidence of contamination had occurred in the investigated area. Results of activity concentrations of thorium series 228 Ac or 208 Tl, 212 Pb, and 212 Bi are in the range of reference sample and close to those values given worldwide for natural uranium in soil. The levels of 40 K in soil are within the natural abundance of this isotope in the soil where the range was 207.6-266.1 with 220.3 Bq/kg for the reference sample. On the other hand, 137 Cs specific activities showed great variation among measured samples. The minimum value for 137 Cs was 0.6 and the maximum 7.6 compared with 0.8 Bq/kg for the control soil sample. The non-uniformity of radioactivity concentration of 137 Cs suggest the presence of contamination in some locations although this level is considered as an acceptable level and no hazardous effect will be generated.

  9. The quality of the diet of foxes (<em>Vulpes vulpesem> in a Mediterranean coastal area (Central Italy / Qualità della dieta della Volpe <em>Vulpes vulpesem> in un'area costiera mediterranea

    Directory of Open Access Journals (Sweden)

    Claudio Cavani

    1991-07-01

    Full Text Available Abstract The diet of foxes in the Natural Park of Maremma includes essentially <em>Juniperus> fruits and Arthropods, mainly Coleoptera and Orthoptera. These components were analysed in order to value their chemical nutritive. The following parameters were determined: proximate analysis (crude protein Nx6.25; ether extract; crude fibre; ash, aminoacids, and mineral contents. <em>Juniperus> berries are characterized by a low crude protein and ash content (1.83 and 2.75% on dry matter while the level of fibrous constituents, expressed in terms of crude fibre, occurs in relatively high quantities (30.8% on dry matter. By contrast, Orthoptera and Coleoptera show high crude protein content (67.3 and 57.8% on dry matter of average nutritive value (chemical score 0.52 and 0.51. The ash level is 68.8 and 76.6 g/kg on dry matter, with high phosphorus, iron and zinc content. <em>Juniperus> berries are a feed component of moderate energy level, while Arthropods seem to be an important mineral and protein source. Riassunto La dieta della Volpe (<em>Vulpes vulpesem> nel Parco Naturale della Maremma è costituita essenzialmente da frutti di Ginepro e da Artropodi, soprattutto Coleotteri ed Ortotteri. Allo scopo di fornire una valutazione delle caratteristiche chimico-nutritive di questi componenti alimentari, sono stati analizzati diversi campioni della dieta. Sono stati determinati i parametri riguardanti le analisi standard per gli alimenti di uso zootecnico, il contenuto in aminoacidi e in elementi minerali. I frutti di Ginepro sono caratterizzati da uno scarso tenore in proteine grezze e in ceneri (1,83 e 2,75% della sostanza secca, mentre il contenuto in costituenti fibrosi, espressi in termini di fibra grezza, risulta relativamente elevato (30,8% della sostanza secca. Gli Ortotteri ed i Coleotteri mostrano invece un considerevole contenuto in proteine grezze (67,3 e 57,8% della sostanza secca, di valore

  10. Position paper on main areas of nuclear chemistry research and application

    International Nuclear Information System (INIS)

    2001-01-01

    Nuclear chemistry, with its specialized areas of nuclear chemistry, radiochemistry, and radiation chemistry, mainly covers these fields: basic research in nuclear chemistry; actinide chemistry; radioanalysis; nuclear chemistry in the life sciences, geosciences, and cosmic chemistry; radiotracers in technology; nuclear power technology; nuclear waste management; tritium chemistry in fusion technology, and radiation protection and radioecology. In the more than one hundred years of history of this branch of science and technology, which was opened up by the discovery of radioactivity and of the radioelements, pioneering discoveries and developments have been made in many sectors. Far beyond the confines of this area of work, they have achieved overriding importance in applications in many fields of technology and industry and in the life sciences. Research and application in nuclear chemistry continue to be highly relevant to society, ecology, and the economy, and the potential of science and technology in this field in Germany is acknowledged internationally. In the light of this vast area of activity, and against the need to maintain competence in nuclear chemistry for the use of nuclear power, irrespective of the status of this continued use in Germany, nuclear chemistry is indispensable to the solution of future problems. The Nuclear Chemistry Group of the Gesellschaft Deutscher Chemiker therefore uses this position paper to draw attention to the urgent need to keep up and further advance nuclear chemistry applications in a variety of areas of science and technology, also as a public duty of thorough education and research. (orig.) [de

  11. Espansione del Cinghiale (<em>Sus scrofaem> e danni alle coltivazioni in un'area delle Prealpi occidentali

    Directory of Open Access Journals (Sweden)

    Anna Brangi

    2003-10-01

    Full Text Available Abstract Wild boar (<em>Sus scrofaem> spreading and crop damage in an area of western Prealps We analysed the agricultural damage reports from 1986 to 1996 to evidence the wild boar distribution in Biella province and the pattern of land occupancy. These reports were yearly divided and mapped for the single municipalities to obtain a picture of the range variations in the time. From the same reports we calculated three indexes of the importance of the Wild boar damages: the damaged surface for each municipality, its percentage value on the surface of each municipality and the occurrence of damages for each municipality. During the study period, we observed a dramatic increase of the number of municipalities affected by wild boar damages and of the species range. The yearly damaged surface grew over 25 times too. The Discriminant Function Analysis carried out between damaged and undamaged municipalities correctly classified 78,1% of total cases by three variables: mixed woods, pastures and dry crops, the second one being the most important. The Multiple Regression Analysis of the damages occurrence vs. habitat variables explained 77,3% of independent variable variance by five variables, which entered the model. The trend analysis, carried out by the seasonal regression, using the surface and the occurrence of damages, evidenced a marked seasonality of the damages and a stability trend, after an initial positive trend. Riassunto Per evidenziare la distribuzione del Cinghiale in provincia di Biella e le modalità d'occupazione del territorio nel corso degli anni, sono state utilizzate le denunce dei danni pervenute all Amministrazione provinciale dal 1986 al 1996. Queste sono state ripartite per comune e mappate anno per anno per fornire una rappresentazione delle variazioni di areale nel corso del tempo. Dalle stesse denunce di danni e per lo stesso arco di tempo sono stati calcolati tre indici

  12. Selection of Possible Candidate Area for Nuclear Power Plant in Johor, Malaysia

    International Nuclear Information System (INIS)

    Nor Afifah Basri; Ahmad Termizi Ramli

    2012-01-01

    Nuclear power is considered as one of the best option for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation, commissioning the first nuclear power plant needs tremendous effort in various aspects. Site selection is one of important step in nuclear power plant commissioning process. This paper proposes candidate sites for nuclear power plant in Mersing, Kota Tinggi, Muar and Batu Pahat district in Johor, Malaysia. The candidate selection process uses the IAEA document and AELB guideline as main reference, supported by site selection procedure by various countries. MapInfo Professional software was used to simulate the selection process for candidate areas for the nuclear power plant. This paper concluded that Tenggaroh and Jemaluang area are the most suitable area for nuclear power plant facilities in Johor, Malaysia. (Author)

  13. Selection of possible candidate area for nuclear energy facility in Johor, Malaysia

    International Nuclear Information System (INIS)

    Nor Afifah Basri; Ahmad Termizi Ramli

    2012-01-01

    Nuclear power is considered as one of the best option for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation, commissioning the first nuclear power plant needs tremendous effort in various aspects. Site selection is one of important step in nuclear power plant commissioning process. This paper proposes candidate sites for nuclear power plant in Mersing, Kota Tinggi, Muar and Batu Pahat district in Johor, Malaysia. The candidate selection process uses the IAEA document and AELB guideline as main reference, supported by site selection procedure by various countries. MapInfo Professional software was used to stimulate the selection process for candidate areas for the nuclear power plant. This paper concluded that Tenggaroh and Jemaluang area are the most suitable area for nuclear power plant facilities in Johor, Malaysia. (Author)

  14. Public perception of the nuclear area in Brazil

    International Nuclear Information System (INIS)

    Almeida, Renata Araujo de; Moreira, Maria de Lourdes

    2013-01-01

    Nowadays human dependence on electricity is increasing and as a result access to energy resources and / or energy, is becoming a priority in most countries, both developed and developing. With this comes the need for government involvement in the planning and expansion of energy activities, especially when dealing with nuclear energy. This study makes a detailed assessment of the availability of energy and its capacity, the geographical location of current and future nuclear plants, economic criteria, the deployment period and public opinion concerning the construction of new nuclear plants. The aim of the study is not only to show the advantages of the expansion of nuclear energy in Brazil but also to evaluate public opinion on this issue. (author)

  15. População estelar nuclear e extranuclear em galáxias Seyfert 2

    Science.gov (United States)

    Raimann, D. I.; Storchi-Bergmann, T.; Cid Fernandes, R., Jr.; Delgado, R. M. G.; Schmitt, H.; Heckman, T.; Leitherer, C.

    2003-08-01

    A luz das estrelas foi, historicamente, vista por observadores de AGNs como uma poluição inconveniente. Conseqüentemente, a informação contida nas características estelares foi, durante muito tempo, largamente omitida. Nos primeiros estudos, o método empregado para remover esta contaminação estelar foi representá-la por um template de galáxia elíptica e subtraí-la do espectro observado, restando o puro AGN como um resíduo. Hoje sabemos que não é tão simples representar essa população. Vários estudos têm mostrado a presença de formação estelar recente próxima a região nuclear de galáxias Seyfert. Neste trabalho foi revisada a abordagem tradicional, tendo-se focalizado a análise na luz estelar. Espectros óticos de fenda longa, com alta razão sinal/ruído, foram usados para estudar a variação radial das larguras equivalentes de linhas de absorção e cores do contínuo. Utilizando o método de síntese espectral de populações estelares, foram estimadas as contribuições de populações estelares de diferentes idades (e de um contínuo tipo lei de potência) para a luz integrada das galáxias, em 4020A. As principais conclusões deste trabalho são: na região nuclear, mais da metade das galáxias Seyfert 2 da amostra (57%) apresenta contribuições das populações com 100 milhões de anos ou mais jovens superior a 20% do fluxo em 4020A, enquanto que em cerca de 40% delas a componente de 3 milhões de anos (e/ou luz que provem de um núcleo ativo) tem contribuição significativa (maior do que 10%). Estas contribuições em geral decrescem quando se vai para regiões mais distantes do centro das galáxias, respectivamente 53% e 30% a 1kpc, 40% e 15% a 3kpc do centro das galáxias. Estes resultados foram comparados com aqueles obtidos para uma amostra de galáxias não ativas de mesmo tipo de Hubble das Seyfert. Em uma análise inicial nota-se que em geral as galáxias Seyfert apresentam contribuições das populações de 100 milh

  16. SURVEY, IDENTIFICATION AND EVALUATION OF INSECT INJURIES IN ORNAMENTAL TREES IN THE URBAN AREA OF GOIÂNIA, GOIÁS STATE, BRASIL LEVANTAMENTO, IDENTIFICAÇÃO E AVALIAÇÃO DOS DANOS DE INSETOS EM ÁRVORES ORNAMENTAIS NA ÁREA URBANA DE GOIÂNIA (GO

    Directory of Open Access Journals (Sweden)

    Antônio Henrique Garcia

    2007-09-01

    Full Text Available

    From 1800 ornamental trees sampled in Goiânia urban area, <em>Paquira> <em>aquatica> represented 62,7 %, <em>Cesalpinia> <em>sp.> 15,3 %, <em>Bauhinia variegataem> 10 %, <em>Sapthodea> <em>campanulata> 6 %, <em>Terminalia> <em>catappa> 3,2 %, <em>Acacia> <em>sp.> 1,2%, <em>Ponciana> <em>sp.> 1,0 %, and other species 1 %. The most frequent insect species observed in P. aquatica were <em>Psylla> <em>floccosa> ( 92,3%, <em>Steirastoma> <em>breve> (76,7%, <em>Palindia> <em>detracta> (63,4%, <em>Phelypera> <em>shuppeli> (43,4% and <em>Euchroma> <em>gigantea> (23,7%. The most severe injuries to plants are caused by <em>S. breveem>, which desiccates trunk and stems, and <em>E. giganteaem>. Its larvae destroy the whole root system and cause the fall of the tree. <em>Orthezia> <em>praelonga> was observed in 84,6 % of the sampled <em>B. variegataem>; in 30 trees 20% died after three years and 40% at the of the fourth year; from 50 seedlings 36% were desiccated after one year and 58% 36 months later. <em>O. praelongaem> was observed in 94,6% of <em>S. campanulataem>; in 32 trees 8% were desiccated in one year, 18% in the second and the remaining at the end of the third year. <em>Icerya purchasiem> was observed in 84,7% of <em>Cesalpinia spem>.; from 48 trees 5% were desiccated after six, 16 % two years later and 30% at the end of the fourth year; from 50 seedlings of this species, under intense attack, 78% were desiccated in 15 days. Quesadas gigas e <em>Dorisiana sp.em> were observed in <em>Acacia sp.em> In <em>Ponciana sp.em> it was observed the presence of some species of <em>Scolytidae>, <em>Platipodidae> and <em>Rhinotermitidae>, and no injuries were observed in <em>Terminalia> <em>catappa>.

    KEY-WORDS: <em

  17. General presentation of the instrumentation area of IPEN (Instituto de Pesquisas Energeticas e Nucleares)

    International Nuclear Information System (INIS)

    Anon.

    The area of electronic instrumentation of IPEN (Instituto de Pesquisas Energeticas e Nucleares), is presented. The activities of AIE (Electronic Instrumentation Area) is constituted basically in a technical attendance to the IPEN research centers and sometimes to industry that needs maintenance in nuclear equipments. (E.G.) [pt

  18. Proposal of a model for evaluation of research and development projects in a public scientific and technological institution: a survey in CNEN; Proposta de modelo de avaliacao de projetos de pesquisa e desenvolvimento em uma instituicao cientifica e tecnologica publica da area nuclear: um survey na CNEN

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Eduardo de Assumpcao

    2017-11-01

    Science and technology are directly related to the development of a country. The research and development projects in CNEN are financed by the direct resources of the budget of the Union and of the Development Agencies such as FINEP and CNPq. In general, project managers believe they can succeed when they complete a project on schedule, budget, and anticipated requirements, which is commonly known as a 'triple constraint' or 'iron triangle'. However, in the review of the literature, other criteria for evaluating success in projects, such as the benefits generated by society, the development of the team's capabilities, future opportunities, new technologies, among others, were verified. In this way, in order to assist the manager in the evaluation of this type of project, the present research carried out a review in the literature aiming to find concepts about success in projects and their evaluation criteria, proposed a model based on the theoretical reference and Importance and use of these criteria with the CNEN specialists, who work directly in the R and D projects of a public ICT in the nuclear area. The results showed that the criteria proposed in the model have a high degree of importance and show a decrease in the degree of utilization, suggesting that the criteria used in the model can help managers in the evaluation of these projects. (author)

  19. Management of risks in the chemical and nuclear areas

    International Nuclear Information System (INIS)

    Venuti, G.C.; Frullani, S.; Pocchiari, F.; Rogani, A.; Silano, V.; Tabet, E.; Zapponi, G.

    1984-01-01

    A comparative overview is provided of some major aspects concerning assessment and management of chemical and nuclear risks arising as a consequence of accidents. Statutory procedures for constructing and running nuclear and chemical plants in Italy are discussed in detail. Special attention is given to the major changes that are likely to occur after the adoption of the EEC Council Directive 82/501, designed to prevent major accidents which might result from certain industrial activities and to limit their consequences for humans and their environment. Present status and future trends of accident analysis and risk assessment are also dealt with, and special emphasis is placed on aspects common to both nuclear and chemical plants. Lastly, managerial aspects of contingency planning for, and response to, emergencies and accidents involving toxic chemical and/or ionizing radiations are examined with the aim of identifying more critical steps. (author)

  20. População nuclear e extranuclear em rádio-galáxias

    Science.gov (United States)

    Raimann, D. I.; Storchi-Bergmann, T.; Quintana, H.; Alloin, D.; Hunstead, R.; Wisotzki, L.

    2003-08-01

    A natureza do contínuo UV/ótico em rádio-galáxias é muito importante para o seu entendimento. Em baixos redshifts existem evidências de que muitas delas são dominadas no ótico por luz de estrelas velhas, características de galáxias early-type e em altos redshifts a característica dominante é um excesso de luz no UV, freqüentemente associado com estruturas que estão alinhadas aos eixos das estruturas rádio em grande escala. Inicialmente esse excesso foi interpretado como devido a episódios intensos de formação estelar nas galáxias hospedeiras. Entretanto, as descobertas dos alinhamentos entre as estruturas UV e rádio modificaram essa idéia. Foi proposto que a formação estelar é iniciada pela passagem do jato rádio através do meio interestelar das galáxias hospedeiras. A natureza do excesso UV começou a ser compreendida em um estudo detalhado do continuo ótico da 3C321, onde se concluiu que o contínuo desta galáxia tem origem multicomponente, com contribuições de populações velhas e intermediárias, de luz espalhada oriunda de um quasar obscurecido e do contínuo nebular. No presente trabalho estudamos a população nuclear e extranuclear de uma amostra de 24 rádio-galáxias, utilizando espectros óticos de fenda longa, com alta razão sinal/ruído. Através do método de síntese espectral de populações estelares, foram estimadas as contribuições de populações estelares de diferentes idades (e de um contínuo tipo lei de potência devido a um AGN, FC) para a luz integrada das galáxias, em 4020Å. As principais conclusões deste trabalho são: apenas quatro dos objetos estudados têm contribuições significativas (maiores do que 10%) das populações de 100 milhões de anos ou mais jovens (ou de FC) ao longo da região espacial estudada (6 kpc centrais); nenhuma das rádio-galáxias de tipo FRI estudadas tem contribuição significativa destas populações ao longo desta região; duas (de oito) de tipo FRII tem contribui

  1. Development and implementation of a geographical area categorisation method with targeted performance indicators for nationwide EMS in Finland.

    Science.gov (United States)

    Pappinen, Jukka; Laukkanen-Nevala, Päivi; Mäntyselkä, Pekka; Kurola, Jouni

    2018-05-15

    In Finland, hospital districts (HD) are required by law to determine the level and availability of Emergency Medical Services (EMS) for each 1-km 2 sized area (cell) within their administrative area. The cells are currently categorised into five risk categories based on the predicted number of missions. Methodological defects and insufficient instructions have led to incomparability between EMS services. The aim of this study was to describe a new, nationwide method for categorising the cells, analyse EMS response time data and describe possible differences in mission profiles between the new risk category areas. National databases of EMS missions, population and buildings were combined with an existing nationwide 1-km 2 hexagon-shaped cell grid. The cells were categorised into four groups, based on the Finnish Environment Institute's (FEI) national definition of urban and rural areas, population and historical EMS mission density within each cell. The EMS mission profiles of the cell categories were compared using risk ratios with confidence intervals in 12 mission groups. In total, 87.3% of the population lives and 87.5% of missions took place in core or other urban areas, which covered only 4.7% of the HDs' surface area. Trauma mission incidence per 1000 inhabitants was higher in core urban areas (42.2) than in other urban (24.2) or dispersed settlement areas (24.6). The results were similar for non-trauma missions (134.8, 93.2 and 92.2, respectively). Each cell category had a characteristic mission profile. High-energy trauma missions and cardiac problems were more common in rural and uninhabited cells, while violence, intoxication and non-specific problems dominated in urban areas. The proposed area categories and grid-based data collection appear to be a useful method for evaluating EMS demand and availability in different parts of the country for statistical purposes. Due to a similar rural/urban area definition, the method might also be usable for

  2. Counts of fox breeding dens in a riverine area of Northern Italy / Conteggio delle tane riproduttive di Volpe (<em>Vulpes vulpesem> in un'area golenale dell'Italia settentrionale

    Directory of Open Access Journals (Sweden)

    Claudio Prigioni

    1991-07-01

    Full Text Available Abstract From 1982 to 1986 the fox breeding dens were counted over areas ranging from 37 to 188 km² of the Ticino Park (Lombardy region. Eighty-eight breeding dens were found, of which 84.1% was along the wooded slopes of the river valley, 12.5% on the edge of woods, and 3.4% on the edge of poplar plantations. Breeding foxes used almost exclusively deserted setts of <em>Meles melesem> and burrows of <em>Oryctolagus cuniculusem>. The mean density was 0.22 dens/km² (min-max: 0.0-1.0 dens/km² and the highest values were found in agricoltura1 areas with wooded slopes of the river valley (1.0 dens/km² and in mixed woods with prevailing <em>Quercus roburem> and <em>Carpinus betulusem> (0.5 dens/km². The density of breeding dens does not seem to be influenced by the presence of protected areas and by the density of hares and of pheasants. Riassunto La ricerca delle tane riproduttive di Volpe <em>Vulpes vulpesem> è stata effettuata nel periodo 1982-86 nel Parco Lombardo della Valle del Ticino e ogni anno ha interessato una superficie variabile da 37 a 188 km². Su un totale di 88 tane rilevate, l'84,1% è stato rinvenuto lungo le scarpate dei terrazzi fluviali, il 12,5% al margine di boschi golenali e il 3,4% al margine di pioppeti. La Volpe utilizza quasi esclusivamente le tane abbandonate dal Tasso e quelle del Coniglio selvatico. La densità media di tane riproduttive è stata di 0,22 tane/km² (min-max: 0,O-1,0 tane/km² e i valori più elevati sono stati riscontrati in zone agricole con presenza di scarpate boscate (1,O tane/km² e in zone con boschi a prevalenza di Farnia e Carpino bianco (0,5 tane/km². Le densità trovate in aree protette non differiscono significativamente da quelle rilevate in aree in cui l'esercizio venatorio è consentito e non sembrano essere influenzate positivamente dalla densità di specie di particolare interesse venatorio come la Lepre e il Fagiano.

  3. Deployment Evaluation Methodology for the Electrometallurgical Treatment of DOE-EM Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Dahl, C.A.; Adams, J.P.; Rynearson, M.A.; Ramer, R.J.

    1999-01-01

    The Department of Energy - Environmental Management (DOE-EM) National Spent Nuclear Fuel Program (NSNFP) is charged with the disposition of legacy spent nuclear fuel (SNF). While direct repository disposal of the SNF is the preferred disposition option, some DOE SNF may need treatment to meet acceptance criteria at various disposition sites. The treatments may range from electrometallurgical treatment (EMT) and chemical dissolution to engineering controls. As a planning basis, a need is assumed for a treatment process, either as a primary or backup technology, that is compatible with, and cost-effective for, this portion of the DOE-EM inventory. The current planning option for treating this SNF, pending completion of development work and National Environmental Policy Act (NEPA) analysis, is the EMT process under development by Argonne National Laboratory - West (ANL-W). A decision on the deployment of the EMT is pending completion of an engineering scale demonstration currently in progress at ANL-W. For this study, a set of questions was developed for the EMT process for fuels at several locations. The set of questions addresses all issues associated with design, construction, and operation of a production facility. A matrix table was developed to determine questions applicable to various fuel treatment options. A work breakdown structure (WBS) was developed to identify a treatment process and costs from initial design to shipment of treatment products to final disposition. Costs were applied to determine the life-cycle cost of each option. This technique can also be applied to other treatment techniques for treating SNF

  4. Nuclear magnetic resonance of randomly diluted magnetic materials; Ressonancia nuclear magnetica em materiais magneticos diluidos aleatoriamente

    Energy Technology Data Exchange (ETDEWEB)

    Magon, C J

    1986-12-31

    The temperature dependence of the nuclear relaxation rates and line shapes of the F{sub O} resonance in the diluted antiferromagnet Fe{sub x} Zn{sub 1-x} F{sub 2} and Mn{sub x} Zn{sub 1-x} F{sub 2} are studied over a large temperature range T{sub N} < {approx} T {<=} 300 K. The high (room) temperature spin-lattice relaxation rates (1/T{sub 1}) of the F{sub O} nuclei, which are not transfer hyperfine coupled to the Fe (or Mn) spins, have been measured and calculated as a function of the concentration x. Good agreement with experiment is found for the theoretical results, which have been obtained in the range 0.1 {<=} x {<=} 0.8. The temperature dependence of 1/T{sub 1} for T{sub N}

  5. Location condition of nuclear power generation at a viewpoint of location area

    International Nuclear Information System (INIS)

    Kawase, Kazuharu

    1999-01-01

    In the thirty years memorial meeting of the National Nuclear Power Generation located Commune Conference (NNGC) held in October, 1998, an extremely important fact was clarified, relation deeply to main aim of NNGC that permanent development was not promised at the location area even if a nuclear power plant was constructed there. Therefore, it is required that Japan government receives operation of three laws on electric source development as soon as possible, establishes a basic target on permanent area promotion in the nuclear power generation located commune, realizes some examples on development of the commune together with nuclear power generation and intends to promoted its location. (G.K.)

  6. Nuclear power programmes and medium term projections in the OECD area

    International Nuclear Information System (INIS)

    Miida, J.; Haeussermann, W.; Mankin, S.

    1977-01-01

    The paper describes nuclear power growth forecasts up to 1985 on an individual country basis for the OECD area, based on present nuclear programmes. For the period between 1985 and the year 2000, no individual countries' estimates are given. The projections for this period are subdivided into three main areas: OECD Europe, North America and OECD Pacific Region. These projections are derived from the presently prevailing estimates concerning total energy growth, the increasing share of electricity requirements in total energy requirements and the growth of the nuclear share in electrical installed capacity. The basic assumptions are discussed and the combination of various possibilities results in upper and lower growth limits, which should include the most likely development. An attempt is also made to describe probable scenarios of nuclear reactor strategies, taking into account developments under way in the OECD area. Finally, the factors liable to influence nuclear power growth in a positive or negative way are briefly analysed

  7. The socio-economic impacts on regional areas as a result of new nuclear construction and nuclear decommissioning

    International Nuclear Information System (INIS)

    Devine, J. Michael

    2010-01-01

    Large social and economic impacts are caused by new nuclear construction and eventual shutdown of operations and decommissioning. When new construction begins, the impact on the local area is enormous. The influx of construction workers and businesses to provide services and goods usually overwhelms the area which previously may have had a minimal amount of infrastructure and little population. Also, given that many of the current nuclear facilities worldwide are located in somewhat remote regions, they have become the primary source of jobs for those regions. When these facilities shut down and go into decommissioning, there can be several adverse effects upon the region or area. This paper will address some of the primary socio-economic influences of both new nuclear construction and subsequent decommissioning. (author)

  8. Identification of Vital Areas at Nuclear Facilities. Technical Guidance (French Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    nuclear installations against sabotage are contained in IAEA Nuclear Security Series No. 13, Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5). After the attacks of 11 September 2001, the perception of the potential terrorist threat to nuclear installations changed significantly, and the IAEA initiated an effort to develop a series of guidance publications on the security of nuclear and radioactive material and facilities. This publication presents a structured approach to identifying the areas that contain equipment, systems, and components to be protected against sabotage. It specifically provides detailed guidance with regard to the identification of vital areas, that is, the areas to be protected in high consequence facilities. However, the process described is applicable to the identification of areas that should be protected at any nuclear facility. The method builds upon safety analyses to develop sabotage logic models for sabotage scenarios that could cause unacceptable radiological consequences. The sabotage actions represented in the logic models are linked to the areas from which they can be accomplished. The logic models are then analysed to determine areas that should be protected to prevent these unacceptable radiological consequences

  9. Cutting out the middleman: measuring nuclear area in histopathology slides without segmentation

    NARCIS (Netherlands)

    Veta, M.; van Diest, P.J.; Pluim, J.P.W.

    2016-01-01

    The size of nuclei in histological preparations from excised breast tumors is predictive of patient outcome (large nuclei indicate poor outcome). Pathologists take into account nuclear size when performing breast cancer grading. In addition,the mean nuclear area (MNA) has been shown to have

  10. Cutting out the middleman : Measuring nuclear area in histopathology slides without segmentation

    NARCIS (Netherlands)

    Veta, Mitko; Van Diest, Paul J.; Pluim, Josien P W

    2016-01-01

    The size of nuclei in histological preparations from excised breast tumors is predictive of patient outcome (large nuclei indicate poor outcome). Pathologists take into account nuclear size when performing breast cancer grading. In addition,the mean nuclear area (MNA) has been shown to have

  11. Feasible research on VLLW disposal in control area of nuclear installation

    International Nuclear Information System (INIS)

    Kong Jinsong; Guo Weiqun

    2013-01-01

    Based on the basic requirements on the VLLW landfill disposal specified by the national codes and standards, a on-site disposal of VLLW in the control area of nuclear installation was proposed. A detail analysis of the advantages and disadvantages about the disposal method and the problem to be solved were described. Results showed that the on-site disposal of VLLW in the control area of nuclear installation was feasible in practice. (authors)

  12. EM-50 Tanks Focus Area retrieval process development and enhancements. FY97 technology development summary report

    International Nuclear Information System (INIS)

    Rinker, M.W.; Bamberger, J.A.; Alberts, D.G.

    1997-09-01

    The Retrieval Process Development and Enhancements (RPD and E) activities are part of the US Department of Energy (DOE) EM-50 Tanks Focus Area, Retrieval and Closure program. The purpose of RPD and E is to understand retrieval processes, including emerging and existing technologies, and to gather data on these processes, so that end users have requisite technical bases to make retrieval decisions. Technologies addressed during FY97 include enhancements to sluicing, the use of pulsed air to assist mixing, mixer pumps, innovative mixing techniques, confined sluicing retrieval end effectors, borehole mining, light weight scarification, and testing of Russian-developed retrieval equipment. Furthermore, the Retrieval Analysis Tool was initiated to link retrieval processes with tank waste farms and tank geometric to assist end users by providing a consolidation of data and technical information that can be easily assessed. The main technical accomplishments are summarized under the following headings: Oak Ridge site-gunite and associated tanks treatability study; pulsed air mixing; Oak Ridge site-Old Hydrofracture Facility; hydraulic testbed relocation; cooling coil cleaning end effector; light weight scarifier; innovative tank mixing; advanced design mixer pump; enhanced sluicing; Russian retrieval equipment testing; retrieval data analysis and correlation; simulant development; and retrieval analysis tool (RAT)

  13. Cross-fault pressure depletion, Zechstein carbonate reservoir, Weser-Ems area, Northern German Gas Basin

    Energy Technology Data Exchange (ETDEWEB)

    Corona, F.V.; Brauckmann, F.; Beckmann, H.; Gobi, A.; Grassmann, S.; Neble, J.; Roettgen, K. [ExxonMobil Production Deutschland GmbH (EMPG), Hannover (Germany)

    2013-08-01

    A cross-fault pressure depletion study in Upper Permian Zechstein Ca2 carbonate reservoir was undertaken in the Weser-Ems area of the Northern German Gas Basin. The primary objectives are to develop a practical workflow to define cross-fault pressures scenarios for Zechstein Ca2 reservoir drillwells, to determine the key factors of cross-fault pressure behavior in this platform carbonate reservoir, and to translate the observed cross-fault pressure depletion to fault transmissibility for reservoir simulation models. Analysis of Zechstein Ca2 cross-fault pressures indicates that most Zechstein-cutting faults appear to act as fluid-flow baffles with some local occurrences of fault seal. Moreover, there appears to be distinct cross-fault baffling or pressure depletion trends that may be related to the extent of the separating fault or fault system, degree of reservoir flow-path tortuosity, and quality of reservoir juxtaposition. Based on the above observations, a three-part workflow was developed consisting of (1) careful interpretation and mapping of faults and fault networks, (2) analysis of reservoir juxtaposition and reservoir juxtaposition quality, and (3) application of the observed cross-fault pressure depletion trends. This approach is field-analog based, is practical, and is being used currently to provide reliable and supportable pressure prediction scenarios for subsequent Zechstein fault-bounded drill-well opportunities.

  14. Engineering with nuclear explosives near populated areas - A survey from the technological and economic viewpoint

    Energy Technology Data Exchange (ETDEWEB)

    Parker, K [AWRE, Aldermaston (United Kingdom)

    1970-05-01

    Current experience with underground firings of nuclear explosives and of large charges of conventional explosives is largely confined to sparsely populated areas such as the Nevada and Sahara deserts and parts of Siberia. On the other hand many of the commercial applications proposed for nuclear explosives are directly relevant to industrialized areas, where consumptions of energy and natural resources are high, as are population densities. In many of these areas there is a need to increase the efficiency with which natural gas, oil and electrical power are supplied and to make safe disposal of fluid wastes; completely contained nuclear explosions could be a useful tool in achieving some or all of these aims. Whilst radioactivity and air blast hazards are likely to rule out nuclear cratering operations near densely populated areas, the prospects for carrying out completely contained explosions are much better, providing seismic damage is kept within reasonable bounds. In large areas of Western Europe and on the eastern, southern and western seaboards of the United States this might be achieved by using nuclear explosions beneath the seabed at a reasonable distance from the nearest coastline, always provided the relevant political issues can be resolved. Stimulation and storage of North Sea natural gas, construction of off-shore oil storage and storage of electrical energy are areas where engineering with nuclear explosives merits more detailed investigation and some of the relevant technical problems are discussed. (author)

  15. Engineering with nuclear explosives near populated areas - A survey from the technological and economic viewpoint

    International Nuclear Information System (INIS)

    Parker, K.

    1970-01-01

    Current experience with underground firings of nuclear explosives and of large charges of conventional explosives is largely confined to sparsely populated areas such as the Nevada and Sahara deserts and parts of Siberia. On the other hand many of the commercial applications proposed for nuclear explosives are directly relevant to industrialized areas, where consumptions of energy and natural resources are high, as are population densities. In many of these areas there is a need to increase the efficiency with which natural gas, oil and electrical power are supplied and to make safe disposal of fluid wastes; completely contained nuclear explosions could be a useful tool in achieving some or all of these aims. Whilst radioactivity and air blast hazards are likely to rule out nuclear cratering operations near densely populated areas, the prospects for carrying out completely contained explosions are much better, providing seismic damage is kept within reasonable bounds. In large areas of Western Europe and on the eastern, southern and western seaboards of the United States this might be achieved by using nuclear explosions beneath the seabed at a reasonable distance from the nearest coastline, always provided the relevant political issues can be resolved. Stimulation and storage of North Sea natural gas, construction of off-shore oil storage and storage of electrical energy are areas where engineering with nuclear explosives merits more detailed investigation and some of the relevant technical problems are discussed. (author)

  16. Density and habitat use by the European wild rabbit (<em>Oryctolagus cuniculusem> in an agricultural area of northern Italy

    Directory of Open Access Journals (Sweden)

    Sara Serrano Pérez

    2009-02-01

    Full Text Available Abstract Habitat selection by the European wild rabbit (<em>Oryctolagus cuniculusem> in agro-ecosystems is still poorly understood. From December 2005 to March 2008, we assessed pre- and post-breeding wild rabbit densities and habitat use at different range levels in an agro-ecosystem area of northern Italy. Rabbit presence/absence, based on faecal pellets, was assessed in July and August 2007 for 150 1-m radius plots. The range of the species was defined by Kernel Analyese (99% and 50% of the total positive plots and Jacobs'index of selection was calculated for each habitat type. Moreover, we calculated the <em>w> index of selection and Manly's <em>α> indexof preference to compare habitat use to availability within the range. Ten macro-habitat variables and 11 micro-habitat ones were measured and tested for difference between plots with and without rabbits. Discriminant Function Analysis was applied to test for variables that differed between the two types of plots. Wild rabbit density averaged 113.4 individuals per km2 (SD=19.88. Rabbits selected woods and field edges, which provide food in the proximity of refuges, avoiding open areas. The dense tree cover of woods would reduce rabbit detectability by raptors while the undergrowth provides shelter against terrestrial predator, reducing the risk of predation. On the basis of our results, management actions for rabbit conservation should aim to improve the ecotones between woods and arable lands and to preserve scrub and woodland. Riassunto Densità e uso dell'habitat da parte de lconiglio selvatico (<em>Oryctolagus cuniculusem> in un'area agricola dell'Italia settentrionale L'individuazione delle caratteristiche dell'habitat che determinano la qualità ambientale per il coniglio selvatico è importante per la conoscenza dell'ecologia della specie e per la gestioen delle popolazioni. L'abbondanza e la distribuzione

  17. Problems caused by the Concentration of Nuclear Power Plants in Border Areas

    International Nuclear Information System (INIS)

    Billman, C.

    1979-01-01

    The concentration of nuclear power plants in border areas raises the problem of protection of the population and the environment in border lands. The author recalls the fundamental legal principle according to which no country may cause a prejudice to a neighbouring country due to installations harmful to the environment which are located in its own territory. Several legal systems are reviewed which provide for participation by neighbouring states in nuclear plant projects and licensing; the recourse procedure against such plants is also discussed. Finally, consideration is given to problems to be solved in order to coordinate legal and administrative measures in case of construction of nuclear plants in border areas. (NEA) [fr

  18. Vital area identification software VIP for the physical protection of nuclear power plants

    International Nuclear Information System (INIS)

    Jung, Woo Sik; Park, Chang Kue; Yang, Joon Eon

    2004-01-01

    There are two major factors to be considered for the physical protection of nuclear power plants. They are a design basis threat (DBT) and the vital area identification (VAI). The DBT has been considered as 'the maximum credible threat.' The vital area is defined as 'an area inside a protected area containing equipment, systems or devices, or nuclear materials, the sabotage of which could directly or indirectly lead to unacceptable radiological consequences.' For the VAI of nuclear power plants, a software VIP (Vital area Identification Package based on PSA method) is being developed. The VIP is based on the current probabilistic safety assessment (PSA) techniques. The PSA method, including internal as well as external events, is known as the most complete and consistent method for identifying various accident sequences that might result in a core melt and radioactive material release to the environment. Thus, the VIP employs a fault tree analysis method in the PSA and utilizes the PSA results

  19. Safety aspects of nuclear power plants nearby urban areas

    International Nuclear Information System (INIS)

    Kroeger, W.

    1986-01-01

    According to the Environmental Experts Council smaller reactors would correspond best to the heat demand of the Federal Republic of Germany. The study discusses and investigates into the present safety concepts and site selection criteria, trends towards power plant sites nearby urban areas, site-dependent parameters and their influence on the extent of damage, protective aims, compatibility of the protective aims proposed, and the protective measures required. (DG) [de

  20. Deployment Evaluation Methodology for the Electrometallurgical Treatment of DOE-EM Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Ramer, Ronald James; Adams, James Paul; Rynearson, Michael Ardel; Dahl, Christian Adam

    1999-01-01

    The Department of Energy - Environmental Management (DOE-EM) National Spent Nuclear Fuel Program (NSNFP) is charged with the disposition of legacy Spent Nuclear Fuel (SNF). The NSNFP, conducted by Lockheed Martin Idaho Technology Co. (LMITCO) at the Idaho National Engineering and Environmental Laboratory (INEEL), is evaluating final disposition of SNF in the DOE complex. While direct repository disposal of the SNF is the preferred disposition option, some DOE SNF may need treatment to meet acceptance criteria at various disposition sites. Evaluations of treatment needs and options have been previously prepared, and further evaluations are ongoing activities in the DOE-EM NSNFP. The treatments may range from electrometallurgical treatment (EMT) and chemical dissolution to engineering controls. As a planning basis, a need is assumed for a treatment process, either as a primary or backup technology, that is compatible with, and cost-effective for, this portion of the DOE-EM inventory. The current planning option for treating this SNF, pending completion of development work and National Environmental Policy Act (NEPA) analysis, is the EMT process under development by Argonne National Laboratory - West (ANL-W). A decision on the deployment of the EMT is pending completion of an engineering scale demonstration currently in progress at ANL-W. Treatment options and treatment locations will depend on fuel type and location of the fuel. One of the first steps associated with selecting one or more sites for treating SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. One of the major issues associated with SNF treatment is final disposition of treatment products and associated waste streams. During conventional SNF treatment, various chemicals are added that may increase the product

  1. Analysis of Leukemia incidence (1997-2007) in vicinity area of a nuclear installation

    International Nuclear Information System (INIS)

    Jin Rong; Sun Quanfu; Liu Fen; Zhang Xu; Xing Ru; Xu Xinmei; Li Xiaoliang; Su Xu

    2012-01-01

    Objective: To investigate the leukemia incidence among residents in the vicinity area of a nuclear installation. Methods: The data were collected by the retrospective survey. Diagnosis is based on the medical records in all the relevant hospitals. The study area was those residential areas within 10 km of radium surrounding the installation. All residents who had lived in the study area for six months and over were recruited into the study group. Results: The survey ascertained 643 newly diagnosed leukemia cases in the study area during 1997 to 2007. The crude rate was 2.51/100000, and its standardized rate to national population structure was 2.53/100000. The incidence rate in the study area was slightly lower than that in the whole city. No increase trend was detected during the period. Conclusions: No significant difference of the leukemia incidence rate was found between the vicinity area of the nuclear installation and the whole city. (authors)

  2. Open area E.M. field measurements for radiation hazard purposes

    International Nuclear Information System (INIS)

    Bevacqua, F.; Cipollone, E.; Morviducci, A.; Venditti, L.

    1989-01-01

    This article reports on an extensive set of measurements of the E.M. pollution that has been done for radiation hazard purposes. The measurement results are compared with international standards, regulations and laws. Special attention is devoted to the measurement of the E.M. field near hospitals and some important remarks are made on risks related to induced errors on pacemarker and medial instrumentation

  3. Improvement of Aircraft Crash Effective Areas for Koeberg Nuclear Power Plant

    International Nuclear Information System (INIS)

    Momoti, S.; Dongmo, G.B.; Combrink, Y.

    2017-01-01

    Probabilistic Safety Assessment (PSA): Tool for determining safe functioning of nuclear power plant to meet regulatory requirements; One of the inputs to the PSA are the frequency and consequences of an aircraft crash. Overview: Frequency of Aircraft Crash; Effective Area of an Aircraft Crashing into Koeberg - Aviation Categories, - Shielding of sensitive target buildings; Impact of refining the Effective AreaFrequency of Aircraft Crash

  4. Consolidated progress report for 1976 on nuclear data activities in the NDS service area

    International Nuclear Information System (INIS)

    1977-10-01

    A consolidated progress report for 1976 prepared for countries in the NDS service area. It is intended to encourage a closer relationship between Member States and provide for a wider circulation of unpublished progress reports from countries within the Nuclear Data Section service area

  5. Contribution of Nuclear Training Centre in Ljubljana to Training and Information in the Area of Nuclear Technology

    International Nuclear Information System (INIS)

    Stritar, A.

    1998-01-01

    Nuclear Training Centre in Ljubljana ia a part of the Jozef Stefan Institute. The paper presents its main activities, which consist of training for NPP Krsko staff, training in the area of radiation protection, organization of international training courses and public information. NPP Krsko personnel obtains initial technical training at our training centre. We are also offering training courses and licensing for people working with radioactive substances in medicine, industry and science. We are internationally recognized training centre for organization of regional and interregional courses and meeting. Our fourth activity is public information. We are visited by around 7000 students per year and answer to every question about nuclear energy. (author)

  6. Means of surveying contaminated areas resulting from overseas nuclear accidents

    International Nuclear Information System (INIS)

    Looney, J.H.H.; Thorne, M.C.; Dickson, D.M.J.

    1989-09-01

    The Chernobyl accident is briefly reviewed as a useful basis to examine some of the considerations related to the design of surveys. The plans and procedures of key European and North American countries are reviewed, as well as the plans and capabilities of UK facilities and government agencies. The survey design incorporates the concepts of land use category, topography climate, etc. and discusses the spatial and temporal scale requirements. Use of a Geographic Information System is recommended to co-ordinate the data. Models address the requirement to detect an annual effective dose equivalent of 0.5 mSv to an individual in the first year following the accident. The equipment requirements are based on transit-type vans, each, preferably, with one or two gamma spectrometers, MCA's and ancillary equipment, with three teams of two men. This unit could survey about 150 km 2 within a larger area in 3 days. The cost per survey team is estimated to be Pound 60,000 - Pound 80,000 in the first year, with annual costs of Pound 20-23,000. (author)

  7. Cleanup of large areas contaminated as a result of a nuclear accident

    International Nuclear Information System (INIS)

    1989-01-01

    The purposes of the report are to provide an overview of the methodology and technology available to clean up contaminated areas and to give preliminary guidance on matters related to the planning, implementation and management of such cleanups. This report provides an integrated overview of important aspects related to the cleanup of very large areas contaminated as a result of a serious nuclear accident, including information on methods and equipment available to: characterize the affected area and the radioactive fallout; stabilize or isolate the contamination; and clean up contaminated urban, rural and forested areas. The report also includes brief sections on planning and management considerations and the transport and disposal of the large volumes of wastes arising from such cleanups. For the purposes of this report, nuclear accidents which could result in the deposition of decontamination over large areas if the outer containment fails badly include: 1) An accident with a nuclear weapon involving detonation of the chemical high explosive but little, if any, nuclear fission. 2) A major loss of medium/high level liquid waste (HLLW) due to an explosion/fire at a storage site for such waste. 3) An accident at a nuclear power plant (NPP), for example a loss of coolant accident, which results in some core disruption and fuel melting. 4) An accident at an NPP involving an uncontrolled reactivity excursion resulting in the violent ejection of a reactor core material and rupture of the containment building. 117 refs, 32 figs, 12 tabs

  8. Areas for US-India civilian nuclear cooperation to prevent/mitigate radiological events.

    Energy Technology Data Exchange (ETDEWEB)

    Balachandran, Gopalan; Forden, Geoffrey Ethan

    2013-01-01

    Over the decades, India and the United States have had very little formal collaboration on nuclear issues. Partly this was because neither country needed collaboration to make progress in the nuclear field. But it was also due, in part, to the concerns both countries had about the others intentions. Now that the U.S.-India Deal on nuclear collaboration has been signed and the Hyde Act passed in the United States, it is possible to recognize that both countries can benefit from such nuclear collaboration, especially if it starts with issues important to both countries that do not touch on strategic systems. Fortunately, there are many noncontroversial areas for collaboration. This study, funded by the U.S. State Department, has identified a number of areas in the prevention of and response to radiological incidents where such collaboration could take place.

  9. Literature survey of blast and fire effects of nuclear weapons on urban areas

    Energy Technology Data Exchange (ETDEWEB)

    Reitter, T.A.; McCallen, D.B.; Kang, S.W.

    1982-06-01

    The American literature of the past 30 years on fire and blast effects of nuclear weapons on urban areas has been surveyed. The relevant work is briefly sketched and areas where information is apparently lacking are noted. This report is intended to provide the basis for suggesting research priorities in the fire and blast effects area for the Federal Emergency Management Agency. It is also intended to provide entry into the literature for researchers. over 850 references are given.

  10. Literature survey of blast and fire effects of nuclear weapons on urban areas

    International Nuclear Information System (INIS)

    Reitter, T.A.; McCallen, D.B.; Kang, S.W.

    1982-06-01

    The American literature of the past 30 years on fire and blast effects of nuclear weapons on urban areas has been surveyed. The relevant work is briefly sketched and areas where information is apparently lacking are noted. This report is intended to provide the basis for suggesting research priorities in the fire and blast effects area for the Federal Emergency Management Agency. It is also intended to provide entry into the literature for researchers. over 850 references are given

  11. Diet of the Eurasian badger (<em>Meles melesem> in an area of the Italian Prealps

    Directory of Open Access Journals (Sweden)

    Monica Marassi

    2002-12-01

    Full Text Available Abstract Samples of Eurasian badger faeces (n= 147 were collected at monthly intervals from October 1997 to December 1999 in an area of the Italian Prealps (58 km², on the eastern coast of Lario (Como Lake. The altitude of the area ranged from 200 to 1300 m. Badger scats were analysed to estimate the relative volume and the frequency of occurrence of identifiable food items. Fruits, arthropodes, earthworms and mammals constituted the main food categories. Differences were found between the seasonal frequency of occurrences of arthropodes, earthworms and mammals, considering however that the small sample size in summer does not allow any definitive conclusions. The wide range of food items eaten by badgers and the seasonal differences would suggest that the badger is a "generalist" species which adopts an opportunist feeding strategy.

  12. Problems and possibilities of establishing greenery within nuclear power plant areas

    International Nuclear Information System (INIS)

    Supuka, J.

    1987-01-01

    The environmental impacts of nuclear power plants are briefly discussed. The arrangement of the green in the area of nuclear power plants is illustrated by an example of the territorial plans of the Bohunice nuclear power plants. The green must fullfil multiple functions, such as architectonical, aesthetical, wind protection, dust protection, noise and radioactivity protection, soil improvement, psychological, soil reclamation, renaturalization, and social functions. The green zones are differentiated into the actual plant zone, the hygiene protection zone, the accompanying green zone, and the peripheral housing development green zone. (M.D.). 6 figs., 1 tab., 7 refs

  13. Management of communication area in a nuclear research and development institute

    International Nuclear Information System (INIS)

    Soares, Wellington Antonio

    2005-01-01

    Nuclear energy to the general public is always associated to the production of nuclear weapons or to nuclear and radiological accidents. Public communication actions done by the National Commission of Nuclear Energy (CNEN) have been contributing to make known the social and peaceful applications of nuclear energy, reaching different kinds of public. Interaction programs with society and in particular with students have also been carried out by the Nuclear Technology Development Center (CDTN/CNEN). Measuring public communication results can help to show that financial resource in this area should be considered as investment and not as expenses. One needs therefore a well-established managing system. Fundamentals of the National Quality Award Criteria for Excellence - PNQ are being applied in the area in charge of business and public communication at CDTN. Systematic registration of results started in 2000 and a gradual increase in the number of means of communication for the internal public has occurred in the last five years. The Center has now a bimonthly newspaper edition. Communication indicators have shown an increasing number of students received in the Center or provided with lectures in schools. Results of satisfaction inquiry from these students show good results. The implemented management system has allowed informing the nature and quantity of people reached by the information on nuclear applications and the improvement in the institutional image. (author)

  14. Management of communication area in a nuclear research and development institute

    Energy Technology Data Exchange (ETDEWEB)

    Soares, Wellington Antonio [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil). Servico de Negocios e Comunicacao]. E-mail: soaresw@cdtn.br

    2005-07-01

    Nuclear energy to the general public is always associated to the production of nuclear weapons or to nuclear and radiological accidents. Public communication actions done by the National Commission of Nuclear Energy (CNEN) have been contributing to make known the social and peaceful applications of nuclear energy, reaching different kinds of public. Interaction programs with society and in particular with students have also been carried out by the Nuclear Technology Development Center (CDTN/CNEN). Measuring public communication results can help to show that financial resource in this area should be considered as investment and not as expenses. One needs therefore a well-established managing system. Fundamentals of the National Quality Award Criteria for Excellence - PNQ are being applied in the area in charge of business and public communication at CDTN. Systematic registration of results started in 2000 and a gradual increase in the number of means of communication for the internal public has occurred in the last five years. The Center has now a bimonthly newspaper edition. Communication indicators have shown an increasing number of students received in the Center or provided with lectures in schools. Results of satisfaction inquiry from these students show good results. The implemented management system has allowed informing the nature and quantity of people reached by the information on nuclear applications and the improvement in the institutional image. (author)

  15. Approval of land divisions in passage way servitude areas: OSBRA pipeline; Aprovacao de loteamento em areas de servidao de passagem: experiencia do OSBRA em Senador Canedo, GO

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Andreia B. dos; Araujo, Adriano C. [TRANSPETRO, Rio de Janeiro, RJ (Brazil); Brito, Walderes [Universidade Federal de Goias (UFG), Goiania, GO (Brazil). Faculdade de Comunicacao e Biblioteconomia

    2008-07-01

    This work systematizes actions taken by TRANSPETRO and the Department of Planning of the City of Senador Canedo, in order to discipline the urban growth in areas around the Pipeline Sao Paulo - Brasilia, OSBRA. The need for such measure was identified with the increase of the number of interferences of new lots planned for the areas of servitude for the OSBRA. These lots imply a significant change in the characteristics of the track use of pipelines, since the transformation of status from rural to urban implies a greater amount of interference and increase the potential of others. Actions to deal with that reality began with the creation of a working group, whose goal was to identify the problems and solutions to establish a routine for approval of lots in areas of servitude of the pipelines, so as to enable ventures, seeking the integrity of equipment, the security of the population and the preservation of the environment. (author)

  16. Evaluation Of The Exclusion And Low Population Areas Around A Nuclear Power Plant

    International Nuclear Information System (INIS)

    Tawfik, F.S.

    2011-01-01

    Being adjacent to the nuclear power plant (NPP) the exclusion area (EA) is the area of greatest importance. It essentially defines a buffer zone where the public has no access. It helps to define the fenced plant area, the site area and the public area. Also, the low population area is the area immediately surrounding the exclusion area near a licensed reactor in terms of public safety and the ability of residents to get away from the plant in an emergency. This study clarifies their significance and reviews the international approach on them. Assuming the nuclear power plant site at the north coast of Egypt, the exclusion area and low population area are determined according to CFR (2002). In this method, a maximum possible amount of radioactivity release (called a source term) should be assumed. The boiling water reactor (BWR) with a power 1000 MW was used to carry the calculation and assuming a severe loss of coolant accident with meltdown of reactor. The site specific data have been collected, investigated and processed. The effect of the degree of atmospheric stability and building width of the plant were examined. The proceeding factors that control the determination of exclusion area and low population area should be taken into consideration in the site evaluation stage and design basis of NPP to set a minimum distances for them

  17. The application of PSA techniques to the vital area identification of nuclear power plants

    International Nuclear Information System (INIS)

    Ha, Jae Joo; Jung, Woo Sik; Park, Chang Kue

    2005-01-01

    This paper presents a Vital Area Identification (VAI) method based on the current Fault Tree Analysis (FTA) and Probabilistic Safety Assessment (PSA) techniques for the physical protection of nuclear power plants. A structured framework of a Top Event Prevention set Analysis (TEPA) application to the VAI of nuclear power plants is also delineated. One of the important processes for physical protection in a nuclear power plant is VIA that is a process for identifying areas containing nuclear materials, Structures, Systems or Components (SSCs) to be protected from sabotage, which could directly or indirectly lead to core damage and unacceptable radiological consequences. A software VIP (Vital area Identification Package based on the PSA method) is being developed by KAERI for the VAI of nuclear power plants. Furthermore, the KAERI fault tree solver FTREX (Fault Tree Reliability Evaluation eXpert) is specialized for the VIP to generate the candidates of the vital areas. FTREX can generate numerous MCSs for a huge fault tree with the lowest truncation limit and all possible prevention sets

  18. Construction of Temelin nuclear power plant and its impact on possible recreational uses of the area

    Energy Technology Data Exchange (ETDEWEB)

    Uvirova, E

    1985-01-01

    The possible recreational use is assessed of the territory within 25 kms from the Temelin nuclear power plant site. The territory includes 3 tourist areas (South Bohemian lakes, Middle Vltava, Tabor area). From the point of view of time usability, all three areas are of the single-season type, i.e., they are used in the summer season, as they are oriented to water sports and tourism. Neither the Temelin nuclear power plant nor its 3 km protective zone overlap with the reacreational areas, and thus the areas can also in future be used for tourism. The use of the Temelin plant in district heating will contribute to reducing fallout from the existing thermal power plants. (J.C.).

  19. Construction of Temelin nuclear power plant and its impact on possible recreational uses of the area

    International Nuclear Information System (INIS)

    Uvirova, E.

    1985-01-01

    The possible recreational use is assessed of the territory within 25 kms from the Temelin nuclear power plant site. The territory includes 3 tourist areas (South Bohemian lakes, Middle Vltava, Tabor area). From the point of view of time usability, all three areas are of the single-season type, i.e., they are used in the summer season, as they are oriented to water sports and tourism. Neither the Temelin nuclear power plant nor its 3 km protective zone overlap with the reacreational areas, and thus the areas can also in future be used for tourism. The use of the Temelin plant in district heating will contribute to reducing fallout from the existing thermal power plants. (J.C.)

  20. Volumes, Masses, and Surface Areas for Shippingport LWBR Spent Nuclear Fuel in a DOE SNF Canister

    International Nuclear Information System (INIS)

    J.W. Davis

    1999-01-01

    The purpose of this calculation is to estimate volumes, masses, and surface areas associated with (a) an empty Department of Energy (DOE) 18-inch diameter, 15-ft long spent nuclear fuel (SNF) canister, (b) an empty DOE 24-inch diameter, 15-ft long SNF canister, (c) Shippingport Light Water Breeder Reactor (LWBR) SNF, and (d) the internal basket structure for the 18-in. canister that has been designed specifically to accommodate Seed fuel from the Shippingport LWBR. Estimates of volumes, masses, and surface areas are needed as input to structural, thermal, geochemical, nuclear criticality, and radiation shielding calculations to ensure the viability of the proposed disposal configuration

  1. The situation of the wolf (<em>Canis lupusem> in the area of the Regional Park of the Simbruini Mountains / La situazione del Lupo (<em>Canis lupusem> nell'area del Parco Naturale Regionale dei Monti Simbruini

    Directory of Open Access Journals (Sweden)

    Paolo Verucci

    1992-07-01

    Full Text Available Abstract This work presents the results of a field research on the species <em>Canis lupusem> in the Regional Park of the Simbruini Mountains. In relation to Wolf conservation, an investigation on feral and free-roving dogs was carried out. The method of snowtracking was used for Wolves and Feral dogs, the method of sighting was used for free-roving dogs. The research underlines the importance of the Simbruini Mountains for the protection of Wolf in central Apennines and the factors, at present, threatening its survival. Riassunto Nel presente lavoro vengono illustrati i risultati di una ricerca sul campo sulla specie <em>Canis lupusem> nel Parco Naturale Regionale dei Monti Simbruini. In relazione agli aspetti riguardanti la conservazione del Lupo, è stata compiuta un'indagine sul fenomeno del randagismo canino. Per i lupi e i cani inselvatichiti è stato usato il metodo dello snowtracking, per le altre categorie di Cani è stato utilizzato il metodo dell'avvistamento. La ricerca ha messo in luce l'importanza dell'area dei Simbruini per la salvaguardia del Lupo nell'Appennino centrale e i fattori che, attualmente, ne minacciano la sopravvivenza.

  2. Sustainability indicators for innovation and research institutes of nuclear area in Brazil; Indicadores de sustentabilidade para institutos de pesquisa e inovacao da area nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Alves, S.F.; Barreto, A.A.; Rodrigues, P.C.H.; Feliciano, V.M.D., E-mail: sfa@cdtn.br, E-mail: aab@cdtn.br, E-mail: pchr@cdtn.br, E-mail: vmfj@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2016-11-01

    Indicators are relevant tools for measuring sustainability process. In this study, the relevance of sustainability indicators appropriate for research and innovation institutes in Brazil is discussed. As reference for case study, nuclear research and innovation institutes were chosen. Sixty-nine sustainability indicators were considered. Some of these indicators were obtained from lists in the literature review, distributed between the dimensions environmental, economic, social, cultural and institutional. The other indicators were developed through discussions between professionals from nuclear, environmental, economic, social and cultural areas. Among the investigated indicators, 32 were selected as being the most relevant. Discrepancies were found during the analysis the opinions of the experts in relation to sustainability dimensions proposed. (author)

  3. A systematic method for identifying vital areas at complex nuclear facilities.

    Energy Technology Data Exchange (ETDEWEB)

    Beck, David Franklin; Hockert, John

    2005-05-01

    Identifying the areas to be protected is an important part of the development of measures for physical protection against sabotage at complex nuclear facilities. In June 1999, the International Atomic Energy Agency published INFCIRC/225/Rev.4, 'The Physical Protection of Nuclear Material and Nuclear Facilities.' This guidance recommends that 'Safety specialists, in close cooperation with physical protection specialists, should evaluate the consequences of malevolent acts, considered in the context of the State's design basis threat, to identify nuclear material, or the minimum complement of equipment, systems or devices to be protected against sabotage.' This report presents a structured, transparent approach for identifying the areas that contain this minimum complement of equipment, systems, and devices to be protected against sabotage that is applicable to complex nuclear facilities. The method builds upon safety analyses to develop sabotage fault trees that reflect sabotage scenarios that could cause unacceptable radiological consequences. The sabotage actions represented in the fault trees are linked to the areas from which they can be accomplished. The fault tree is then transformed (by negation) into its dual, the protection location tree, which reflects the sabotage actions that must be prevented in order to prevent unacceptable radiological consequences. The minimum path sets of this fault tree dual yield, through the area linkage, sets of areas, each of which contains nuclear material, or a minimum complement of equipment, systems or devices that, if protected, will prevent sabotage. This method also provides guidance for the selection of the minimum path set that permits optimization of the trade-offs among physical protection effectiveness, safety impact, cost and operational impact.

  4. The European nuclear safety and radiation protection area: steps and prospects

    International Nuclear Information System (INIS)

    Gillet, G.

    2010-01-01

    Launched with enthusiasm and determination in 1957, The European Atomic Energy Community (EAEC - EURATOM), which aimed to promote the development of a 'powerful nuclear industry' in Europe, has not ultimately fulfilled the wishes of its founding fathers. Rapidly, and on a topic as strategic as the peaceful use of the atom, national reflexes prevailed. The Chernobyl disaster, in 1986, also substantially slowed down the use of nuclear energy in Europe. Nuclear safety and radiation protection have followed two different paths. Backed by Chapter III of the EURATOM treaty, over time the EAEC has developed a substantial legislative corpus on radiation protection. Meanwhile, and strange as it may seem, nuclear safety has remained the poor relation, on the grounds that the treaty does not grant EURATOM competence in the area. It is true that legislation was adopted in reaction to Chernobyl, but for a long time there was no specific regulation of nuclear safety in the EU. The European nuclear safety and radiation protection area owes its construction to Community mechanisms as well as to informal initiatives by safety authorities. Today, more than ever, this centre provides consistency, an overall balance which should both strengthen it and impose it as an international reference. Progress can now be expected on waste management, radiation protection and the safety objectives of new reactors. (author)

  5. The Minister Council decree about conditions for to bring into the Polish customs area, to take away from the Polish customs area, and to transit through this area nuclear materials, radioactive sources and device including such sources

    International Nuclear Information System (INIS)

    Miller, L.

    2002-01-01

    The decree refers to conditions for to bring into the Polish customs area, to take away from the Polish customs area, and to transit through this area nuclear materials, radioactive sources and devices containing such sources

  6. Development of the detection technology of the source area derived from nuclear activities

    International Nuclear Information System (INIS)

    Suh, Kyungsuk; Kim, Ingyu; Keum, Dongkwon; Lim, Kwangmuk; Lee, Jinyong

    2012-07-01

    - It is necessary to establish of the overall preparedness for analysis of the nuclear activities near the neighboring countries by increasing of the construction of the nuclear power plants and reprocessing facilities in China, North Korean Japan and Russia. - In Korea, the analysis and measurements for nuclear activities have been conducted, however the detection technology to find out the source area has not been developed. It is important to estimate the source origin of the radioisotope from the neighboring countries including Korea in the aspects of the surveillance and safety for the covert nuclear activities in Northeast Asia region - In this study, the data DB, treatment of the weather data and the development of connection module were conducted to track the origin of the radioisotope in the first year of the research. It had constructed the DB like the reactor types, places in China, Taiwan, Japan and Korea and the release amounts of the noble gas released into the air

  7. Development of the detection technology of the source area derived from nuclear activities

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Kyungsuk; Kim, Ingyu; Keum, Dongkwon; Lim, Kwangmuk; Lee, Jinyong

    2012-07-15

    - It is necessary to establish of the overall preparedness for analysis of the nuclear activities near the neighboring countries by increasing of the construction of the nuclear power plants and reprocessing facilities in China, North Korean Japan and Russia. - In Korea, the analysis and measurements for nuclear activities have been conducted, however the detection technology to find out the source area has not been developed. It is important to estimate the source origin of the radioisotope from the neighboring countries including Korea in the aspects of the surveillance and safety for the covert nuclear activities in Northeast Asia region - In this study, the data DB, treatment of the weather data and the development of connection module were conducted to track the origin of the radioisotope in the first year of the research. It had constructed the DB like the reactor types, places in China, Taiwan, Japan and Korea and the release amounts of the noble gas released into the air.

  8. 200 city survey. JEMS 2001 annual report on EMS operational & clinical trends in large, urban areas.

    Science.gov (United States)

    Cady, Geoff

    2002-02-01

    This year's survey offered examples of evolving partnerships between the public and EMS providers with a growing number of systems implementing PAD programs. The apparent influence of a communication center's managing agency on prioritization strategies is concerning. However, further study is needed. EMS managers must pay careful attention to comm center practices and technology to ensure their ability to support response prioritization and the efficient management of EMS resources. The small reduction in the use of hot response (lights and siren) to every request for service is disappointing in light of medical literature and position statements that condemn this practice. Resource response can be safely prioritized using today's EMD protocol systems. Prioritization and changing response [figure: see text] time requirements to address impending revenue and service demand changes will require additional standardization of methodologies and reporting of response times to relate this measure to other system performance indicators (e.g., patient morbidity/mortality, cost, customer satisfaction, etc.). The future presents a difficult road for system administrators. However, the adoption of a growing number of information-management tools and changes in procedures and dispatch processes offer potential solutions. The increased use of hand-held computers or personal digital assistant (PDAs) to gather and provide information and the almost universal use of CAD will aid providers in performing the research necessary to change response time performance requirements, improving EMS system efficiency. Use of this technology will also likely improve patient care and reimbursement through more timely and accurate reporting and analysis. The medical director's role will be critical to ensuring potential changes don't compromise patient care. Obtaining a better understanding of how much time can safely elapse between the time of the 9-1-1 call and when patient-care activities

  9. Personnel and working area monitoring at the Department of Nuclear Science, Universiti Kebangsaan Malaysia

    International Nuclear Information System (INIS)

    Amran Abd Majid; Muhamad Samudi Yasir; Che Rosli Che Mat

    1995-01-01

    Personnel (staff and student) and working area absorbed dose monitoring at the Department of Nuclear Science from 1984 until September 1993 is reported. Generally average absorbed dose received by the staff and working area were less than 0.5 and 2.0 mSv/yr respectively. The application of low activity of radioactive materials and complying the UKM (Universiti Kebangsaan Malaysia) and LPTA (AELB) - Atomic Energy Licensing Board regulations contributing to the low rate recorded. (author)

  10. Main ecopathology syndromes of children living in the area of nuclear waste tailings

    Directory of Open Access Journals (Sweden)

    Saatova G. M.

    2016-05-01

    Full Text Available the clinical forms of ecopathology and clinical and epidemiological features of congenital and acquired diseases of children living in the area of nuclear waste tailings (city Mailu-Suu Kyrgyz Republic are studied in this article. The authors figured out that 52.6% of children living in stressful environmental conditions had a high medical and social risk of chronic disease.

  11. CG-DAR-1: Guide to the declassified areas of nuclear energy research

    International Nuclear Information System (INIS)

    Lytle, J.E.

    1984-08-01

    This guide, which is based on classification of information by the Atomic Energy Act of 1954, as amended, and on subsequent declassification actions by the Department of Energy (DOE) and its predecessors, is intended to identify those areas of nuclear research and development that have been removed from the Restricted Data (RD) category and declassified

  12. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1982

    International Nuclear Information System (INIS)

    Black, S.C.; Grossman, R.F.; Mullen, A.A.; Potter, G.D.; Smith, D.D.

    1983-07-01

    A principal activity of the Offsite Radiological Safety Program is routine environmental monitoring for radioactive materials in various media and for radiation in areas which may be affected by nuclear tests. It is conducted to document compliance with standards, to identify trends, and to provide information to the public. This report summarizes these activities for CY 1982

  13. Radiation dose distribution monitoring at neutron radiography facility area, Nuclear Energy Unit, Malaysia

    International Nuclear Information System (INIS)

    Abdul Razak Daud

    1995-01-01

    One experiment was carried out to get the distribution of radiation doses at the neutron radiography facilities, Nuclear Energy Unit, Malaysia. The analysis was done to evaluate the safety level of the area. The analysis was used in neutron radiography work

  14. Tomography of the 2011 Iwaki earthquake (M 7.0) and Fukushima nuclear power plant area

    Energy Technology Data Exchange (ETDEWEB)

    Tong, P. [Tohoku Univ., Sendai (Japan). Dept. of Geophysics; Tsinghua Univ., Beijing (China). Dept. of Mathematical Sciences; Zhao, D. [Tohoku Univ., Sendai (Japan). Dept. of Geophysics; Yang, D. [Tsinghua Univ., Beijing (China). Dept. of Mathematical Sciences

    2012-07-01

    High-resolution tomographic images of the crust and upper mantle in and around the area of the 2011 Iwaki earthquake (M 7.0) and the Fukushima nuclear power plant are determined by inverting a large number of high-quality arrival times with both the finite-frequency and ray tomography methods. The Iwaki earthquake and its aftershocks mainly occurred in a boundary zone with strong variations in seismic velocity and Poisson's ratio. Prominent low-velocity and high Poisson's ratio zones are revealed under the Iwaki source area and the Fukushima nuclear power plant, which may reflect fluids released from the dehydration of the subducting Pacific slab under Northeast Japan. The 2011 Tohoku-oki earthquake (Mw 9.0) caused static stress transfer in the overriding Okhotsk plate, resulting in the seismicity in the Iwaki source area that significantly increased immediately following the Tohoku-oki main-shock. Our results suggest that the Iwaki earthquake was triggered by the ascending fluids from the Pacific slab dehydration and the stress variation induced by the Tohoku-oki main-shock. The similar structures under the Iwaki source area and the Fukushima nuclear power plant suggest that the security of the nuclear power plant site should be strengthened to withstand potential large earthquakes in the future. (orig.)

  15. Tomography of the 2011 Iwaki earthquake (M 7.0 and Fukushima nuclear power plant area

    Directory of Open Access Journals (Sweden)

    P. Tong

    2012-02-01

    Full Text Available High-resolution tomographic images of the crust and upper mantle in and around the area of the 2011 Iwaki earthquake (M 7.0 and the Fukushima nuclear power plant are determined by inverting a large number of high-quality arrival times with both the finite-frequency and ray tomography methods. The Iwaki earthquake and its aftershocks mainly occurred in a boundary zone with strong variations in seismic velocity and Poisson's ratio. Prominent low-velocity and high Poisson's ratio zones are revealed under the Iwaki source area and the Fukushima nuclear power plant, which may reflect fluids released from the dehydration of the subducting Pacific slab under Northeast Japan. The 2011 Tohoku-oki earthquake (Mw 9.0 caused static stress transfer in the overriding Okhotsk plate, resulting in the seismicity in the Iwaki source area that significantly increased immediately following the Tohoku-oki mainshock. Our results suggest that the Iwaki earthquake was triggered by the ascending fluids from the Pacific slab dehydration and the stress variation induced by the Tohoku-oki mainshock. The similar structures under the Iwaki source area and the Fukushima nuclear power plant suggest that the security of the nuclear power plant site should be strengthened to withstand potential large earthquakes in the future.

  16. The nuclear energy in debate. Myths, realities and climatic changes; A energia nuclear em debate. Mitos, realidades e mudancas climaticas

    Energy Technology Data Exchange (ETDEWEB)

    Matthes, Felix; Rosenkranz, Gerd; Bermann, Celio (orgs.)

    2003-07-01

    This study argues myths and the truths that involve nuclear energy: on the one hand, the universal issue on the nuclear energy and its supposed contribution for the global warming reduction, and another one, there are many lower-risk options available to fight against climate change. Investing in nuclear energy carries not only considerable health, financial and security risks, it may also prove to be a dangerous lock-in and dead end. Twenty years after the nuclear disaster of Chernobyl, any attempts by the nuclear industry to celebrate its revival and to paint itself as the solution to climate change should be rejected. Policy makers around the world should learn from its people, who largely resist the use of nuclear energy. In this context the authors firmly believe that nuclear energy is no answer to climate change. A short-sighted renaissance of nuclear energy would require considerable amounts of public money, which should rather be invested in the development and deployment of renewable energy technologies and energy efficiency measures.

  17. Protocol between the Nuclear Protection and Safety Bureau of Portugal and the Nuclear Energy Commission of Spain on Technical Information concerning Nuclear Installations in Border Areas

    International Nuclear Information System (INIS)

    1980-01-01

    This Protocol was concluded under the Agreement of the same date on the safety of nuclear installations in border areas. Its purpose is to prescribe the type of information referred to in the Agreement. It lays down in detail all the documents to be supplied concerning the siting, construction, operation and decommissioning of nuclear installations, including the geological, seismological, meteorological, hydrological and ecological aspects of the sites concerned, for purposes of environmental protection; the characteristics of the projected installations and emergency plans must also be provided. Similarly to the Agreement, this Protocol will remain in force for a period of ten years. (NEA) [fr

  18. Hydrodynamic characterization in areas under influence in the petroleum industry; Caracterizacao hidrodinamica em areas sob influencia na industria petrolifera

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Daniel Alexsander Silva dos; Silva, Andre Giskard Aquino da [Rio Grande do Norte Univ., Natal, RN (Brazil)]. E-mail: danielsandersilva@hotmail.com; Vital, Helenice [Conselho Nacional de Desenvolvimento Cientifico e Tecnologico (CNPq), Brasilia, DF (Brazil); Silveira, Iracema Miranda da [Museu Camara Cascudo, Natal, RN (Brazil); Chaves, Marcelo dos Santos; Lima, Zuleide Maria Carvalho [Rio Grande do Norte Univ., Natal, RN (Brazil). Programa de Pos-graduacao em Geodinamica e Geofisica

    2003-07-01

    For elaboration of contingency plans it is necessary to execute the mapping of sensitive areas to oil spill, as well as to create suitable forecast models for oil pollution movements. These models should start from a consistent database, so that it can encompass the several phases of the environmental monitoring. In both cases hydrodynamic data are essential. The analysis of hydrodynamic parameters is also an important phase for the knowledge of the Holocene evolution of the study area, as well as for execution of a suitable development policy to be applied on the area. The activities developed in this research involve collection of data 'in situ' at the Galinhos-Guamare and Diogo Lopes lagoons, as well as data manipulation referring to the littoral drift collected monthly along the North coast of the state of Rio Grande do Norte by members of the Grupo de Geologia e Geofisica Marinha e Melhoramento Ambiental (GGEMMA) from UFRN.

  19. Characterization of Discharge Areas of Radionuclides Originating From Nuclear Waste Repositories

    Science.gov (United States)

    Marklund, L.; Xu, S.; Worman, A.

    2009-05-01

    If leakages in nuclear waste repositories located in crystalline bedrock arise, radionuclides will reach the biosphere and cause a risk of radiological impact. The extent of the radiological impact depends on in which landscape elements the radionuclides emerge. In this study, we investigate if there are certain landscape elements that generally will act as discharge areas for radionuclides leaking from subsurface deposits. We also characterize the typical properties that distinguish these areas from others. In humid regions, landscape topography is the most important driving force for groundwater flow. Because groundwater is the main transporting agent for migrating radionuclides, the topography will determine the flowpaths of leaking radionuclides. How topography and heterogeneities in the subsurface affect the discharge distribution of the radionuclides is therefore an important scope of this study. To address these issues, we developed a 3-D transport model. Our analyses are based on site-specific data from two different areas in Sweden, Forsmark, Uppland, and Oskarshamn, Småland. The Swedish Nuclear Waste Management Company (SKB) has selected these two areas as candidate areas for a deep repository of nuclear waste and the areas are currently subject to site investigations. Our results suggest that there are hot-spots in the landscape i.e. areas with high probability of receiving large amounts of radionuclides from a leaking repository of nuclear waste. The hot-spots concentrate in the sea, streams, lakes and wetlands. All these elements are found at lower elevations in the landscape. This pattern is mostly determined by the landscape topography and the locations of fracture zones. There is a relationship between fracture zones and topography, and therefore the importance of the topography for the discharge area distribution is not contradicted by the heterogeneity in the bedrock. The varieties of landscape elements which have potential for receiving

  20. Characterisation of discharge areas of radionuclides originating from nuclear waste repositories

    International Nuclear Information System (INIS)

    Marklund, L.; Woerman, A.

    2008-01-01

    In this study, we investigate if there are certain landscape elements that will generally act as discharge areas for radio-nuclides leaking from a subsurface deposit of nuclear waste. We also characterize the typical properties that distinguish these areas from others. Understanding the processes controlling the clustering of discharge to certain areas is an additional topic of study. Landscape topography is the most important driving force for groundwater flow. Because groundwater is the main transporting agent for migrating radio-nuclides, the topography will determine the flow paths of leaking radionuclides. How topography and heterogeneities in the subsurface affect the discharge distribution of the radionuclides is the main scope of this study. An analytical and a numerical model are used. Conclusions are: Our results suggest that the varieties of landscape elements which have potential for receiving significant amounts of radio-nuclides are limited. To save recourses, the surficial radiological assessments should therefore be focused in these areas. Furthermore, the discharge areas of groundwater from repository depth have defining characteristics that distinguish them from discharge areas of shallower groundwater flow cells. Due to the similarities within deep groundwater discharge areas, one can make site-specific analyses of those areas, which have a broad applicability for migration of radio-nuclides originating from a nuclear waste repository (author)(tk)

  1. The Activities of Nuclear Training Centre Ljubljana in the Area of Radioactive Waste Management

    International Nuclear Information System (INIS)

    Jencic, I.

    2006-01-01

    Nuclear Training Centre Ljubljana has several activities related to radioactive waste management. These activities include training of professionals in the area of nuclear physics and nuclear technology, radiation protection courses, organization of international courses and workshops in the area of radioactive waste management, and public information on radioactivity and waste management. The paper will describe the specifics and the extent of training related to radioactive waste. Recently we have participated in a European coordination action CETRAD and an overview of the results of this project will also be presented. Very important component of our activity is public information that is based on an information centre and live lectures to organized groups of visitors, mostly schoolchildren. About one half of one school generation of Slovenia visits the Information centre every year. A poll is conducted among visitors every year and its results are a very useful tool to follow the evolution of public opinion on nuclear energy and radioactive waste disposal. The latter is, at least in Slovenia, still considered as the major obstacle against the use of nuclear energy. (authors)

  2. Nuclear reactors project optimization based on neural network and genetic algorithm; Otimizacao em projetos de reatores nucleares baseada em rede neural e algoritmo genetico

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Claudio M.N.A. [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); Schirru, Roberto; Martinez, Aquilino S. [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia

    1997-12-01

    This work presents a prototype of a system for nuclear reactor core design optimization based on genetic algorithms and artificial neural networks. A neural network is modeled and trained in order to predict the flux and the neutron multiplication factor values based in the enrichment, network pitch and cladding thickness, with average error less than 2%. The values predicted by the neural network are used by a genetic algorithm in this heuristic search, guided by an objective function that rewards the high flux values and penalizes multiplication factors far from the required value. Associating the quick prediction - that may substitute the reactor physics calculation code - with the global optimization capacity of the genetic algorithm, it was obtained a quick and effective system for nuclear reactor core design optimization. (author). 11 refs., 8 figs., 3 tabs.

  3. Sizing of integrated energy systems in rural areas; Dimensionamento de sistemas integrados de energia em areas rurais

    Energy Technology Data Exchange (ETDEWEB)

    Nogueira, Carlos Eduardo Camargo [Universidade Estadual do Oeste do Parana (UNIOESTE), Cascavel, PR (Brazil). Centro de Ciencias Exatas e Tecnologicas], e-mail: cecn@correios.net.br; Zuern, Hans Helmut [Universidade Federal de Santa Catarina (UFSC), Florianopolis, SC (Brazil). Dept. de Energia Eletrica], e-mail: hans@labspot.ufsc.br

    2004-07-01

    The purpose of this work was to develop a new model for sizing integrated energy systems in rural areas, based on simulation techniques and linear programming, producing a system with minimum cost and high reliability level. The used reliability level was the loss of power supply probability (LPSP), for periods of consecutive hours. With the developed model, many simulations are accomplished with the parameters and sizing variables, making possible the analysis of different scenarios for the optimized energy systems. (author)

  4. Plutonium focus area

    International Nuclear Information System (INIS)

    1996-08-01

    To ensure research and development programs focus on the most pressing environmental restoration and waste management problems at the U.S. Department of Energy (DOE), the Assistant Secretary for the Office of Environmental Management (EM) established a working group in August 1993 to implement a new approach to research and technology development. As part of this new approach, EM developed a management structure and principles that led to the creation of specific Focus Areas. These organizations were designed to focus the scientific and technical talent throughout DOE and the national scientific community on the major environmental restoration and waste management problems facing DOE. The Focus Area approach provides the framework for intersite cooperation and leveraging of resources on common problems. After the original establishment of five major Focus Areas within the Office of Technology Development (EM-50, now called the Office of Science and Technology), the Nuclear Materials Stabilization Task Group (EM-66) followed the structure already in place in EM-50 and chartered the Plutonium Focus Area (PFA). The following information outlines the scope and mission of the EM, EM-60, and EM-66 organizations as related to the PFA organizational structure

  5. Environmental control by means of studying the natural areas with nuclear physics methods

    International Nuclear Information System (INIS)

    Boyarkina, A.P.; Glukhov, G.G.; Rezchikov, V.I.; Shelud'ko, S.I.

    1988-01-01

    Element composition of precipitation accumulated in natural areas (snow, peat) is investigated by neutron activation technique using nuclear reactor. Content of microelements (Fe, Co, Sc, Au, Hg, Sb, Br, Na) is determined in both maximal contamination industrial area and at a distance more, than 40 km from the area. Snow cover and peat occurrence are shown to be convenient substrates to investigate contamination of the industrial centre vicinities in space and time. Standard development of MPC (maximum permissible concentration) contents of industrial dust ingredients, especially toxic ones, in these substrates allows to solve quickly many problems raised by environmental monitoring. 10 refs.; 2 tabs

  6. IAEA activities in the back-end area of nuclear fuel cycle

    International Nuclear Information System (INIS)

    Fukuda, Kosaku

    1999-01-01

    This paper concerns recent outcomes from the IAEA's activities in the area of the nuclear fuel cycle, particularly focusing on the back-end of the fuel cycle. It includes spent fuel management, plutonium utilization and burnup credit. In the area of spent fuel management, worldwide prospects and status of the spent fuel arising, storage and reprocessing are presented. In the area of plutonium utilization worldwide, only MOX fuel fabrication is described. Finally, the worldwide status of the burnup credit implementation is described. (author)

  7. Determination of karst collapse intensity indicator in area of nuclear power plant construction using incomplete data

    International Nuclear Information System (INIS)

    Sharapov, R

    2014-01-01

    The paper deals with the definition of karst collapse intensity. The technique for determining the intensity of karst formation and collapse on the basis of calculation and probabilistic method is given. Karst collapse formation is affected by a great variety of natural and anthropogenic factors. Each factor can vary quite widely. The paper describes a technique for determining karst collapse intensity from incomplete data. It uses karst processes monitoring data in the area and monitoring data of areas with similar values of the most significant factors leading to the karst collapses. The method used for determination of karst collapse intensity indicator in area of Nizhny Novgorod nuclear power plant construction

  8. Activities of Nuclear Research Institute Rez in the area of hydrogen technologies

    International Nuclear Information System (INIS)

    Doucek, A.; Janik, L.; Misak, J.

    2010-01-01

    NRI is a research institution established in 1955. Nowadays, the Institute provides wide range of expertise and services for operators of the nuclear power plants in the Czech Republic and abroad, supports Czech central state institutions in the domains of strategic energy planning and development, management of radioactive waste (for the Ministry of Trade and Industry), provides independent expertise for the State Office of Nuclear Safety, performs activities in the area of exploitation of ionising radiation and irradiation services for basic and applied research, health service and industry, performs research and provides services for radioactive waste disposal, production of radiopharmaceuticals, education and training of experts and scientific specialists and performs many other activities. With the gradual changes in energy policy, hydrogen economy becomes one of the important topics related to nuclear energy. NRI is participating in the research and development in this area and as a member of the Czech Hydrogen Technology Platform is currently the leader in this area in the country. To promote hydrogen economy, NRI prepared and participated in several demonstration projects. Studies on production of hydrogen in current and future nuclear power plants are performed as well. (authors)

  9. Current legal issues of European integration in the area of peaceful uses of nuclear energy

    International Nuclear Information System (INIS)

    Handrlica, Jakub

    2009-01-01

    The main issues of current discussions concerning the status of European integration in the area of peaceful uses of nuclear energy are described with focus on the present and future of the EURATOM Treaty. The basic features of the EURATOM Treaty are highlighted and those issues which are currently subject to discussion in foreign literature (e.g. EURATOM's legitimacy, specification of competencies, obsolete provisions, etc.) are pointed out. The major attempts to reform the wording of the EURATOM Treaty and the relevance of the Treaty to its Member States in the future, in relation to the 'Nuclear New Build' in particular, are also described. (orig.)

  10. Nuclear incident response in industrial areas: assessing the economic impact of the decision to evacuate

    International Nuclear Information System (INIS)

    Pauwels, N.; Walle, B. van de; Hardeman, F.; Sohier, A.; Soudan, K.

    1996-01-01

    The economic impact of imposing countermeasures in case of a nuclear emergency is a very important aspect in both the Probabilistic Risk Assessment code COSYMA and the Real-time On-line DecisiOn Support system RODOS. Therefore, these codes make use of the economic model ECONOM. In this paper, we will show that this economic model is not very well suited, nor designed, to predict the economic impact of evacuating a highly industrialised area in case of a nuclear emergency. Furthermore, we will indicate how recent economic investment theories can be used to deal with this decision problem in a more elaborate way. (author)

  11. Modificações nucleares em células parasitadas pelo Trypanosoma cruzi em chagásicos crônicos

    Directory of Open Access Journals (Sweden)

    Hipólito de Oliveira Almeida

    1987-09-01

    Full Text Available Através do estudo da musculaturalisa da parede da veia central das supra-renais de chagásicos crônicos foram identificados núcleos em 18 dentre 40 células parasitadaspelo Trypanosoma cruzi. Com o auxílio de uma ocular micrométrica foram tomados dois diâmetros de cada ninho e núcleo, obtendo-se suas médias e desvios padrões (25,7 µm ± 17,2 e 12 µm ± 5,3 e 7,5 µm ± 2,82 para diâmetros dos ninhos e dos núcleos para células mononucleadas e binucleadas respectivamente. A relação diâmetro do núcleo/diâmetro do ninho foi de 0,5 ± 0,16. 83,3% dos ninhos eram mononucleados e apenas 16,7% binucleados. A média do volume nuclear para as células parasitadas foi de 1204µm³ ± 807,0 e para as células musculares lisas não parasitadasfoi de 69,6µm ± 7,2. A forma e o contorno nucleares eram variados e irregulares. Os núcleos hipercromáticos ou vesiculosos, com membrana cromatínica geralmente espessa e bem definida, freqüentemente mostrando um a dois nucléolos por secção, podendo, no entanto, serem encontrados até 8 nucléolos. Sendo as alterações nucleares descritas freqüentes nos chagásicos crônicos, épossível que sejam a expressão morfológica de importantes interações entre o T. cruzi e o leiomiócito.

  12. Basofilia e anisotropia nucleares em células de camundongo após tratamento com oxamniquine

    Directory of Open Access Journals (Sweden)

    Ivanira José Bechara

    1984-02-01

    Full Text Available Com o objetivo de se estudar a ação da oxamniquine, uma droga utilizada no tratamento da esquistossomose, sobre a cromatina de núcleos de células animais, foram estudados os padrões de basofilia e anisotropia nucleares em hepatócitos, em células do músculo cardíaco e em linfócitos de camundongos adultos jovens. A oxamniquine foi administrada por via oral (436 mg/kg e preparados foram obtidos após diversos tempos de fornecimento da droga aos animais. Nos núcleos corados com azul de toluidina a pH 4,0, após digestão com RNAse, não se encontrou diferença quanto aos padrões de basofilia e anisotropia comparando-se animais tratados com controles. Demonstrou se assim que as moléculas de oxamniquine não se alojam no interior da dupla hélice do DNA, não alteram a sua conformação helicoidal nem se ligam aos grupos fosfatos livres desta macromolécula, diferindo, portanto, da atuação de outro esquistossomicida, o hycanthone.

  13. Viabilidade económica da implementação de um reactor nuclear para a produção de energia eléctrica em Portugal

    OpenAIRE

    Pedro, Miguel António de Morais

    2012-01-01

    O presente trabalho tem como objectivo avaliar economicamente e determinar a viabilidade da implementação de um reactor nuclear para produção de energia eléctrica. Faz-se uma abordagem a aspectos da energia nuclear no mundo e em particular a energia nuclear na união europeia, faz-se uma análise sobre a estrutura do sector nuclear em Espanha e o futuro da energia no mundo. É realizada uma análise sobre a energia nuclear em Portugal, são abordados aspectos como o planeamento energético, a local...

  14. Drogas em áreas de risco: o que dizem os jovens Drugs in risk areas: what young people say

    Directory of Open Access Journals (Sweden)

    Anacely Guimarães Costa

    2012-06-01

    Full Text Available A pesquisa teve como ponto de partida um planejamento comunitário para discussão da situação de saúde de uma das principais áreas de risco de Fortaleza-Ceará, no qual o tema das drogas ganhou destaque. Pretendeu-se entrar em contato com o que os adolescentes da área percebiam como fatores de risco e de proteção para consumo de drogas em sua comunidade. Trata-se de um estudo qualitativo em que foi usado o grupo focal como técnica para obtenção de informações. O tratamento dos dados foi o de sistematizar temas comuns, dividindo-os em duas categorias de análise: fatores de risco e de proteção para o envolvimento com drogas. Nas falas dos adolescentes, percebeu-se que coexistem múltiplos fatores que se relacionam, ora aparecendo como aspectos de influência, ora como protetores, entre eles: família, grupo social, escola, vida em área de risco e mídia. Por outro lado, as redes sociais de apoio apareceram essencialmente como protetoras. Também percebeu-se que alguns assuntos foram levantados de forma transversal aos temas centrais, como as perspectivas de vida desses jovens e a necessidade de políticas públicas, importantes no apoio às redes sociais, à família e na atuação em áreas de risco. Assim, o que se põe em questão é a impossibilidade de consenso sobre os fatores exclusivos de risco ou de proteção. A partir disso, destaca-se a importância de potencializar a discussão e provocar reflexões a respeito da possibilidade de modos de vida fora do circuito das drogas.The research has as starting point a community planning to discuss the health status of one of the key risk areas of Fortaleza, Ceará state, in which the theme of drugs was highlighted. It was intended to get in touch with what young people perceive as factors of risk and protection for drug abuse in their community. It is a qualitative study in which the focus group was used as technique for obtaining information. Data processing systematized common

  15. IAEA Sees Safety Commitment at Spain’s Almaraz Nuclear Power Plant, Areas for Enhancement

    International Nuclear Information System (INIS)

    2018-01-01

    An International Atomic Energy Agency (IAEA) team of experts said the operator of Spain’s Almaraz Nuclear Power Plant demonstrated a commitment to the long-term safety of the plant and noted several good practices to share with the nuclear industry globally. The team also identified areas for further enhancement. The Operational Safety Review Team (OSART) today concluded an 18-day mission to Almaraz, whose two 1,050-MWe pressurized-water reactors started commercial operation in 1983 and 1984, respectively. Centrales Nucleares Almaraz-Trillo (CNAT) operates the plant, located about 200 km southwest of Madrid. OSART missions aim to improve operational safety by objectively assessing safety performance using the IAEA’s safety standards and proposing recommendations for improvement where appropriate. Nuclear power generates more than 21 per cent of electricity in Spain, whose seven operating power reactors all began operation in the 1980s.The mission made a number of recommendations to improve operational safety, including: • The plant should implement further actions related to management, staff and contractors to enforce standards and expectations related to industrial safety. • The plant should take measures to reinforce and implement standards to enhance the performance of reactivity manipulations in a deliberate and carefully-controlled manner. • The plant should improve the support, training and documented guidance for Severe Accident Management Guideline users in order to mitigate complex severe accident scenarios. The team provided a draft report of the mission to the plant’s management. The plant management and the Nuclear Safety Council (CSN), which is responsible for nuclear safety oversight in Spain, will have the opportunity to make factual comments on the draft. These will be reviewed by the IAEA and the final report will be submitted to the Government of Spain within three months. The plant management said it would address the areas

  16. Absorbed dose by thyroid in case of nuclear accidents; Dose absorvida pela tireoide em casos de acidentes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Campos, Laelia; Attie, Marcia Regina Pereira [Universidade Federal de Sergipe (UFS), Sao Cristovao, SE (Brazil). Dept. de Fisica; Lima, Fernando Roberto de Andrade, E-mail: falima@cnen.gov.b [Centro Regional de Ciencias Nucleares do Nordeste (CRCN-NE/CNEN-PE), Recife, PE (Brazil); Amaral, Ademir [Universidade Federal de Pernambuco (UFPE), Recife, PE (Brazil). Dept. de Energia Nuclear

    2011-07-01

    Radioisotopes of iodine are produced in abundance in nuclear fission reactions, and great amounts of radioiodine may be released into the environment in case of a nuclear reactor accident. Thyroid gland is among the most radiosensitive organs due to its capacity to concentrate iodine. The aim of this work was to evaluate the importance of contributions of internally deposited iodines ({sup 131}I, {sup 132}I, {sup 133}I, {sup 134}I and {sup 135}I) to the dose absorbed to thyroid follicle and to the whole organ, after internal contamination by those isotopes. For internal dose calculation, the code of particles transport MCNP4C was employed. The results showed that, in case of nuclear accidents, the contribution of short-lived iodines for total dose is about 45% for thyroid of newborn and about 40% for thyroid of adult. Thus, these contributions should not be neglected in a prospective evaluation of risks associated to internal contamination by radioactive iodine. (author)

  17. Nuclear desalination: harnessing the seas for development of coastal areas of Pakistan

    International Nuclear Information System (INIS)

    Ayub, M.S.; Butt, W.M.

    2005-01-01

    Pakistan has a population of 140 million with more than 30% of the population living in cities and towns. Karachi, the major port city of the country, is the most densely populated with a population crossing the 11 million mark. The city receives 435 MGD of drinking water from the River Indus and other sources. However, the net demand for the year 2000 was 594 MGD thus there is a gap of 159 MGD in demand and supply. Statistics show that the water demand in Karachi is increasing at the rate of 100 MGD every five years. The coastal belt of the country extends to 1046 sq. km. Of this, 930 km is from the Karachi to Gwader region in the province of Baluchistan. Most of the coastal areas lie outside the monsoon system of weather and therefore the climate is extremely dry. The annual rainfall in this belt is about 15 cms. Therefore, fresh water availability is a major factor for development of the coastal belt of Pakistan. In the wake of the looming water crisis it is becoming increasingly clear that all available and appropriate technologies, including nuclear and related technologies, have to be used for the sustainable development and management of freshwater resources in Pakistan. One particular approach is the desalination of seawater, and countries are increasing their capacity to harness the seas for tapping fresh water. The prospects of using nuclear energy for seawater desalination on a large scale are attractive since desalination is an energy intensive process. Pakistan Atomic Energy Commission (PAEC) is planning to actively participate in the activities of IAEA in the field of nuclear desalination by offering one of its nuclear power plants for coupling a demonstration nuclear desalination plant. Karachi Nuclear Power Plant (KANUPP), which is the country's first nuclear plant has been successfully operating for the last 30 years. This plant is proposed to be used as a potential site for installation of a demonstration nuclear desalination plant. KANUPP is

  18. Bioremediation process in impacted area of petroleum activities; Processos de biorremediacao em areas influenciadas por atividades petroliferas

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Olivia Maria Cordeiro de; Trigueis, Jorge Alberto; Queiroz, Antonio Fernando de Souza; Celino, Joil Jose; Lima, Danusia Ferreira; Santana, Robson Carneiro [Universidade Federal da Bahia (UFBA), Salvador, BA (Brazil). Inst. de Geociencias

    2008-07-01

    The present work's objective is to test sampling methodologies applied on the bioremediation processes in situ, involving the establishment of sample replicates, specific laboratory procedures and its results, inedited on the referred technique. Agricultural fertilizers were used, NPK and OSMOCOTE, as biostimulants on mangroves substrates affected by petroleum activities. The tested methodology used on the experiment was based on the monitoring of this technology in aquarium with water from Sao Paulo's river and sediment contaminated by oil, realized in three steps (first pre-test, second pre-test and third pre-test) that happened between the months of August and November of 2007. The physical-chemical parameters were measured with portable devices carefully calibrated and the oil analyzed with gas chromatography. The saturated hydrocarbons (n-alkenes) had an increase on the concentrations for some aquariums and these found results do not permit to confirm if the inhibition of the degradation of the saturated hydrocarbons are somehow related to the usage of the nutrients NPK or OSMOCOTE. The time interval applied on the procedure, the sampling methodology used and even the intrinsic heterogeneity of the mangrove substrate are in the evaluation stage with new tests in order to make better the technique delineation, inedited, utilized in the area. (author)

  19. Inspection of the brazilian nuclear regulatory body in the area of radiotherapy. A critical analysis; Inspecao do orgao regulador nuclear brasileiro na area de radioterapia. Uma analise critica

    Energy Technology Data Exchange (ETDEWEB)

    Brito, Ricardo Roberto de Azevedo

    2005-07-01

    The National Commission of Nuclear Energy (CNEN) is responsible in Brazil for the activities of licensing and control of radioactive installations in the radiotherapy medical area. The majority of these activities are developed by CNEN Co-ordination of Radioactive Installations (CORAD). One of the necessary stages for the development of licensing and control activities is the inspection of radiotherapy services (clinics and hospitals). Almost all of these inspections are carried out by CNEN Inst. of Radiation Protection and Dosimetry (IRD), through its Service of Medical Physics in Radiotherapy and Nuclear Medicine (SEFME). This work makes a survey of the main nonconformities found during ten years of inspections in radiotherapy services (1995 - 2004) and analyses the efficiency of these inspections in making the radiotherapy services develop their activities according to the norms in vigour in the country and adopt corrective actions against, at least, the nonconformities evidenced by CNEN inspectors. Additionally, it analyses the possibility of improvement and / or the optimisation of the process, through a procedure able to be unified and controlled, aiming a prompt communication to those involved in the licensing process (SEFME and CORAD) about the attendance by the radiotherapy services to the non-conformity items observed during the inspection. (author)

  20. The outline of the research and development EM-ACROSS in Tono area

    International Nuclear Information System (INIS)

    Nakajima, Takahiro; Kunitomo, Takahiro; Kumazawa, Mineo; Nagao, Hiromichi

    2010-07-01

    ACROSS (Accurately Controlled Routinely Operated Signal System) has developed to acquire the detailed information on the tectonically active zone. The technology for example the transmission and receiving technique, the data analysis and the interpretation technique of the ACROSS signal is able to apply not only to seismology but also to other field. We considered the ACROSS technology may apply to the engineering technology of the Mizunami Underground Research Laboratory (MIU) project, for example monitoring of the change of the geological environment around shafts and also the strength of the shaft concrete itself. It is planned that the examination for three years will be made from fiscal year 2007, and the new observation site around the MIU was established, and the data acquisition and data analysis have been carried out. This report compiled technical matters among the results obtained in the research and the development of the EM-ACROSS. (author)

  1. Aerial radiological survey of the San Onofre Nuclear Generating Station and surrounding area, San Clemente, California

    International Nuclear Information System (INIS)

    Hilton, L.K.

    1980-12-01

    An airborne radiological survey of an 11 km 2 area surrounding the San Onofre Nuclear Generating Station was made 9 to 17 January 1980. Count rates observed at 60 m altitude were converted to exposure rates at 1 m above the ground and are presented in the form of an isopleth map. Detected radioisotopes and their associated gamma ray exposure rates were consistent with that expected from normal background emitters, except directly over the plant

  2. NCRP Program Area Committee 3: Nuclear and Radiological Security and Safety.

    Science.gov (United States)

    Taylor, Tammy P; Buddemeier, Brooke

    2016-02-01

    Program Area Committee (PAC) 3 provides guidance and recommendations for response to nuclear and radiological incidents of both an accidental and deliberate nature. Leadership of PAC 3 was transitioned in March 2015, and the newly composed PAC has been working to delineate and then prioritize the landscape of possible activities for PAC 3. The major activity of PAC 3 during the past year was the establishment of Scientific Committee 3-1 to begin producing a report on Guidance for Emergency Responder Dosimetry.

  3. Modificações nucleares em células parasitadas pelo Trypanosoma cruzi em chagásicos crônicos

    Directory of Open Access Journals (Sweden)

    Hipólito de Oliveira Almeida

    1987-09-01

    Full Text Available Através do estudo da musculaturalisa da parede da veia central das supra-renais de chagásicos crônicos foram identificados núcleos em 18 dentre 40 células parasitadaspelo Trypanosoma cruzi. Com o auxílio de uma ocular micrométrica foram tomados dois diâmetros de cada ninho e núcleo, obtendo-se suas médias e desvios padrões (25,7 µm ± 17,2 e 12 µm ± 5,3 e 7,5 µm ± 2,82 para diâmetros dos ninhos e dos núcleos para células mononucleadas e binucleadas respectivamente. A relação diâmetro do núcleo/diâmetro do ninho foi de 0,5 ± 0,16. 83,3% dos ninhos eram mononucleados e apenas 16,7% binucleados. A média do volume nuclear para as células parasitadas foi de 1204µm³ ± 807,0 e para as células musculares lisas não parasitadasfoi de 69,6µm ± 7,2. A forma e o contorno nucleares eram variados e irregulares. Os núcleos hipercromáticos ou vesiculosos, com membrana cromatínica geralmente espessa e bem definida, freqüentemente mostrando um a dois nucléolos por secção, podendo, no entanto, serem encontrados até 8 nucléolos. Sendo as alterações nucleares descritas freqüentes nos chagásicos crônicos, épossível que sejam a expressão morfológica de importantes interações entre o T. cruzi e o leiomiócito.By the study of histological sections of smooth muscle in the wall of the adrenal vein in human chronic Chagas'disease 18 nuclei were identified in 40 cells parasitized by T. cruzi. With an ocular micrometer two diameters of each nest and their nucleus were taken, obtaining their mean size and standard deviation (SD (25.7 µm ± 17.2 for nest diameters and 12 µm ± 5.3 and 7.5 pm ± 2.82 for the nuclear diameters of the mononucleated and binucleated cells respectively. The relation nucleus diameter/nest diameter was 0.5 ± 0.16. 83.3% of the nests had one nucleus and 16.7% were binucleated. The mean nuclear volume of the parasitized cells was 1204 µm³ ± 807.0 and of the non parasitized smooth muscle cells

  4. Radioactive waste management of the nuclear medicine services; Gestao de rejeitos radioativos em servicos de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Barboza, Alex

    2009-07-01

    Radioisotope applications in nuclear medicine services, for diagnosis and therapy, generate radioactive wastes. The general characteristics and the amount of wastes that are generated in each facility are function of the number of patients treated, the procedures adopted, and the radioisotopes used. The management of these wastes embraces every technical and administrative activity necessary to handle the wastes, from the moment of their generation, till their final disposal, must be planned before the nuclear medicine facility is commissioned, and aims at assuring people safety and environmental protection. The regulatory framework was established in 1985, when the National Commission on Nuclear Energy issued the regulation CNEN-NE-6.05 'Radioactive waste management in radioactive facilities'. Although the objective of that regulation was to set up the rules for the operation of a radioactive waste management system, many requirements were broadly or vaguely defined making it difficult to ascertain compliance in specific facilities. The objective of the present dissertation is to describe the radioactive waste management system in a nuclear medicine facility and provide guidance on how to comply with regulatory requirements. (author)

  5. Experimental study of water flow in nuclear fuel elements; Estudo experimental do escoamento de agua em elementos combustiveis nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Rodrigues, Lorena Escriche, E-mail: ler@cdtn.br [Centro Federal de Educacao Tecnologica de Minas Gerais (CEFET), Belo Horizonte, MG (Brazil); Rezende, Hugo Cesar; Mattos, Joao Roberto Loureiro de; Barros Filho, Jose Afonso; Santos, Andre Augusto Campagnole dos, E-mail: hcr@cdtn.br, E-mail: jrmattos@cdtn.br, E-mail: jabf@cdtn.br, E-mail: aacs@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2013-07-01

    This work aims to develop an experimental methodology for investigating the water flow through rod bundles after spacer grids of nuclear fuel elements of PWR type reactors. Speed profiles, with the device LDV (Laser Doppler Velocimetry), and the pressure drop between two sockets located before and after the spacer grid, using pressure transducers were measured.

  6. Energia nuclear em um cenário de trinta anos Nuclear energy over a 30-year scenario

    Directory of Open Access Journals (Sweden)

    Carlos Feu Alvim

    2007-04-01

    Full Text Available A perspectiva da Energia Nuclear no Brasil é analisada sob os aspectos demanda, custos, ambiental, tecnológico e estratégico. A demanda energética projetada, mesmo para crescimentos abaixo dos desejados e considerando algum esforço de redução da intensidade energética, mostra a necessidade de adicionar energia térmica à geração elétrica, hoje predominantemente hídrica. A energia nuclear deve ter participação nessa geração por motivos econômicos, ambientais, tecnológicos e estratégicos.The perspectives of nuclear energy in Brazil is analyzed regarding demand, costs, environmental, technological and strategic aspects. The projected energy demand, even for a growth rate below the desired one and considering some efforts relative to energy intensity reduction, shows the need of adding thermal energy to electricity generation, now predominantly hydraulic. Nuclear energy should have a share in this generation due to economical, environmental, technological and strategic reasons.

  7. Radioactive waste management of the nuclear medicine services; Gestao de rejeitos radioativos em servicos de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Barboza, Alex

    2009-07-01

    Radioisotope applications in nuclear medicine services, for diagnosis and therapy, generate radioactive wastes. The general characteristics and the amount of wastes that are generated in each facility are function of the number of patients treated, the procedures adopted, and the radioisotopes used. The management of these wastes embraces every technical and administrative activity necessary to handle the wastes, from the moment of their generation, till their final disposal, must be planned before the nuclear medicine facility is commissioned, and aims at assuring people safety and environmental protection. The regulatory framework was established in 1985, when the National Commission on Nuclear Energy issued the regulation CNEN-NE-6.05 'Radioactive waste management in radioactive facilities'. Although the objective of that regulation was to set up the rules for the operation of a radioactive waste management system, many requirements were broadly or vaguely defined making it difficult to ascertain compliance in specific facilities. The objective of the present dissertation is to describe the radioactive waste management system in a nuclear medicine facility and provide guidance on how to comply with regulatory requirements. (author)

  8. Fish cultures in the area of the nuclear power station Dukovany and their prospects

    International Nuclear Information System (INIS)

    Penaz, M.

    1980-01-01

    The results of investigating the fishery production and measurements of radiation background in the ecosystem of the Jihlava river, in the area of a nuclear power station being built near Dukovany are evaluated with regard to the prospects of fish cultures when the power station operates in full extent. Basic data were provided for calculating the burden of significant groups of the population, resulting from the ingestion of fish of local provenance. All available information shows that under normal operating conditions, the power station should not exert a negative influence on the quality of fish food and that in the area under study it would be possible to manage intensive fish cultures. (author)

  9. Nuclear criticality safety analysis summary report: The S-area defense waste processing facility

    International Nuclear Information System (INIS)

    Ha, B.C.

    1994-01-01

    The S-Area Defense Waste Processing Facility (DWPF) can process all of the high level radioactive wastes currently stored at the Savannah River Site with negligible risk of nuclear criticality. The characteristics which make the DWPF critically safe are: (1) abundance of neutron absorbers in the waste feeds; (2) and low concentration of fissionable material. This report documents the criticality safety arguments for the S-Area DWPF process as required by DOE orders to characterize and to justify the low potential for criticality. It documents that the nature of the waste feeds and the nature of the DWPF process chemistry preclude criticality

  10. 2006 EM300 and EM3002D Multibeam Sonar Data from Cruise Hi'ialakai HI-06-01 - Pacific Remote Island Areas

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — EM300 and EM3002D multibeam Data were collected from 15 Jan - 6 Feb 2006 aboard NOAA Ship Hi'ialakai at Johnston Island, Howland Island, and Baker Island in the...

  11. Aerial radiological survey of the Three Mile Island Nuclear Station and surrounding area, Middletown, Pennsylvania

    International Nuclear Information System (INIS)

    Colton, D.P.

    1983-08-01

    An aerial radiological survey was performed over the area surrounding the Three Mile Island Nuclear Station during October 26 to 30, 1982. The survey covered an 82-square-kilometer area centered on the nuclear plant and encompassed the communities of Middletown, York Haven, Goldsboro and Royalton, Pennsylvania. The highest radiation exposure rates, up to a maximum of 200 microroentgens per hour (μR/h), were inferred from data measured directly over the TMI facilities. This detected radiation was due to the presence of cobalt-58, cobalt-60 and cesium-137, which was consistent with normal plant operations. Similar activity is routinely observed in aerial surveys over nuclear power plants which have been or are presently in an operational mode. For the remainder of the survey area, the inferred radiation exposure rates varied from 6 to 14 μR/h. The reported exposure rate values include an estimated cosmic ray contribution of 3.7 μR/h. Ground-based measurements, conducted during the time of the aerial survey, were compared to the aerial results. Pressurized ionization chamber readings and a group of soil samples were acquired at several locations within the survey area, along the river banks upstream and downstream of the survey area, and at the ground-based locations used for a previous aerial survey which was conducted in 1976. The exposure rate values obtained from these measurements were in agreement with the corresponding aerial data. With the exception of the activity observed within the TMI facilities, no evidence of any contamination which might have occurred as a result of past reactor operations or the 1979 TMI Unit 2 accident was detected from the aerial survey data. This was further supported by the results of the soil sample analyses and the comparison with the 1976 aerial survey data. 7 references, 12 figures, 4 tables

  12. Agentes de saúde em comunidades urbanas Community-based health workers in urban areas

    Directory of Open Access Journals (Sweden)

    João Cláudio L. Fernandes

    1992-06-01

    Full Text Available A utilização de agentes comunitários nos programas de atenção primária à saúde é uma experiência amplamente difundida, principalmente nos países do Terceiro Mundo. É importante, entretanto, discriminar o perfil de atuação destes agentes em função da área onde atuam, principalmente no que diz respeito às diferenças entre o meio rural e o urbano. A simples substituição de profissionais de medicina, odontologia, psicologia etc, por agentes comunitários pode significar uma abordagem limitada do conceito de atenção primária, levando ao desenvolvimento de modelos assistenciais distintos, determinados em função da classe social a que se dirigem. Neste artigo, é apontada a necessidade de formação de recursos humanos de nível superior para a atenção primária à saúde, buscando-se também identificar o lugar dos agentes comunitários nesta área, sua especificidade técnica, bem como alguns obstáculos percebidos neste campo profissional.The employment of community-based health workers (CHWs in primary health care projects is a widespread experience, mainly in Third World countries. However, it is important to differentiate between the rural and urban profiles of these professionals. The replacement of medical/odontological/psychological professionals by CHWs alone may represent a limited approach to primary health care problems, leading to the development of different health care patterns, depending on the social class they are addressed. This paper points to need for the qualification of high-level health personnel also trying to identify the location of CHWs in this field, their technical specificity, as well as some difficulties observed in this practice.

  13. Construction of sustainability indicators for Nuclear Area Innovation and Research Institutes in Brazil

    International Nuclear Information System (INIS)

    Alves, Simone Fonseca

    2017-01-01

    The dissertation consists of a construction of appropriate sustainability indicators for nuclear area innovation and research institutes in Brazil. In order to do so, the results of the construction process, as well as, the perception of the population that resides in the area surrounding this type of institute are presented and discussed. As reference for this case study, the Nuclear Technology Development Center (CDTN) was chosen. It is located in Pampulha, more specifically, on the campus of the Federal University of Minas Gerais (UFMG), Belo Horizonte, MG, Brazil. One of the methodological processes present in this research is the Delphi method, because it is the most used in the construction of indicators. Its application in this work allowed obtaining the of specialist group opinions collected through a questionnaire. Initially, sixty-nine sustainability indicators were considered. They were distributed among the environmental, economic, socio cultural and institutional dimensions, some of which were obtained through lists of indicators pointed by literature review. Other indicators were built through discussions with groups from the nuclear, environmental, economic and socio cultural areas. Among the set of indicators investigated, twenty-six were selected as being the most relevant. A questionnaire was then applied to one hundred and twenty individuals living in the vicinity of the CDTN. Discrepancies were found during the analysis the opinions of the experts in relation to sustainability dimensions proposed, as well as, indicators of the same dimensions were varied. However, the opinion of the population and the opinion of the experts had similar results. Finally, this study is the first proposal for the nuclear sector to construct this kind of indicator that takes into account the evaluation of experts and the opinion of the community that resides around these institutions. (author)

  14. Information dissemination in nuclear energy: ideology, speech and language; Divulgacao da informacao em energia nuclear: ideologia, discurso e linguagem

    Energy Technology Data Exchange (ETDEWEB)

    Ramos, Marcos Goncalves

    1992-07-01

    The social impact of Goiania nuclear accident is analysed from a semiotic investigation upon papers issued on popular magazines, newspapers and scientific periodicals. Also the communication of Science Information is discussed through three basic models: diffusionist, bibliometric and cultural perspectives. Divulgation and diffusion process of scientific information are reviewed on the bases of theory of representation and theory of sign. The relationship between energy and society is discussed though a compared analysis upon the information sources available to public and scientific community. (author)

  15. Floating nuclear power plants and associated technologies in the Northern areas

    International Nuclear Information System (INIS)

    Dowdall, M.; Standring, W.J.F.

    2008-12-01

    Although floating nuclear power plants are not a new concept, all indications are that Russia, amongst other countries, has identified FNPP's (floating nuclear power plants) as one of a range of potential power solutions for both the domestic and international commercial market, utilising LCNPP's (low-capacity nuclear power plants). This focus on LCNPP's in general and LCNPP's in particular appears to be a key part of Russia's positioning of itself as a future leader in the global nuclear energy market. Given the fact that much of the support infrastructure for Russia's existing civilian nuclear fleet is located in the northern regions, the development of FNPP's as part of the nuclear industry is a matter of some interest to a number of countries including Norway. Although FNPP technology is not new, the business models being proposed to effectively commercialise FNPP's as a product on the international market are somewhat novel. This novelty may place FNPP's in a relatively grey area with respect to international laws and regulations. This situation is however also a product of recent developments and initiatives regarding the global nuclear industry and how it operates in the 21st century and the consideration of such business models by countries other than Russia means that it may not be unique to either FNPP's or Russia. A review of the available information indicates that FNPP's may be constructed, located and operated in the Russian Arctic region for a variety of purposes (civilian power/heat generation, resource extraction etc.) as well as being made available for export internationally for purposes such as desalination. Russia is and has been engaged in marketing of such systems to a wide range of potential customers. Information as to potential FNPP technologies is available from a range of sources which indicate a suite of potential designs that may be used in FNPP systems. The nature of these plants, with respect to operation, life cycle, waste handling

  16. Floating nuclear power plants and associated technologies in the Northern areas

    Energy Technology Data Exchange (ETDEWEB)

    Dowdall, M.; Standring, W.J.F.

    2008-12-15

    Although floating nuclear power plants are not a new concept, all indications are that Russia, amongst other countries, has identified FNPP's (floating nuclear power plants) as one of a range of potential power solutions for both the domestic and international commercial market, utilising LCNPP's (low-capacity nuclear power plants). This focus on LCNPP's in general and LCNPP's in particular appears to be a key part of Russia's positioning of itself as a future leader in the global nuclear energy market. Given the fact that much of the support infrastructure for Russia's existing civilian nuclear fleet is located in the northern regions, the development of FNPP's as part of the nuclear industry is a matter of some interest to a number of countries including Norway. Although FNPP technology is not new, the business models being proposed to effectively commercialise FNPP's as a product on the international market are somewhat novel. This novelty may place FNPP's in a relatively grey area with respect to international laws and regulations. This situation is however also a product of recent developments and initiatives regarding the global nuclear industry and how it operates in the 21st century and the consideration of such business models by countries other than Russia means that it may not be unique to either FNPP's or Russia. A review of the available information indicates that FNPP's may be constructed, located and operated in the Russian Arctic region for a variety of purposes (civilian power/heat generation, resource extraction etc.) as well as being made available for export internationally for purposes such as desalination. Russia is and has been engaged in marketing of such systems to a wide range of potential customers. Information as to potential FNPP technologies is available from a range of sources which indicate a suite of potential designs that may be used in FNPP systems. The nature of these plants

  17. Strategic areas for non-electric application of nuclear energy in Indonesia

    International Nuclear Information System (INIS)

    Sasmojo, S.; Subki, I.R.; Lasman, A.N.

    1997-01-01

    An attempt is made to identify strategic areas, whereby non-electric application of nuclear energy may be justified. Subject to further evaluation, particularly on the economic aspects, non-electric application of nuclear energy in Indonesia may have justifiable strategic role in the long term sustainability of the development of the country. The key arguments are: (a) within not too far distant future, domestic resources constraints of oil and natural gas will strongly be felt, especially if the current trend in the rate of production of the two commodities has to be maintained to satisfy the growing demand for energy and to secure foreign exchange earning; (b) nuclear option, in concurrent with coal and biomass options, can provide the need for heat supply required to undertake strategic schemes for (i) improving oil production capacity; (ii) prolong the availability of oil and natural gas by displacing their uses as heat sources in industry, whenever appropriate; (iii) coal conversion to synthetic natural gas (SNG), or synthesis gas, to substitute or at least supplement the use of natural gas as industrial chemical feedstock; and (iv) sea water desalination by evaporation, to overcome shortage of fresh drinking and industrial water supply, as well as to secure its reliability and availability. In terms of carbon emission to the atmosphere, the nuclear option offers an interesting choice. In view of those, serious consideration for further technical assessment, and thorough evaluation on the economic viability and social acceptability for the option is recommended. (author). 7 refs, 5 figs, 2 tabs

  18. Web design and development for centralize area radiation monitoring system in Malaysian Nuclear Agency

    Science.gov (United States)

    Ibrahim, Maslina Mohd; Yussup, Nolida; Haris, Mohd Fauzi; Soh @ Shaari, Syirrazie Che; Azman, Azraf; Razalim, Faizal Azrin B. Abdul; Yapp, Raymond; Hasim, Harzawardi; Aslan, Mohd Dzul Aiman

    2017-01-01

    One of the applications for radiation detector is area monitoring which is crucial for safety especially at a place where radiation source is involved. An environmental radiation monitoring system is a professional system that combines flexibility and ease of use for data collection and monitoring. Nowadays, with the growth of technology, devices and equipment can be connected to the network and Internet to enable online data acquisition. This technology enables data from the area monitoring devices to be transmitted to any place and location directly and faster. In Nuclear Malaysia, area radiation monitor devices are located at several selective locations such as laboratories and radiation facility. This system utilizes an Ethernet as a communication media for data acquisition of the area radiation levels from radiation detectors and stores the data at a server for recording and analysis. This paper discusses on the design and development of website that enable all user in Nuclear Malaysia to access and monitor the radiation level for each radiation detectors at real time online. The web design also included a query feature for history data from various locations online. The communication between the server's software and web server is discussed in detail in this paper.

  19. Deployment evaluation methodology for the electrometallurgical treatment of DOE-EM spent nuclear fuel

    International Nuclear Information System (INIS)

    Dahl, C.A.; Adams, J.P.; Ramer, R.J.

    1998-07-01

    Part of the Department of Energy (DOE) spent nuclear fuel (SNF) inventory may require some type of treatment to meet acceptance criteria at various disposition sites. The current focus for much of this spent nuclear fuel is the electrometallurgical treatment process under development at Argonne National Laboratory. Potential flowsheets for this treatment process are presented. Deployment of the process for the treatment of the spent nuclear fuel requires evaluation to determine the spent nuclear fuel program need for treatment and compatibility of the spent nuclear fuel with the process. The evaluation of need includes considerations of cost, technical feasibility, process material disposition, and schedule to treat a proposed fuel. A siting evaluation methodology has been developed to account for these variables. A work breakdown structure is proposed to gather life-cycle cost information to allow evaluation of alternative siting strategies on a similar basis. The evaluation methodology, while created specifically for the electrometallurgical evaluation, has been written such that it could be applied to any potential treatment process that is a disposition option for spent nuclear fuel. Future work to complete the evaluation of the process for electrometallurgical treatment is discussed

  20. Sustainability indicators for innovation and research institutes of nuclear area in Brazil

    International Nuclear Information System (INIS)

    Alves, S.F.; Barreto, A.A.; Rodrigues, P.C.H.; Feliciano, V.M.D.

    2016-01-01

    Indicators are relevant tools for measuring sustainability process. In this study, the relevance of sustainability indicators appropriate for research and innovation institutes in Brazil is discussed. As reference for case study, nuclear research and innovation institutes were chosen. Sixty-nine sustainability indicators were considered. Some of these indicators were obtained from lists in the literature review, distributed between the dimensions environmental, economic, social, cultural and institutional. The other indicators were developed through discussions between professionals from nuclear, environmental, economic, social and cultural areas. Among the investigated indicators, 32 were selected as being the most relevant. Discrepancies were found during the analysis the opinions of the experts in relation to sustainability dimensions proposed. (author)

  1. User requirements in the area of safety of innovative nuclear reactors and fuel cycle installations

    International Nuclear Information System (INIS)

    Kuczera, B.; Juhn, P.E.; Fukuda, K.; )

    2002-01-01

    Full text: Against the background of already existing IAEA and INSAC publications in the area of safety, in the framework of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) a set of user requirements for the safety of future nuclear installations has been established. Five top-level requirements are expected to apply to any type of innovative design. They should foster an increased level of safety that is transparent to and fully accepted by the general public. The approach to future reactor safety includes two complementary strategies: increased emphasis on inherent safety characteristics and enhancement of defense in depth. As compared to existing plants, the effectiveness of preventing measures should be highly enhanced, resulting in fewer mitigation measures. The targets and possible approaches of each of the five levels of defense developed for innovative reactor designs are outlined in the paper

  2. Radiation protection during backfitting or dismantling work in the controlled area of nuclear facilities

    International Nuclear Information System (INIS)

    Baumann, J.; Kausch, S.; Palmowski, J.

    1980-01-01

    Backfitting measures or dismantling activities within the controlled area put special requirements on radiological protection. This is to be shown by the example of the following cases. Sanitation of the general decontamination services of the Karlsruhe Nuclear Research Center; waste water, equipment decontamination, incineration and packaging facility; dismantling and disposal of high-radiation components including decontamination of buildings of the Eurochemic reprocessing plant at Mol; reconstruction of the HDR plant for safety experiments together with waste management for components and systems, as e.g. pressure vessel internals, pipes etc.; exchange of the steam dryer and the water separator including planning of the conditioning process in the Wuergassen nuclear power plant. This lecture deals with the engineering and organizational problems, especially accounting for radiological protection and enters into planning of measures for radiological protection, their organization and execution, problems of direct and remote-controlled work also being discussed. The question of personnel qualification is also commented on. (orig.) [de

  3. Aspects of supervision of the clearance of nuclear fuel production sites in the Hanau area

    International Nuclear Information System (INIS)

    Hummel, L.; Ibach, T.M.; Lehmann, K.-H.

    2002-01-01

    Five nuclear fuel production facilities in the Hanau area are shut down and have to be dismantled. The activities and the licenses for these activities are carried out and issued step by step. In charge of the licensing authorities, TUeV Sueddeutschland evaluated clearance limits as far as they were not given by law and carried out the on-site supervision. This includes independent measurements, the control of a safe clearance strategy and the solution of the specific problems that arise by the characteristics of nuclear fuel. These problems were solved, mainly by specific gamma spectrometric measuring and evaluation techniques, such as adapted in situ spectrometry and a conveyor belt device. At the end of this process is a green field or a site with buildings which can be re-used for purposes not subject to the atomic law. (author)

  4. Quality control related to total quality: why not to nuclear area too?

    International Nuclear Information System (INIS)

    Vasques, R.J.

    1992-01-01

    We're living in a new economical age, where quality, productivity, competence, competitiveness and costumer satisfaction are necessary. We must develop our capacity more and more, daily, for could survive and to excel in this new age. Only through Total Quality Control (TQC) is that we'll go to achieve these requirements. TQC is expanding all over the world and is already, the new universal language. Why not get the TQC's benefits to nuclear area too? We must stay within this reality. With our quality assurance systems turned to TQC, certainly we'll get best results. This is the intention of this paper: to call the nuclear professionals attention to knowledge, application and commitment to TQC's philosophy. (author)

  5. Generating a quality management system for application in the field of management of nuclear energy area

    International Nuclear Information System (INIS)

    Fernández, L.; Arias, M.

    2013-01-01

    The actual work has as a main objective to present the development of a quality management system to be applicable to the Nuclear Energy Management confines at the National Atomic Energy Commission (CNEA) in Argentina Republic. The GAEN Quality Management Section (SGC) has as main central tasks to streamline, collaborate and facilitate the development of activities and their applications on quality management systems in all the sections and projects belonging to GAEN. This achievement will tend to accredit, certificate and qualify them. Groups of work cooperating with each other integrate the GAEN. They are at present dealing with several tasks. Some outstanding ones are research activities, technology development, design, engineering, assembling, starting, services, and human resources development on Nuclear Reactors and Nuclear Supplies, particularly on powerful nuclear reactors. In 2012, at the annual CNEA Presidential meeting, it was presented one of the several projects from the SGC. It consists in the development of a quality management system available to every area belonging to the GAEN. To carry this project out, it was first begun with the elaboration of Guide Documents which were available for everybody. The documents establish the criteria and general requirements for obtaining guaranteed quality results about the performed activities. At the same time, several areas, sections and Management groups of work have been working united and well-disposed towards the application on their own Management System using the Guide Documents and considering, in addition, some own regards. In conclusion, this first step shows that the developed work facilitates the implementation of Management Systems around the GAEN. (author)

  6. A Program for Cultivating Nuclear Talent at Engineering Educational Institute in a Remote Area from Nuclear Power Plants

    Science.gov (United States)

    Takahashi, Tsuyoshi

    Recently, in Japan, the number of students who hope for finding employment at the nuclear power company has decreased as students‧ concern for the nuclear power industry decreases. To improve the situation, Ministry of Education, Culture, Sports, Science and Technology launched the program of cultivating talent for nuclear power which supports research and education of nuclear power in the academic year of 2007. Supported by the program, Kushiro College of Technology conducted several activities concerning nuclear power for about a year. The students came to be interested in nuclear engineering through these activities and its results.

  7. A proactive method for safety management in nuclear facilities; Um metodo proativo para gerenciamento da seguranca em instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Grecco, Claudio Henrique dos Santos; Carvalho, Paulo Victor Rodrigues de; Santos, Isaac Antonio Luquetti dos, E-mail: grecco@ien.gov.br, E-mail: paulov@ien.gov.br, E-mail: luquetti@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN/RJ), Rio de Janeiro, RJ (Brazil). Div. de Instrumentacao e Confiabilidade Humana

    2014-07-01

    Due to the modern approach to address the safety of nuclear facilities which highlights that these organizations must be able to assess and proactively manage their activities becomes increasingly important the need for instruments to evaluate working conditions. In this context, this work presents a proactive method of managing organizational safety, which has three innovative features: 1) the use of predictive indicators that provide current information on the performance of activities, allowing preventive actions and not just reactive in safety management, different from safety indicators traditionally used (reactive indicators) that are obtained after the occurrence of undesired events; 2) the adoption of resilience engineering approach in the development of indicators - indicators are based on six principles of resilience engineering: top management commitment, learning, flexibility, awareness, culture of justice and preparation for the problems; 3) the adoption of the concepts and properties of fuzzy set theory to deal with subjectivity and consistency of human trials in the evaluation of the indicators. The fuzzy theory is used primarily to map qualitative models of decision-making, and inaccurate representation methods. The results of this study aim an improvement in performance and safety in organizations. The method was applied in a radiopharmaceutical shipping sector of a nuclear facility. The results showed that the method is a good monitoring tool objectively and proactively of the working conditions of an organizational domain.

  8. The Sustainable Nuclear Future: Fission and Fusion E.M. Campbell Logos Technologies

    Science.gov (United States)

    Campbell, E. Michael

    2010-02-01

    Global industrialization, the concern over rising CO2 levels in the atmosphere and other negative environmental effects due to the burning of hydrocarbon fuels and the need to insulate the cost of energy from fuel price volatility have led to a renewed interest in nuclear power. Many of the plants under construction are similar to the existing light water reactors but incorporate modern engineering and enhanced safety features. These reactors, while mature, safe and reliable sources of electrical power have limited efficiency in converting fission power to useful work, require significant amounts of water, and must deal with the issues of nuclear waste (spent fuel), safety, and weapons proliferation. If nuclear power is to sustain its present share of the world's growing energy needs let alone displace carbon based fuels, more than 1000 reactors will be needed by mid century. For this to occur new reactors that are more efficient, versatile in their energy markets, require minimal or no water, produce less waste and more robust waste forms, are inherently safe and minimize proliferation concerns will be necessary. Graphite moderated, ceramic coated fuel, and He cooled designs are reactors that can satisfy these requirements. Along with other generation IV fast reactors that can further reduce the amounts of spent fuel and extend fuel resources, such a nuclear expansion is possible. Furthermore, facilities either in early operations or under construction should demonstrate the next step in fusion energy development in which energy gain is produced. This demonstration will catalyze fusion energy development and lead to the ultimate development of the next generation of nuclear reactors. In this presentation the role of advanced fission reactors and future fusion reactors in the expansion of nuclear power will be discussed including synergies with the existing worldwide nuclear fleet. )

  9. Area effect on galvanic corrosion of condenser materials with titanium tubes in nuclear power plants

    International Nuclear Information System (INIS)

    Hwang, Seong Sik; Kim, Joung Soo; Kim, Uh Chul

    1993-01-01

    Titanium tubes have recently been used in condensers of nuclear power plants since titanium has very good corrosion resistance to seawater. However, when it is connected to Cu alloys as tube sheet materials and these Cu alloys are connected to carbon steels as water box materials, it makes significant galvanic corrosion on connected materials. It is expected from electrochemical tests that the corrosion rate of carbon steel will increase when it is galvanically coupled with Ti or Cu in sea water and the corrosion rate of Cu will increase when it is coupled with Ti, of this couple is exposed to sea water for a long time. It is also expected that the surface area ratios, R 1 (surface area of carbon steel/surface area of Ti) and R 2 (surface area of carbon steel/surface area of Cu) are very improtant for the galvanic corrosion of carbon steel and that these should not be kept to low values in order to minimize the galvanic corrosion on the carbon steel of the water box. Immersed galvanic corrosion tests show that the corrosion rate of carbon steel is 4.4 mpy when this ratio is 10 -2 . The galvanic corrosion rate of this carbon steel is increased from 4.4 mpy to 13 mpy at this area ratio, 1, when this connected galvanic specimen is galvanically coupled with a Ti tube. This can be rationalized by the combined effects of R 1 and R 2 on the polarization curve. (Author)

  10. Cancer incidence in an area contaminated with radionuclides near a nuclear installation

    International Nuclear Information System (INIS)

    Johnson, C.J.

    1981-01-01

    Exposures of a large population in the Denver area to plutonium and other radionuclides in the exhaust plumes from the Rocky Flats (nuclear weapons) plant date back to 1953. Anglo cancer incidence in 1969-1971 was evaluated in census tracts with and without contamination in the Denver area (1970 pop. 1 019 130). Cancer incidence in males was 24% higher, and in females, 10% higher in the suburban area(pop. 154 170) with most contamination nearest the plant, compared to the unexposed area (pop. 423 870), also predominantly suburban, which had virtually the same age-adjusted incidence rate for all cancer as the state. Excess cases of cancer were due to more cases than expected of leukemia, lymphoma and myeloma and cancer of the lung, thyroid, breast, esophagus, stomach and colon, a pattern similar to that obs- erved in the survivors of Hiroshima and Nagasaki. The ratio of these cancers to all other cancer was 17.6% higher in males and 11.9% higher in females in the area near the plant. Cancer of the gonads (especially the testes), liver, and, in females, pancreas and brain contributed to the higher incidence of all cancer in areas near the plant. (Auth.)

  11. Weed control in young coffee plantations through post emergence herbicide application onto total area Controle de plantas daninhas em cafezais recém-implantados, com herbicidas aplicados em pós-emergência em área total

    Directory of Open Access Journals (Sweden)

    C.P. Ronchi

    2004-12-01

    at doses recommended for bean crop, these herbicides may be applied to control weeds in coffee and bean intercropping systems by spraying the entire area.Este trabalho foi realizado com o objetivo de investigar, em campo, a eficiência de vários herbicidas aplicados em pós-emergência em área total no controle de plantas daninhas, em cafezais recém-implantados e no consórcio de café e feijão, assim como seus efeitos sobre essas culturas. Mudas de Coffea arabica, cultivar Catuaí Vermelho, com quatro a seis pares de folhas foram transplantadas para o campo e cultivadas segundo práticas agronômicas usuais. O consórcio de café e feijão foi obtido por meio do plantio de três linhas de feijão nas entrelinhas do cafezal. Quando os herbicidas foram aplicados sobre as culturas, as plantas de café estavam com seis a dez pares de folhas, as de feijão com três folíolos e as plantas daninhas no estádio inicial de desenvolvimento. Fluazifop-p-butil e clethodim foram seletivos às plantas de café e controlaram eficientemente Brachiaria plantaginea e Digitaria horizontalis. Plantas daninhas dicotiledôneas (Amaranthus retroflexus, Bidens pilosa, Coronopus didymus, Emilia sonchifolia, Galinsoga parviflora, Ipomoea grandifolia, Lepidium virginicum e Raphanus raphanistrum foram controladas eficientemente por aplicações isoladas de fomesafen, flazasulfuron e oxyfluorfen, com exceção de B. pilosa, C. didymus e R. raphanistrum para o oxyfluorfen. Aplicações seqüenciais com intervalos de sete dias de fomesafen + fluazifop-p-butil ou clethodim, e as duas misturas comerciais de fomesafen + fluazifop-p-butil controlaram simultaneamente ambos os tipos de plantas daninhas. Cyperus rotundus foi controlada apenas por flazasulfuron. Com exceção de fluazifop-p-butil e clethodim todos os demais tratamentos herbicidas provocaram apenas leves injúrias às folhas mais novas das plantas de café. Contudo, o crescimento das plantas não foi prejudicado, de forma que tanto a

  12. International Cooperation in the Area of Nuclear Safety Regulation: Current Status and Way Forward

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, J. W.; Byeon, M. J.; Lee, J. M.; Lim, J. H. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2016-10-15

    Global effort and initiatives undertaken after the Fukushima Daiichi accident was the adoption of the Vienna Declaration on Nuclear Safety in February 2015. The Contracting Parties to the Convention on Nuclear Safety (CNS) collaboratively prepared the documentation of the Declaration and unanimously adopted it with the idea to prevent accidents with radiological consequences and to mitigate such consequences should they occur. The OECD/NEA has been working closely with its member and partner countries to identify lessons learnt and follow-up actions at the national and international levels so as to maintain and enhance the level of safety at nuclear facilities following the Fukushima Daiichi nuclear power plant accident. In 2013, the NEA published a report entitled The Fukushima Daiichi Nuclear Power Plant Accident: OECD/NEA Nuclear Safety Response and Lessons Learnt detailing the key immediate responses of the NEA and its member countries. Subsequent to the publish of the report and based on the lessons presented, NEA published a new report entitled Five Years after the Fukushima Daiichi Accident: Nuclear Safety Improvements and Lessons Learnt, focusing on what has been done by the Agency and its member countries to improve safety since the accident in 2011. cooperation based on the needs of technical area would further enhance effectiveness of cooperative activities and would enable to foresee future regulatory needs which can be considered when establishing a strategy. Since the establishment of NSSC in 2011, NSSC has played a major role in concluding agreements with regulatory bodies of other countries. Despite of the change, KINS, yet, is able to pursue technical-specified cooperation as a TSO under the umbrella of agreements between governments or regulatory bodies. establishment of expert pool and systematic mid- and long-term capacity building framework of relevant experts would enhance continuity and expertise. Currently, most of the participants or

  13. High resolution spectroscopy in solids by nuclear magnetic resonance; Espectroscopia de alta resolucao em solidos por ressonancia magnetica nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Bonagamba, T J

    1991-07-01

    The nuclear magnetic resonance (NMR) techniques for High Resolution Spectroscopy in Solids are described. Also the construction project of a partially home made spectrometer and its applications in the characterization of solid samples are shown in detail. The high resolution spectrometer used is implemented with the double resonance multiple pulses sequences and magic angle spinning (MAS) and can be used with solid and liquid samples. The maximum spinning frequency for the MAS experiment is in excess of 5 Khz, the double resonance sequences can be performed with any type of nucleus, in the variable temperature operating range with nitrogen gas: -120{sup 0} C to +160{sup 0} C, and is fully controlled by a Macintosh IIci microcomputer. (author).

  14. Nuclear reactors transients identification and classification system; Sistema de identificacao e classificacao de transientes em reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Bianchi, Paulo Henrique

    2008-07-01

    This work describes the study and test of a system capable to identify and classify transients in thermo-hydraulic systems, using a neural network technique of the self-organizing maps (SOM) type, with the objective of implanting it on the new generations of nuclear reactors. The technique developed in this work consists on the use of multiple networks to do the classification and identification of the transient states, being each network a specialist at one respective transient of the system, that compete with each other using the quantization error, that is a measure given by this type of neural network. This technique showed very promising characteristics that allow the development of new functionalities in future projects. One of these characteristics consists on the potential of each network, besides responding what transient is in course, could give additional information about that transient. (author)

  15. Development of an area monitor for neutrons using solid state nuclear track detector; Desenvolvimento de um monitor de area para neutrons utilizando detector solido de tracos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zahn, G.S.

    1994-12-31

    An area monitor for neutrons composed of the solid state nuclear track detector (SSNTD) Makrofol DE, together with a (n,{alpha}) converter, in the center of a 25 cm diameter polyethylene sphere, is developed. The optimal electrochemical etching conditions for the detection of thermal neutrons by the Makrofol DE using the BN converter are studied, leading to the choice of 55 min, at 30{sup 0} C, under a 44,2 kV.cm{sup -1} electric field with oscillation frequency of 2,0 khz. The response of this system to thermal neutrons, in the optimal conditions, is of 2,76(10)x 10{sup -3} tr/n. Changing from the BN converter to a 2,73(3)g compressed boric acid tablet this value lowers to 3,88(17)x 10{sup -4} tr/n. The performance of the whole monitor in the detection of fast neutrons is examined using the BN converter and neutrons from a {sup 241} Am Be source, with a response of 4,4(2)x 10{sup 3} tr.mSv{sup -1}.cm{sup -2} and operational limits between 7(3){mu}Sv and 5,6(2)mSv. The result of the monitoring of the control room of the IPEN Cyclotron accelerator are also presented as a final test for the viability of the practical use of the monitor. (author). 34 refs, 15 figs, 6 tabs, 1 app.

  16. Measurement of Nuclear Interaction Rates in Crystal Using the CERN-SPS North Area Test Beams

    CERN Document Server

    Losito, R; Taratin, A

    2010-01-01

    A number of tests were performed in the North area of the SPS in view of investigating crystal-particles interactions for future application in hadron colliders. The rate of nuclear interactions was measured with 400 GeV proton beams directed into a silicon bent crystal. In this way the background induced by the crystal either in amorphous or in channeling orientation was revealed. The results provide fundamental information to put in perspective the use of silicon crystals to assist halo collimation in hadron colliders, whilst minimizing the induced loss.

  17. Two designs for image digital processing applications in the nuclear area using ImaWin

    International Nuclear Information System (INIS)

    Lavagnino, Carlos E.; Marajofsky, Adolfo

    1999-01-01

    In this work two designs of image processing systems of low cost for the nuclear area are presented. They have the advantage of the adaptability given by the ImaWin software and the connection with Internet, applied to digitalisation in research and development fields. The first design is the development of a digitalisation system for inspection and study of fuel plate radiographs for test reactors, while the second one describes the specification and design of an intelligent system of intrusion signals continuous inspection and administrative control of fissile material deposits. (author)

  18. Acceptance analysis for a large area monopole experiment using nuclear track detectors

    International Nuclear Information System (INIS)

    Hasegan, Monica; Popa, V.

    1998-01-01

    In this paper, we discuss the acceptance of a horizontal plane of 1000 m 2 nuclear track detector for an anisotropic flux of GUT magnetic monopoles (MM) with m MM ∼ 10 16 GeV and g = g D , 2g D , 3g D , considering the monopole energy loss in Earth. It is estimated that a large area experiment for the search of GUT monopoles that uses such detectors and would operate a reasonable number of years could reach a sensitivity of the order of few 10 -17 cm -2 s -1 sr -1 . (authors)

  19. Aerial radiological survey of the area surrounding the Edwin I. Hatch Nuclear Plant, Baxley, Georgia

    International Nuclear Information System (INIS)

    Hilton, L.K.

    1978-11-01

    An airborne radiological survey of a 2146 km 2 area surrounding the Edwin I. Hatch Nuclear Plant was made 28-31 March 1977. Detected radioisotopes, and their associated gamma ray exposure rates, were consistent with that expected from the normal background emitters. Count rates observed at 152 m altitude are converted to equivalent exposure rates at 1 m above the ground, and are presented in the form of an isopleth map. Exposure rates measured with small portable instruments and soil sample analysis showed agreement with the airborne data

  20. An aerial radiological survey of the Saxton Nuclear Experimental Corporation facility and surrounding area, Saxton, Pennsylvania

    International Nuclear Information System (INIS)

    Hoover, R.A.

    1991-10-01

    An aerial radiological survey was conducted during the period July 5 to 22, 1989, over an 83-square kilometer (32-square-mile) area surrounding the Saxton Nuclear Experimental Corporation (SNEC) facility which is owned by General Public Utilities and located near Saxton, Pennsylvania. The survey was conducted at a nominal altitude of 61 meters (200 feet) with line spacings of 91 meters (300 feet). A contour map of the terrestrial gamma exposure rate extrapolated to 1 meter above ground level (AGL) was prepared and overlaid on an aerial photograph and a set of United States Geological Survey (USGS) topographic maps of the area. The terrestrial exposure rates varied from about 9 to 11 microroentgens per hour (μR/h) over most of the survey area. The levels over the SNEC family did not differ from the exposure rates seen over the entire survey area. Cesium-137 (Cs-137) levels typical of worldwide fallout deposition were detected throughout the surveyed area. No other trends of Cs-137 were observed. Soil samples and pressurized ion chamber measurements were obtained at six locations within the survey boundaries to support the aerial data

  1. The recharge area concept: A strategy for siting nuclear waste repositories

    International Nuclear Information System (INIS)

    Sheng, G.; Toth, J.

    2000-01-01

    The Recharge Area Concept is the proposition that in Canadian-Shield type natural environments recharge areas of regional groundwater flow systems are superior for high-level nuclear waste repositories to other types of groundwater flow regimes, especially to areas of groundwater discharge. This conclusion is reached from an analysis of basinal groundwater flow models. The calculations were made for a two-dimensional flank of a fully saturated topographic basin, 20 km long and 4 km deep, in which groundwater is driven by gravity. Variants of hydraulic-conductivity distributions were considered: 1) homogeneous; 2) stratified; and 3) stratified-faulted. The faults attitudes were changed by steps from vertical to horizontal for different variants. The model is assumed conceptually to represent the crystalline-rock environment of the Canadian Shield. The hydrogeologic performances of hypothetical repositories placed 500 m deep in the recharge and discharge areas were characterized by thirteen parameters. The principal advantages of recharge- over discharge-area locations are: 1) longer travel paths and return-flow times from repository to surface; 2) robustness of predicted values of performance parameters; 3) field-verifiability of favourable hydrogeologic conditions (amounting to an implicit validation of the calculated minimum values of return-flow times); 4) site acceptance based on quantifiable and observable flow-controlling parameters; and 5) simple logistics and favourable economics of site selection and screening. As a by-product of modeling, it is demonstrated that the presence of old water is not an indication of stagnancy. (author)

  2. A sedimentation study in the Muda catchment area using nuclear techniques

    International Nuclear Information System (INIS)

    Kamarudin Samuding; Wan Zakaria Wan Muhamad Tahir; Roslan Mohd Ali; Juhari Yusuf

    2002-01-01

    A study on the sediment size distribution and determination of sediment density profile was conducted in a selected area of the Muda Dam catchment area, Kedah. The objective of the study was to establish baseline data of the input sedimentation with regard to the effects of development within the catchment in the future. Three main sampling locations were identified, namely at Sungai Teliang, Sungai Muda and the Muda Reservoir. Results showed that the grain size distribution of sediment generally ranged from clay to gravel size. In the reservoir and downstream the river, most of the samples studied consisted of fine sediment Le, silt and clay (< 63 μm). However, sediment distribution in the upstream section of Sungai Teliang mainly consisted of fine to coarse sand. Based on the sediment distribution profile analysis, the study site could be divided into two parts comprising the dynamic area (region) covering selected locations along the river and the deposited sediment in the reservoir. Measurement of sediment thickness was performed using nuclear gauges, i.e. direct transmission and backscattering methods. The result also showed that the thickness of bed sediment varied from one location to another, whereby the thickness variation could reach up to 0.75 metre in some areas. This study could assist local authorities (AMDA) in identifying the rates and sources of accumulated sediment as well as quality and quantity of water in the study area in order to sustain distribution of good quality water to the farmers. (Author)

  3. Aerial radiological survey of the Joseph M. Farley Nuclear Plant and surrounding area, Dothan, Alabama

    International Nuclear Information System (INIS)

    Maguire, T.C.; Shipman, G.R.

    1982-03-01

    An aerial radiological survey was performed during the period 8 to 19 December 1979 over a 2000 square kilometer area centered on the two unit Joseph M. Farley Nuclear Plant near Dothan, Alabama. Radiological data were collected by flying north-south lines spaced 900 meters apart at an altitude of 150 meters above ground level. Processed data showed that all gamma rays detected within the survey area were those expected from naturally occurring radionuclides. Count rates obtained from the aerial platform were converted to exposure rates at 1 meter above the ground and are presented in the form of a radiation contour map. The observed exposure rates were between 4 and 12 microroentgens per hour (μR/h), with most of the area ranging between 4 and 10 μR/h. These values include an estimated cosmic ray contribution of 4.0 μR/h but do not include any contribution from airborne radionuclides, i.e., radon. Exposure rates obtained from ground measurements taken within the survey area were in close agreement with the aerial data. The data were also in close agreement with those obtained from a similar survey conducted during March 1977. Comparison of the results from both surveys indicated that no detectable change in the radiological characteristics of the survey area has occurred due to the operation of unit number 1 during the intervening period. The same equipment and procedures were utilized for both surveys

  4. An activated barrier for protection of special nuclear materials in vital areas

    International Nuclear Information System (INIS)

    Timm, R.E.; Miranda, J.E.

    1984-01-01

    The Argonne National Laboratory and Sandia National Laboratory have recently installed an activated barrier, the Access Denial System (ADS) for the upgrade of safeguards of special nuclear materials. The technology of this system was developed in the late 70's by Sandia National Laboratory-Albuquerque. The installation was the first for the Department of Energy. Subsequently, two additional installations have been completed. The Access Denial System, combined with physical restraints, provide the system delay. The principal advantages of the activated barrier are: (1) it provides an order of magnitude improvement in delay over that of a fixed barrier, (2) it can be added to existing vital areas with a minimum of renovations, (3) existing operations are minimally impacted, and (4) health and safety risks are virtually nonexistent. Hardening of the vital areas using the ADS was accomplished in a costeffective manner

  5. Activated barrier for protection of special nuclear materials in vital areas

    International Nuclear Information System (INIS)

    Timm, R.E.; Miranda, J.E.; Reigle, D.L.; Valente, A.D.

    1984-01-01

    The Argonne National Laboratory and Sandia National Laboratory have recently installed an activated barrier, the Access Denial System (ADS) for the upgrade of safeguards of special nuclear materials. The technology of this system was developed in the late 70's by Sandia National Laboratory-Albuquerque. The installation was the first for the Department of Energy. Subsequently, two additional installations have been completed. The Access Denial System, combined with physical restraints, provide the system delay. The principal advantages of the activated barrier are: (1) it provides an order of magnitude improvement in delay over that of a fixed barrier, (2) it can be added to existing vital areas with a minimum of renovations, (3) existing operations are minimally impacted, and (4) health and safety risks are virtually nonexistent. Hardening of the vital areas using the ADS was accomplished in a cost-effective manner. 3 references, 1 figure, 1 table

  6. Study on mutual perception between the people living in the area around a nuclear power plant and in a power-consuming area

    International Nuclear Information System (INIS)

    Ueda, Yoshitaka; Sakai, Yukimi; Kita, Hiroyuki

    2009-01-01

    At first we conducted an interview survey of the urban residents, in order to gather various opinions about the area around a nuclear power plant. Then we conducted a questionnaires survey of the urban area to investigate how many people had the same opinions as we had extracted from the interview survey. We also compared these results with the site residents opinion which had been reported in other research. These results show that the urban residents tend to overestimate the risk perception of the local area and the local residents' anxiety about the nuclear power plant, and to underestimate the relationship between the electric company operating nuclear power plant and the local residents. These results also show that the local residents tend to underestimate the urban residents' knowledge of a nuclear power plant, and to take a pessimistic view of the urban residents' perception about the local residents. In order to reduce the sense of unfairness and dissatisfaction and to promote public acceptance of nuclear energy, it is desirable to reduce these misunderstanding and misconception. To this end, this study suggests that it is necessary to make them notice the misconception and grow mutual understanding by exchanging information of the opinions and the situations in each area. (author)

  7. Research and experience report 2013. Developments in the technical and legal areas of nuclear monitoring

    International Nuclear Information System (INIS)

    2014-04-01

    The research into regulatory safety carried out by the Swiss Federal Nuclear Safety Inspectorate (ENSI) serves to clarify outstanding issues, establish fundamentals and develop the tools that ENSI requires for the fulfillment of its responsibilities. The programme is divided into seven areas: 1) research on fuels and materials covers the reactor core and the multiple successive barriers used for the containment of radioactive materials. It is concentrated on high burn-ups and safety criteria. Research into structural materials is focused on ageing mechanisms. The NORA Project at the Paul Scherrer Institute (PSI) looked into the addition of platinum to the coolant as a way of reducing crack formation in primary circuits; 2) the OECD Projects on internal events and damage encourage international exchange of experience on incidents. Specific data bases facilitate a systematic analysis of relevant operating experience from numerous countries. In the field of damage to the influence of pressurised conduits, an overview report on flow-accelerated corrosion was submitted; 3) ENSI supports international projects on external events, including complex experiments and simulations of aircraft crashes and earthquakes. Earthquakes were simulated by shaking-table tests on models of reinforced concrete structures. The structural load-bearing reserves of safety-critical buildings in the event of an earthquake were studied. The Extreme Events Platform is looking at issues related to flood risks; 4) concerning human factors, the research is looking at the reliability of operator behaviour under various conditions. A methodology developed by PSI analyses operator errors with a negative impact on the course of an accident. Research continued into the optimum way to design simulator tests and into the effects of earthquakes on the reliability of operator behaviour; 5) System behaviour and accident sequences in nuclear power plants are analysed in various conditions ranging from normal

  8. Development of renal simulators for use in nuclear medicine; Desenvolvimento de simuladores renais para uso em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Dullius, Marcos Alexandre

    2014-09-01

    Quality control programs in nuclear medicine include verifying the efficiency of all equipment used for diagnosis and therapy, including scintillation cameras. To that end, we have developed and evaluated the performance of four phantom kidneys - two static anthropomorphic, one semi-dynamic, and one dynamic - to acquire static and dynamic renal scintigraphic images. The static anthropomorphic phantoms were used to characterize and evaluate the response of the processing system for different concentrations of radionuclides through static renal scintigraphy images ({sup 99m}Tc-DMSA), obtained with posterior, right posterior oblique, left posterior oblique, and anterior incidences. The static phantoms were made in two ways; one was made of acrylic from a mold of a pair of human kidneys preserved in formalin, and the second was built with acrylonitrile butadiene styrene (ABS), in a 3D printer using the Slicer program, based on a computed tomography (CT) of the thorax, using the Slicer program. The semi-dynamic and dynamic phantoms were constructed to characterize and evaluate images of dynamic renal scintigraphy. In the semi-dynamic phantom, the injection of radiotracer was performed manually, whereas in the dynamic phantom, the radiotracer was automatically injected through an injector system. With the semi-dynamic phantom, it was possible to analyze the formation of a renogram with normal renal scintigraphic appearance using an imaging system. The simulations obtained from the dynamic phantom simulator enabled studies of normal renal scintigraphy and four other forms of renograms. The static anthropomorphic phantom kidneys proved to be efficient for use in evaluations of varying concentrations of radionuclides. The dynamic phantom kidney was useful for analysis of scintigraphic images and obtaining different pathways for elimination of the radioisotope, allowing for analysis of different renograms. Therefore, the new kidney phantoms would be useful for quality

  9. Aerial radiological survey of the Virgil C. Summer Nuclear Station and surrounding area, Jenkinsville, South Carolina

    International Nuclear Information System (INIS)

    1981-07-01

    An aerial radiologic survey was performed from 9 to 16 March 1981 over a 280 square kilometer area centered on the Virgil C. Summer Nuclear Power Station near Jenkinsville, South Carolina. All gamma-photon data were collected by flying North-South lines spaced 230 meters apart at an altitude of 122 meters above ground level. Processed data showed that all gamma-photons detected within the survey area were those expected from naturally occurring terrestrial background emitters. Count rates obtained from the aerial platform were converted to exposure rates at 1 meter above the ground and are presented in the form of an isoradiation contour map. The observed exposure rates over the land areas were between 6 and 30 microroengtens per hour (μR/h) with most of the area ranging from 6 to 15 μR/h. These values include an estimated cosmic ray contribution of 4.0 μR/h. The exposure rate obtained from soil samples taken at the survey site displayed positive agreement with the aerial data

  10. An aerial radiological survey of the Millstone Nuclear Power Station and surrounding area

    International Nuclear Information System (INIS)

    Vojtech, R.J.

    1994-03-01

    An aerial radiological survey was conducted during the period of September 10 to 18, 1990, over a 40-square-mile (104-square-kilometer) area surrounding the Millstone Nuclear Power Station (MNPS). The MNPS is located on the Long Island Sound shoreline, three kilometers south of Waterford, Connecticut. The purpose of the survey was to measure and document the terrestrial gamma ray environment of the plant and surrounding areas. A contour map showing radiation exposure rates at 1 meter above ground level was constructed from the aerial data and overlaid on an aerial photograph and a United States Geological Survey map of the area. The exposure rates within the survey region are quite uniform. The area is characterized by an exposure rate of 10-12 microroentgens per hour including an estimated cosmic ray contribution of 3.6 μR/h. This is typical of natural background. The only exception to the natural background readings is the Millstone station itself, which is characterized by an exposure rate consistent with the standard operation of the reactor units. Radionuclide assays of soil samples and pressurized-ion-chamber gamma ray measurements were obtained at five locations within the survey boundaries. These measurements were taken in support of, and are in agreement with, the aerial data. The radiological environment near the plant is consistent with normal plant operation

  11. An aerial radiological survey of the Babcock and Wilcox Nuclear Facilities and surrounding area, Lynchburg, Virginia

    International Nuclear Information System (INIS)

    Guss, P.P.

    1993-04-01

    An aerial radiological survey was conducted from July 18 through July 25, 1988, over a 41-square-kilometer (16-square-mile) area surrounding the Babcock and Wilcox nuclear facilities located near Lynchburg, Virginia. The survey was conducted at a nominal altitude of 61 meters (200 feet) with line spacings of 91 meters (300 feet). A contour map of the terrestrial gamma exposure rate extrapolated to 1 meter above ground level (AGL) was prepared and overlaid on an aerial photograph. The terrestrial exposure rates varied from 8 to 12 microroentgens per hour (μR/h). A search of the data for man-made radiation sources revealed the presence of three areas of high count rates in the survey area. Spectra accumulated over the main plant showed the presence of cobalt-60 ( 60 Co) and cesium-137 ( 137 Cs). A second area near the main plant indicated the presence of uranium-235 ( 235 U). Protactinium-234m ( 234m Pa) and 60 Co Were detected over a building to the east of the main plant. Soil samples and pressurized ion chamber measurements were obtained at four locations within the survey boundaries in support of the aerial data

  12. An aerial radiological survey of the Millstone Nuclear Power Station and surrounding area

    Energy Technology Data Exchange (ETDEWEB)

    Vojtech, R.J.

    1994-03-01

    An aerial radiological survey was conducted during the period of September 10 to 18, 1990, over a 40-square-mile (104-square-kilometer) area surrounding the Millstone Nuclear Power Station (MNPS). The MNPS is located on the Long Island Sound shoreline, three kilometers south of Waterford, Connecticut. The purpose of the survey was to measure and document the terrestrial gamma ray environment of the plant and surrounding areas. A contour map showing radiation exposure rates at 1 meter above ground level was constructed from the aerial data and overlaid on an aerial photograph and a United States Geological Survey map of the area. The exposure rates within the survey region are quite uniform. The area is characterized by an exposure rate of 10-12 microroentgens per hour including an estimated cosmic ray contribution of 3.6 {mu}R/h. This is typical of natural background. The only exception to the natural background readings is the Millstone station itself, which is characterized by an exposure rate consistent with the standard operation of the reactor units. Radionuclide assays of soil samples and pressurized-ion-chamber gamma ray measurements were obtained at five locations within the survey boundaries. These measurements were taken in support of, and are in agreement with, the aerial data. The radiological environment near the plant is consistent with normal plant operation.

  13. Aerial radiological survey of the Shoreham Nuclear Power Station and surrounding area Brookhaven, New York

    International Nuclear Information System (INIS)

    1984-03-01

    An aerial radiological survey was performed over the area surrounding the Shoreham Nuclear Power Station during 5 to 9 June 1983. The survey, which covered an area of 338 square kilometers (131 square miles), also encompassed the entire Brookhaven National Laboratory (BNL) facility. The highest radiation exposure rate, over 1 milliroentgen per hour (mR/h), was inferred from data measured directly over the BNL facility. This detected activity was due to the presence of cobalt-58, cobalt-60 and cesium-137, which was consistent with normal BNL operations. With the exception of the BNL facility, the only detected man-made radioactivity was found near a cottage in Moriches, New York and was due to the presence of cobalt-60. For the remainder of the survey area, the inferred radiation exposure rates varied generally from 6 to 12 microroentgens per hour (μR/h). The reported exposure rate values include an estimated cosmic ray contribution of 3.7 μR/h. Ground-based measurements, conducted concurrently with the aerial survey, were compared to the inferred aerial results. Pressurized ionization chamber readings and a group of soil samples were acquired from five locations within the survey area. The exposure rate values obtained from these measurements were consistent with those inferred from the aerial results. 11 references, 12 figures, 3 tables

  14. An autonomous nuclear power plant with integrated nuclear steam supply system designed for electric power and heat supply in remote areas with difficult access

    International Nuclear Information System (INIS)

    Adamovich, L.A.; Grechko, G.I.; Lapin, B.D.; Ulasevich, V.K.; Shishkin, V.A.

    1997-01-01

    The paper contains basic conceptual principles used to develop the technical assignment for an autonomous nuclear power plant with integrated nuclear steam supply system (NSSS) designed to provide heat and electricity for areas which are remote with difficult access. The paper also describes technical procedures and equipment, NPP thermal hydraulic flow chart, steam generator design, safety aspects as well as operational and maintenance procedures. (author)

  15. The investigation on hereditary disease and congenital malformation in the surrounding area of the nuclear test site in Xinjiang

    International Nuclear Information System (INIS)

    Zou Wenliang; Zhang Jujing

    1989-01-01

    The investigation on hereditary disease and congenital malformation, on the children below eleven years old and living in the surrounding area of the nuclear test site and control area is reported. The total prevalence rate of the ninteen kinds of hereditary disease and congenital malformation in both areas are 7.12%0 and 7.28%0, respectively. The prevalence rate of congenital foolishness in investigation area is 0.64%0; while in control area, it is 0.54%0. There is no significant difference between the two areas. However, it is found that the prevalence rate of harelip in investigation area is higher than in control area, whereas the prevalence rate of congenital heart disease in control area is higher than in investigation area. As for the rests there is no significant difference. There is no significant difference between the two areas. It is concluded that nuclear tests in China did not cause hereditary disease and congenital malformation for the children who live in surrounding area, of the nuclear test site

  16. Deep repository for spent nuclear fuel. Facility description - Layout E. Spiral ramp with one operational area

    Energy Technology Data Exchange (ETDEWEB)

    Pettersson, Stig [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Forsgren, Ebbe [SwedPower AB, Stockholm (Sweden); Lange, Fritz [Lange Art AB, Stockholm (Sweden)

    2002-04-01

    This report documents a proposal for the design of the deep repository for spent nuclear fuel. The proposal is based on the principles that were formulated in the original KBS-3 study, but has been supplemented by investigations and experience to reflect current knowledge. The purpose of the report is to provide an integrated picture of the deep repository, as a basis for SKB's other work, e.g. environmental impact assessments, transport systems, safety issues and alternative locations, and to provide a co-ordinated account of the conditions and requirements concerning all of the necessary functions in the deep repository in order to have a well functioning facility. In addition, it should be possible to use the report as: a tool in the task of achieving a co-ordinated, safe and accepted design for the facility, a basis for further planning and costing, a basis for adaptation to geographic and other conditions for the particular location, a basis for information material, both within SKB and for interested parties outside, such as public authorities, municipalities and the general public. The capacity of the deep repository has been chosen on the basis of 40 years of operation of the Swedish nuclear power reactors, which will produce approximately 9,000 tons of uranium, equivalent to approximately 4,500 canisters. The design outlined is based on theoretical analyses of functions, safety requirements, procedures etc. that can be identified during the various phases of the construction and operation of the repository. In addition, preliminary organisation and staffing plans have been drawn up, for use as the basis for planning the necessary buildings. The report gives a vision of the overall layout and function of the facility, and a proposal for the design of all individual parts of the repository. The relationships between the various parts of the repository are described, both above and below ground, as is the interplay between the part above ground and part

  17. Deep repository for spent nuclear fuel. Facility description - Layout E. Spiral ramp with one operational area

    International Nuclear Information System (INIS)

    Pettersson, Stig; Forsgren, Ebbe; Lange, Fritz

    2002-04-01

    This report documents a proposal for the design of the deep repository for spent nuclear fuel. The proposal is based on the principles that were formulated in the original KBS-3 study, but has been supplemented by investigations and experience to reflect current knowledge. The purpose of the report is to provide an integrated picture of the deep repository, as a basis for SKB's other work, e.g. environmental impact assessments, transport systems, safety issues and alternative locations, and to provide a co-ordinated account of the conditions and requirements concerning all of the necessary functions in the deep repository in order to have a well functioning facility. In addition, it should be possible to use the report as: a tool in the task of achieving a co-ordinated, safe and accepted design for the facility, a basis for further planning and costing, a basis for adaptation to geographic and other conditions for the particular location, a basis for information material, both within SKB and for interested parties outside, such as public authorities, municipalities and the general public. The capacity of the deep repository has been chosen on the basis of 40 years of operation of the Swedish nuclear power reactors, which will produce approximately 9,000 tons of uranium, equivalent to approximately 4,500 canisters. The design outlined is based on theoretical analyses of functions, safety requirements, procedures etc. that can be identified during the various phases of the construction and operation of the repository. In addition, preliminary organisation and staffing plans have been drawn up, for use as the basis for planning the necessary buildings. The report gives a vision of the overall layout and function of the facility, and a proposal for the design of all individual parts of the repository. The relationships between the various parts of the repository are described, both above and below ground, as is the interplay between the part above ground and part below

  18. Areas of Potential Impact of the Patient Protection and Affordable Care Act on EMS: A Synthesis of the Literature

    Directory of Open Access Journals (Sweden)

    Daniel G. Ostermayer

    2017-04-01

    Full Text Available Introduction: This comprehensive review synthesizes the existing literature on the Patient Protection and Affordable Care Act (ACA as it relates to emergency medical services (EMS in order to provide guidance for navigating current and future healthcare changes. Methods: We conducted a comprehensive review to identify all existing literature related to the ACA and EMS and all sections within the federal law pertaining to EMS. Results: Many changes enacted by the ACA directly affect emergency care with potential indirect effects on EMS systems. New Medicaid enrollees and changes to existing coverage plans may alter EMS transport volumes. Reimbursement changes such as adjustments to the ambulance inflation factor (AIF alter the yearly increases in EMS reimbursement by incorporating the multifactor productivity value into yearly reimbursement adjustments. New initiatives, funded by the Center for Medicare & Medicaid Innovation are exploring novel and cost-effective prehospital care delivery opportunities while EMS agencies individually explore partnerships with healthcare systems. Conclusion: EMS systems should be aware of the direct and indirect impact of ACA on prehospital care due to the potential for changes in financial reimbursement, acuity and volume changes, and ongoing new care delivery initiatives.[West J Emerg Med. 2017;18(3446-453.

  19. Research and experience report 2014. Developments in the technical and legal areas of nuclear monitoring

    International Nuclear Information System (INIS)

    2015-04-01

    The research into regulatory safety carried out by the Swiss Federal Nuclear Safety Inspectorate (ENSI) serves to develop the tools that ENSI requires for the fulfilment of its responsibilities. The programme is divided into seven areas: 1) research on fuels and materials covers the reactor core and the multiple successive barriers used for the containment of radioactive materials. It is concentrated on high burn-ups and safety criteria. Research into structural materials is focused on ageing mechanisms. The SAFE Project has been investigating the formation and growth of cracks in materials used in reactor cooling circuits. The researchers at the Paul Scherrer Institute (PSI) obtained results on how the hydrogen present in hot water as well as the sequence of mechanical stresses affect crack development; 2) the OECD Projects on internal events and damage encourage international exchange of experience on incidents. Specific data bases facilitate the analysis of relevant operating experience from many countries. The ICDE Project, which is looking at common-cause failures in the components used in nuclear power plants, published an overview report on heat exchangers; 3) ENSI supports research projects on external events such as aircraft crashes, flooding and earthquakes. The Swiss Seismological Service (SED) published a report on ground motion attenuation as a function of increasing distance to the earthquake's source. By incorporating data from countries with high seismic activity, the SED has improved the attenuation model for Switzerland. The international SMART project has been looking at the impact of severe earthquakes on nuclear power plant buildings in order to represent the dynamic behaviour and vulnerability of reinforced concrete structures; 4) as far as human factors are concerned, the Halden Reactor Project completed informative simulation studies. A comparative study of 10 operator groups revealed marked variability in the way unforeseen situations

  20. A survey of low-level radioactive waste treatment methods and problem areas associated with commercial nuclear power plants

    International Nuclear Information System (INIS)

    Jolley, R.L.; Rodgers, B.R.

    1987-01-01

    A survey was made (June 1985) of technologies that were currently being used, those that had been discontinued, and those that were under consideration for treatment of low-level radioactive waste from the commercial nuclear power plants in the United States. The survey results included information concerning problems areas, areas needing research and development, and the use of mobile treatment facilities

  1. Inspection of the brazilian nuclear regulatory body in the area of radiotherapy. A critical analysis

    International Nuclear Information System (INIS)

    Brito, Ricardo Roberto de Azevedo

    2005-01-01

    The National Commission of Nuclear Energy (CNEN) is responsible in Brazil for the activities of licensing and control of radioactive installations in the radiotherapy medical area. The majority of these activities are developed by CNEN Co-ordination of Radioactive Installations (CORAD). One of the necessary stages for the development of licensing and control activities is the inspection of radiotherapy services (clinics and hospitals). Almost all of these inspections are carried out by CNEN Inst. of Radiation Protection and Dosimetry (IRD), through its Service of Medical Physics in Radiotherapy and Nuclear Medicine (SEFME). This work makes a survey of the main nonconformities found during ten years of inspections in radiotherapy services (1995 - 2004) and analyses the efficiency of these inspections in making the radiotherapy services develop their activities according to the norms in vigour in the country and adopt corrective actions against, at least, the nonconformities evidenced by CNEN inspectors. Additionally, it analyses the possibility of improvement and / or the optimisation of the process, through a procedure able to be unified and controlled, aiming a prompt communication to those involved in the licensing process (SEFME and CORAD) about the attendance by the radiotherapy services to the non-conformity items observed during the inspection. (author)

  2. A study on the public perception in nuclear area in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Renata Araujo de [Coordenacao dos Programas de Pos-Graduacao de Engenharia (PEN/COPPE/UFRJ), RJ (Brazil). Programa de Engenharia Nuclear; Moreira, Maria de Lourdes; Guimaraes, Antonio Cesar Ferreira, E-mail: malu@ien.gov.b, E-mail: tony@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Wieland, Patricia, E-mail: pwieland@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioprotecao e Seguranca Nuclear. Div. de Normas

    2011-07-01

    During the course of the last years the need for the increase in the electric energy production in Brazil as well as in the rest of the world, has raised the tone of the debate about the environment impact of such production. As a result of these debates, both the several levels of government and some of the Non-Governmental Organizations (NGO's) have commissioned innumerous opinion researches aiming at measuring and evaluating the knowledge and perception of the public in relation of the best non-polluting energy sources. Prior to 2001 these researches would not make any sense in Brazil., however due to that year's drought, the competent authorities were faced with the necessity of developing a plan, the Plano Nacional de Energia (PNE2030) aiming, among others objectives, at finalizing the construction of the Angra 3 plant and implementing new nuclear plants in places still to be determined. Allowing for the complexity of the subject, this paper presents a field research conducted from 28th September 2010 to 28th October 2010 assessing the current level of perception of the Brazilian population about the nuclear area, in particular of the residents of three cities of Rio de Janeiro. As a result of this work, we suggest how the competent authorities should proceed to reach in an efficient manner a greater understanding of the population about the proposed subject, through communication campaigns being both informative and educational. (author)

  3. A study on the public perception in nuclear area in Brazil

    International Nuclear Information System (INIS)

    Almeida, Renata Araujo de; Wieland, Patricia

    2011-01-01

    During the course of the last years the need for the increase in the electric energy production in Brazil as well as in the rest of the world, has raised the tone of the debate about the environment impact of such production. As a result of these debates, both the several levels of government and some of the Non-Governmental Organizations (NGO's) have commissioned innumerous opinion researches aiming at measuring and evaluating the knowledge and perception of the public in relation of the best non-polluting energy sources. Prior to 2001 these researches would not make any sense in Brazil., however due to that year's drought, the competent authorities were faced with the necessity of developing a plan, the Plano Nacional de Energia (PNE2030) aiming, among others objectives, at finalizing the construction of the Angra 3 plant and implementing new nuclear plants in places still to be determined. Allowing for the complexity of the subject, this paper presents a field research conducted from 28th September 2010 to 28th October 2010 assessing the current level of perception of the Brazilian population about the nuclear area, in particular of the residents of three cities of Rio de Janeiro. As a result of this work, we suggest how the competent authorities should proceed to reach in an efficient manner a greater understanding of the population about the proposed subject, through communication campaigns being both informative and educational. (author)

  4. Characterizing the influence of transportation infrastructure on Emergency Medical Services (EMS) in urban area-A case study of Seoul, South Korea.

    Science.gov (United States)

    Cho, Jungwoo; You, Myoungsoon; Yoon, Yoonjin

    2017-01-01

    In highly urbanized area where traffic condition fluctuates constantly, transportation infrastructure is one of the major contributing factors to Emergency Medical Service (EMS) availability and patient outcome. In this paper, we assess the impact of traffic fluctuation to the EMS first response availability in urban area, by evaluating the k-minute coverage under 21 traffic scenarios. The set of traffic scenarios represents the time-of-day and day-of-week effects, and is generated by combining road link speed information from multiple historical speed databases. In addition to the k-minute area coverage calculation, the k-minute population coverage is also evaluated for every 100m by 100m grid that partitions the case study area of Seoul, South Korea. In the baseline case of traveling at the speed limit, both the area and population coverage reached nearly 100% when compared to the five-minute travel time national target. Employing the proposed LoST (Loss of Serviceability due to Traffic) index, which measures coverage reduction in percentage compared to the baseline case, we find that the citywide average LoST for area and population coverage are similar at 34.2% and 33.8%. However, district-wise analysis reveals that such reduction varies significantly by district, and the magnitude of area and population coverage reduction is not always proportional. We conclude that the effect of traffic variation is significant to successful urban EMS first response performance, and regional variation is evident among local districts. Complexity in the urban environment requires a more adaptive approach in public health resource management and EMS performance target determination.

  5. Characterizing the influence of transportation infrastructure on Emergency Medical Services (EMS in urban area-A case study of Seoul, South Korea.

    Directory of Open Access Journals (Sweden)

    Jungwoo Cho

    Full Text Available In highly urbanized area where traffic condition fluctuates constantly, transportation infrastructure is one of the major contributing factors to Emergency Medical Service (EMS availability and patient outcome. In this paper, we assess the impact of traffic fluctuation to the EMS first response availability in urban area, by evaluating the k-minute coverage under 21 traffic scenarios. The set of traffic scenarios represents the time-of-day and day-of-week effects, and is generated by combining road link speed information from multiple historical speed databases. In addition to the k-minute area coverage calculation, the k-minute population coverage is also evaluated for every 100m by 100m grid that partitions the case study area of Seoul, South Korea. In the baseline case of traveling at the speed limit, both the area and population coverage reached nearly 100% when compared to the five-minute travel time national target. Employing the proposed LoST (Loss of Serviceability due to Traffic index, which measures coverage reduction in percentage compared to the baseline case, we find that the citywide average LoST for area and population coverage are similar at 34.2% and 33.8%. However, district-wise analysis reveals that such reduction varies significantly by district, and the magnitude of area and population coverage reduction is not always proportional. We conclude that the effect of traffic variation is significant to successful urban EMS first response performance, and regional variation is evident among local districts. Complexity in the urban environment requires a more adaptive approach in public health resource management and EMS performance target determination.

  6. Planning for cleanup of large areas contaminated as a result of a nuclear accident

    International Nuclear Information System (INIS)

    1991-01-01

    The cleanup of large areas of contaminated as a result of an accident at a nuclear facility could cost hundreds of millions of dollars and cause inconvenience to the public. Such a cleanup programme would be undertaken only if the detriment to health and social life resulting from cleanup activities would be less than that resulting from further exposures. All reasonable means should, however, be used to minimize the costs and detriment to humans of such a cleanup. For such a cleanup to be carried out safely, efficiently and as quickly as possible under adverse conditions requires: Good preliminary and final planning; A cleanup team having a well defined management structure and well trained personnel; and Suitable cleanup methods and equipment and cleanup criteria. 35 refs, 8 figs, 5 tabs

  7. The choice of nuclear material measurement strategy in bulk-form in material balance area

    International Nuclear Information System (INIS)

    Smirnov, V.M.; Sergeev, S.A.; Kirsanov, V.S.

    1999-01-01

    Concepts have been defined such as Shipment batch, Technological batch, and Accounting batch, it has been found that Shipment and Technological batches should be formed through the arrangement of group of measured Accounting batches. The strategy for nuclear material (NM) measurement based on the Accounting batch is shown to give a possibility to use the advantages for the accounting purposes: ensure safeguards of non-diversion of NM at quantitative (numerical) level, which is a higher grade of safeguards compared to the systems of accounting and control now in force of the US and EURATOM; ensure a guaranteed accuracy and reliability (confidence level) when making up NM balance in Material Balance Area (MBA) and at Federal level, which has been realized only in part in the NM control and accounting systems. Strategy of NM measurement for MBAs counting NM in bulk form has been proposed [ru

  8. Development of parallel GPU based algorithms for problems in nuclear area

    International Nuclear Information System (INIS)

    Almeida, Adino Americo Heimlich

    2009-01-01

    Graphics Processing Units (GPU) are high performance co-processors intended, originally, to improve the use and quality of computer graphics applications. Since researchers and practitioners realized the potential of using GPU for general purpose, their application has been extended to other fields out of computer graphics scope. The main objective of this work is to evaluate the impact of using GPU in two typical problems of Nuclear area. The neutron transport simulation using Monte Carlo method and solve heat equation in a bi-dimensional domain by finite differences method. To achieve this, we develop parallel algorithms for GPU and CPU in the two problems described above. The comparison showed that the GPU-based approach is faster than the CPU in a computer with two quad core processors, without precision loss. (author)

  9. Remote system for monitoring and control of controlled area of nuclear installation

    International Nuclear Information System (INIS)

    Assuncao, Daniel Gomes de; Minhoni, Danilo Carlos Rossetto; Farias, Marcos Sant'anna de; Santos, Isaac J.A. Luquetti dos

    2011-01-01

    The maintenance activities in controlled areas of nuclear facilities require adequate planning and control so that these activities do not cause to the worker an undue exposure to radioactivity. For maximum safety of workers from these places, there are standards that determine the maximum radiation dose that a worker can receive. From this context, the objective of this research is to develop a remote system that shows remotely the maintenance tasks being carried out in this work environment; monitors information provided by radiation monitoring devices installed at workplace; tracks the time to carry out scheduled maintenance, reporting alarm if this time is exceeded or not. The system has video camera, radiation monitoring device, interface card to transmit data via ethernet and graphical user interface, developed using the LABVIEW application. The principal objective is to improve the safety and to preserve the worker's health. (author)

  10. Remote system for monitoring and control of controlled area of nuclear installation

    Energy Technology Data Exchange (ETDEWEB)

    Assuncao, Daniel Gomes de; Minhoni, Danilo Carlos Rossetto [Departamento de Ciencias da Administracao e Tecnologia. Centro Universitario de Araraquara (UNIARA) Araraquara, SP (Brazil); Farias, Marcos Sant' anna de; Santos, Isaac J.A. Luquetti dos, E-mail: luquetti@ien.gov.br [Instituto Engenharia Nuclear (IEN/CNEN-RJ), Rio Janeiro, RJ (Brazil). Divisao de Instrumentacao e Confiabilidade Humana

    2011-07-01

    The maintenance activities in controlled areas of nuclear facilities require adequate planning and control so that these activities do not cause to the worker an undue exposure to radioactivity. For maximum safety of workers from these places, there are standards that determine the maximum radiation dose that a worker can receive. From this context, the objective of this research is to develop a remote system that shows remotely the maintenance tasks being carried out in this work environment; monitors information provided by radiation monitoring devices installed at workplace; tracks the time to carry out scheduled maintenance, reporting alarm if this time is exceeded or not. The system has video camera, radiation monitoring device, interface card to transmit data via ethernet and graphical user interface, developed using the LABVIEW application. The principal objective is to improve the safety and to preserve the worker's health. (author)

  11. On necessity of revaluation of nuclear power safety of Ukraine in the tornado hazardous areas

    International Nuclear Information System (INIS)

    Skalozubov, V.I.; Gablaya, T.V.; Vasilchenko, S.V.; Kozlov, I.V.

    2015-01-01

    The article contains the main provisions regulating the tornado danger of objects of atomic energy, as well as analysis of the known results of evaluations of the impact of hurricanes on the safety of nuclear power plants of Ukraine, received in the ''before'' and ''post Fukushima'' periods. As a result of analysis is insufficient justification to the estimated frequency of passing tornadoes and exclusion from consideration emergency events with flooding of indus-trial sites under the influence of tornadoes not less than 2-th class intensity, defined a reassessment of NPP safety of Ukraine taking into account reasonably established performance tornado dangerous areas and lessons Fukushima accident

  12. Nuclear fuel waste management program geotechnical studies of Eye-Dashwa Lakes research area rock properties

    International Nuclear Information System (INIS)

    Chernis, P.J.; Robertson, P.B.

    1992-05-01

    The Eye-Dashwa Lakes pluton near Atikokan Ontario has been used as a study area for the Canadian nuclear fuel waste management research program. The pluton consists predominately of granite. Fractures formed during cooling of the pluton were filled with a succession of different materials at different times. Measurements of a series of geophysical and geotechnical properties of rock samples are published here in this report, including especially microcrack and pore structures. An indication has been found that a larger proportion of the porosity of Whiteshell and Atikokan samples is contained in connecting pores, compared to other rocks. This may seem surprising in view of the finding that approximately 70% of the effective porosity of Atikokan samples is contained in pockets

  13. Offsite environmental monitoring report; radiation monitoring around United States nuclear test areas, Calendar Year 1996

    International Nuclear Information System (INIS)

    Davis, M.G.; Flotard, R.D.; Fontana, C.A.; Huff, P.A.; Maunu, H.K.; Mouck, T.L.; Mullen, A.A.; Sells, M.D.

    1997-08-01

    This report describes the Offsite Radiation Safety Program. This laboratory operated an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs); and using pressurized ionization chambers (PICs). No nuclear weapons testing was conducted in 1996 due to the continuing nuclear test moratorium. During this period, R and IE personnel maintained readiness capability to provide direct monitoring support if testing were to be resumed and ascertained compliance with applicable EPA, DOE, state, and federal regulations and guidelines. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no airborne radioactivity from diffusion or resuspension detected by the various EPA monitoring networks surrounding the NTS. There was no indication of potential migration of radioactivity to the offsite area through groundwater and no radiation exposure above natural background was received by the offsite population. All evaluated data were consistent with previous data history

  14. Danube quality water assessment from the microbiological point of view in Cernavoda nuclear plant area

    International Nuclear Information System (INIS)

    Sundri, Mirela Iuliana

    2003-01-01

    Herein are analysed the following microbiological parameters: total viable count, total coliforms and faecal coliforms, which represent a standard indicator for water quality. The study has been done during 1998-2002 upon the water in the Danube River and in the channels for cooling water used by Cernavoda Nuclear Power Plant condensers. In this area, based on these values of evaluated parameters, the water feature is placed in the quality classes II and III (moderate and critical pollution), in conformity with European Community Directives. Bacterial communities, component part of aquatic biocenoses, are very important for matter and energy flux. Their contribution to self-purification processes of rivers is of great interest related to the water quality assessment. Microorganisms are ideal sensors, because they respond fast to the fluctuation of environmental conditions by specific changes, detectable physiologically and metabolically. The temperature is a major factor, which directly affects the intensity of all microbial processes. Because the microorganisms are interconnected with the other living organisms, the qualitative or quantitative changes of their activity will affect the functions of the whole ecosystem. Bacterial indicators such as total viable count (colony count), total coliforms or faecal coliforms (thermo-tolerant coliforms) are widely applied to the assessment of water quality. Because of their mostly allochthonus origin, these are used as indicators of changes in the natural water conditions; they point out an organic matter or faecal water pollution. Although the water quality can be considered acceptable from the chemical or biological point of view, the bacteriological parameters might be detected in critical concentration. The objectives of this microbiological assessment are analysis of the variation of bacteriological indicators in some sampling points of Cernavoda aquatic ecosystems area, and monitoring the manner of using the water by

  15. Recharge-area nuclear waste repository in southeastern Sweden. Demonstration of hydrogeologic siting concepts and techniques

    International Nuclear Information System (INIS)

    Provost, A.M.; Voss, C.I.

    2001-11-01

    Nuclear waste repositories located in regional ground-water recharge ('upstream') areas may provide the safety advantage that potentially released radionuclides would have long travel time and path length, and large path volume, within the bedrock before reaching the biosphere. Nuclear waste repositories located in ground-water discharge ('downstream') areas likely have much shorter travel time and path length and smaller path volume. Because most coastal areas are near the primary discharge areas for regional ground-water flow, coastal repositories may have a lower hydrogeologic safety margin than 'upstream' repositories located inland. Advantageous recharge-area sites may be located through careful use of regional three-dimensional, variable-density, ground-water modeling. Because of normal limitations of site-characterization programs in heterogeneous bedrock environments, the hydrogeologic structure and properties of the bedrock will generally remain unknown at the spatial scales required for the model analysis, and a number of alternative bedrock descriptions are equally likely. Model simulations need to be carried out for the full range of possible descriptions. The favorable sites are those that perform well for all of the modeled bedrock descriptions. Structural heterogeneities in the bedrock and local undulations in water-table topography, at a scale finer than considered by a given model, also may cause some locations in favored inland areas to have very short flow paths (of only hundreds of meters) and short travel times, compromising the long times and paths (of many kilometers) predicted by the analysis for these sites. However, in the absence of more detailed modeling, the favored upstream sites offer a greater chance of achieving long times and paths than do downstream discharge areas, where times and paths are expected to be short regardless of the level of detail included in the model. As an example of this siting approach, potential repository

  16. Plutonium focus area: Technology summary

    International Nuclear Information System (INIS)

    1996-03-01

    To ensure research and development programs focus on the most pressing environmental restoration and waste management problems at the U.S. Department of Energy (DOE), the Assistant Secretary for the Office of Environmental Management (EM) established a working group in August 1993 to implement a new approach to research and technology development. As part of this approach, EM developed a management structure and principles that led to creation of specific focus areas. These organizations were designed to focus scientific and technical talent throughout DOE and the national scientific community on major environmental restoration and waste management problems facing DOE. The focus area approach provides the framework for inter-site cooperation and leveraging of resources on common problems. After the original establishment of five major focus areas within the Office of Technology Development (EM-50), the Nuclear Materials Stabilization Task Group (NMSTG, EM-66) followed EM-50's structure and chartered the Plutonium Focus Area (PFA). NMSTG's charter to the PFA, described in detail later in this book, plays a major role in meeting the EM-66 commitments to the Defense Nuclear Facilities Safety Board (DNFSB). The PFA is a new program for FY96 and as such, the primary focus of revision 0 of this Technology Summary is an introduction to the Focus Area; its history, development, and management structure, including summaries of selected technologies being developed. Revision 1 to the Plutonium Focus Area Technology Summary is slated to include details on all technologies being developed, and is currently planned for release in August 1996. The following report outlines the scope and mission of the Office of Environmental Management, EM-60, and EM-66 organizations as related to the PFA organizational structure

  17. Wide area change detection with satellite imagery for locating underground nuclear testing

    International Nuclear Information System (INIS)

    Canty, M.J.; Jasani, B.; Schlittenhardt, J.

    2001-01-01

    nicest aspects of the MAD method: It sorts different categories of change into different image components. Another very important characteristic of the MAD transformation is that it is invariant to linear transformations of the data. This means that if for example the sensors used for the two images have different gains, or if atmospheric haze attenuates the reflectance measurement in one of the images but not in the other, the results of the analysis will be unaffected. A Bayesian model of the probability distribution of the MAD components intensities is applied to determine automatically the decision thresholds for change and no change. The prerequisite image-to-image registration is carried out automatically with the help contour and comer matching to determine ground control points, followed by nearest-neighbor resampling. The inclusion of higher resolution panchromatic information into the procedure without loss of spectral discrimination is accomplished via wavelet fusion with the multispectral channels. A computer program CDSAT (Change Detection with SATellite imagery), which implements a user-friendly graphical environment for performing the various steps involved, is described briefly. The technique has been applied successfully to detect the exact position of an underground nuclear test in Rajasthan in 1998. In the present paper we discuss further results for tests carried out in Lop Nor, China in the 1990's and at the Nevada test site in the 1980's. Historical LANDSAT TM satellite images are used for change detection. Results are correlated with seismic and ground truth data and conclusions are drawn regarding the applicability of wide area change detection to complement seismic verification of the Comprehensive Test Ban Treaty

  18. The PRONUCLEAR role (1976-1986) in the human resource training for the nuclear area in Brazil: science history; O papel do PRONUCLEAR (1976 -1986) na formacao de recursos humanos para a area nuclear no Brasil: historia da ciencia

    Energy Technology Data Exchange (ETDEWEB)

    Schmiedecke, Winston Gomes

    2006-07-01

    In 1975, an agreement between the governments of Brazil and West-Germany was signed for the construction of nuclear power plants in Brazil as well as the extraction, processing and enrichment of uranium. As the result of the first oil crisis and facing the perspective of a continuous world energy crisis, the Brazilian government decided to turn to nuclear power as an alternative supply for the country's energy needs. However, serious limitations were present regarding the transfer of nuclear technology for a third world country. This paper analyzes some aspects of the process involved in the creation of the specialized human resources during the extent of the agreement between Brazil and West Germany. Since its inception, the agreement received harsh criticism from the Brazilian nuclear physics and related fields scientific communities. Because the planning and implementation of the agreement took place during a period of military dictatorship, the decisions relating to the agreement were never debated between the policy makers and the scientific community. Not surprisingly, the agreement received plenty of criticism that ranged from the actual need for nuclear power to technical feasibility and suspicious of possible military uses and even the very policies created to prepare human resources to work in the nuclear area. One of the most important tools of these policies was the Programa de Recursos Humanos para o Setor Nuclear - PRONUCLEAR (Nuclear Sector Human Resources Program), implemented in 1976 and gradually deactivated starting in 1983. (author)

  19. The PRONUCLEAR role (1976-1986) in the human resource training for the nuclear area in Brazil: science history; O papel do PRONUCLEAR (1976 -1986) na formacao de recursos humanos para a area nuclear no Brasil: historia da ciencia

    Energy Technology Data Exchange (ETDEWEB)

    Schmiedecke, Winston Gomes

    2006-07-01

    In 1975, an agreement between the governments of Brazil and West-Germany was signed for the construction of nuclear power plants in Brazil as well as the extraction, processing and enrichment of uranium. As the result of the first oil crisis and facing the perspective of a continuous world energy crisis, the Brazilian government decided to turn to nuclear power as an alternative supply for the country's energy needs. However, serious limitations were present regarding the transfer of nuclear technology for a third world country. This paper analyzes some aspects of the process involved in the creation of the specialized human resources during the extent of the agreement between Brazil and West Germany. Since its inception, the agreement received harsh criticism from the Brazilian nuclear physics and related fields scientific communities. Because the planning and implementation of the agreement took place during a period of military dictatorship, the decisions relating to the agreement were never debated between the policy makers and the scientific community. Not surprisingly, the agreement received plenty of criticism that ranged from the actual need for nuclear power to technical feasibility and suspicious of possible military uses and even the very policies created to prepare human resources to work in the nuclear area. One of the most important tools of these policies was the Programa de Recursos Humanos para o Setor Nuclear - PRONUCLEAR (Nuclear Sector Human Resources Program), implemented in 1976 and gradually deactivated starting in 1983. (author)

  20. Improvements of the Regulatory Framework for Nuclear Installations in the Areas of Human and Organizational Factors and Safety Culture

    International Nuclear Information System (INIS)

    Tronea, M.; Ciurea, C.

    2016-01-01

    The paper presents the development of regulatory requirements in the area of human and organizational factors taking account of the lessons learned from major accidents in the nuclear industry and in particular of the factors that contributed to the Fukushima Daiichi accident and the improvement of the regulatory oversight of nuclear safety culture. New requirements have been elaborated by the National Commission for Nuclear Activities Control (CNCAN) on the nuclear safety policy of licencees for nuclear installations, on independent nuclear safety oversight, on safety conscious work environment and on the assessment of nuclear safety culture. The regulatory process for the oversight of nuclear safety culture within licencees’ organizations operating nuclear installations and the associated procedure and guidelines, based on the IAEA Safety Standards, have been developed in 2010-2011. CNCAN has used the 37 IAEA attributes for a strong safety culture, grouped into five areas corresponding to safety culture characteristics, as the basis for its regulatory guidelines providing support to the reviewers and inspectors, in their routine activities, for recognising and gathering information relevant to safety culture. The safety culture oversight process, procedure and guidelines are in process of being reviewed and revised to improve their effectiveness and to align with the current international practices, using lessons learned from the Fukushima Daiichi accident. Starting with July 2014, Romania has a National Strategy for Nuclear Safety and Security, which includes strategic objectives, associated directions for action and concrete actions for promoting nuclear safety culture in all the organizations in the nuclear sector. The progress with the implementation of this strategy with regard to nuclear safety culture is described in the paper. CNCAN started to define its own organizational culture model and identifying the elements that promote and support safety

  1. Solving some socio-economic relations in the area of the projected site of the Blahutovice nuclear power plant

    International Nuclear Information System (INIS)

    Uvirova, E.; Grosikova, B.

    1988-01-01

    Blahutovice nuclear power plant personnel will be accommodated in hostels and newly built appartments in Novy Jicin and in Hranice. Commuting of personnel to the plant from the two towns is discussed. A works health centre will be built in the nuclear power plant area delivering primary health care. A radiation medicine unit is also envisaged. The Beskydy Mts. in Northern Moravia are considered for recreation-rehabilitation facilities. (E.S.). 2 tabs., 5 refs

  2. Agreement between Portugal and Spain on cooperation with regard to the safety of nuclear installations in border areas

    International Nuclear Information System (INIS)

    1980-01-01

    This Agreement provides for exchange of information on nuclear safety and radiation protection in nuclear installations likely to affect mutually the territories of Portugal and Spain. The Agreement defines the type of nuclear installation concerned, the border areas and the respective competent authorities. The competent authorities of both Parties undertake to establish in their respective territories, the systems required to detect any radiation emergency and to inform each other in cases where such emergency may affect them. The Agreement was concluded for a period of the years as from its entry into force. (NEA) [fr

  3. Off-site environmental monitoring report: Radiation monitoring around United States Nuclear Test areas, Calendar year 1986

    International Nuclear Information System (INIS)

    Patzer, R.G.; Fontana, C.A.; Grossman, R.F.; Black, S.C.; Dye, R.E.; Smith, D.D.; Thome', D.J.; Mullen, A.A.

    1987-05-01

    The principal activity at the NTS is testing of nuclear devices, though other related projects are also conducted. The principal activities of the Off-Site Radiological Safety Program are routine environmental monitoring for radioactive materials in various media and for radiation in areas which may be affected by nuclear tests; and protective actions in support of the nuclear testing program. These are conducted to document compliance with standards, to identify trends, and to provide information to the public. 28 refs., 37 figs., 30 tabs

  4. An integrated nuclear reactor unit for a floating low capacity nuclear power plant designed for power supply in remote areas with difficult access

    International Nuclear Information System (INIS)

    Achkasov, A.N.; Grechko, G.I.; Gladkov, O.G.; Pavlov, V.L.; Pepa, V.N.; Shishkin, V.A.

    1997-01-01

    The paper describes the conceptual design of an integrated advanced safety nuclear reactor unit for a low capacity floating, NPP designed for power supply in areas which are remote with difficult access. The paper describes the major structural and lay-out components of the steam generator and reactor units with main technical characteristics. (author)

  5. French practice in the area of seismic hazard assessment on nuclear facility sites and related research

    International Nuclear Information System (INIS)

    Mohammadioun, B.

    1986-06-01

    The methodology put into practice in the analysis of seismic hazard on the site of a nuclear facility relies upon a deterministic approach and endeavors to account for the particularities of every site considered insofar as available data and techniques allow. The calculation of a seismic reference motion for use in the facilities' design calls upon two basic sets of data. Regional seismicity over the past millennium, from historical sources, revised while preparing the seismotectonic map of France, is fundamental to this analysis. It is completed by instrumental data from the last quarter century. A collection of strong-motion accelerograph data from seismic areas worldwide reflects a variety of source characteristics and site conditions. A critical overview of current practice in France and elsewhere highlights shortcomings and areas of particular need both in experimental data and in methodology, and namely the scarcity of near-field data, the predominance of California records, and inaccurate approaches to integrating soil effects into ground-motion calculations. 16 refs

  6. An aerial radiological survey of the Vermont Yankee Nuclear Power Station and surrounding area, Vernon, Vermont

    International Nuclear Information System (INIS)

    Reiman, R.; Bluitt, C.M.

    1993-10-01

    An aerial radiological survey was conducted over the Vermont Yankee Nuclear Power Station in Vernon, Vermont, during the period August 7 through August 17, 1989. The survey was conducted at an altitude of 300 feet (91 meters) over a 65-square-mile (168-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Vermont Yankee Power Station and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 10 microroentgens per hour (μR/h) and were attributed to naturally occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based open-quotes benchmarkclose quotes exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system

  7. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas

    International Nuclear Information System (INIS)

    1990-01-01

    This report describes the Offsite Radiation Safety Program conducted during 1990 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory -- Las Vegas. This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of animals, food crops, and humans. Personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each nuclear weapons test to implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any occurrence of radioactivity release

  8. Radiocesium contamination in house dust within evacuation areas close to the Fukushima Daiichi nuclear power plant.

    Science.gov (United States)

    Shinohara, Naohide; Yoshida-Ohuchi, Hiroko

    2018-05-01

    Outdoor decontamination efforts have been ongoing since the Fukushima Daiichi nuclear power plant (FDNPP) accident; however, little is known about indoor contamination. Therefore, house dust was sampled based on particle size in 21 wooden buildings (19 residential houses and 2 community centers) within the evacuation area close to the FDNPP, Fukushima Prefecture, Japan. Activities of radiocesium ( 137 Cs) per gram of house dust increased with decreasing particle size (mean: 6.1 × 10 3 , 2.6 × 10 3 , 1.6 × 10 3 , 7.5 × 10 2 , 5.0 × 10 2 , and 4.6 × 10 2  Bq/g for house dust were inversely related to the square of distance from the FDNPP for house dust. It was found that 19%, 33%, and 48% of 137 Cs in house dust were extracted in water, 1 M HCl, and not extracted, respectively. Considering the bioaccessibility and assuming a 20 mg/day daily intake of house dust, the daily doses would be 7.2 Bq/day (mean) and 18 Bq/day (95th percent quantile). These results provide valuable insight into indoor radioactive Cs contamination in the area around the FDNPP and possible oral exposure to indoor radioactive Cs after returning home. Copyright © 2018 The Authors. Published by Elsevier Ltd.. All rights reserved.

  9. An aerial radiological survey of the Yankee Rowe Nuclear Power Station and surrounding area, Rowe, Massachusetts

    International Nuclear Information System (INIS)

    Boyns, P.K.; Bluitt, C.M.

    1993-09-01

    An aerial radiological survey was conducted over the Yankee Rowe Nuclear Power Station in Rowe, Massachusetts, during the period August 17--24, 1989. The survey was conducted at an altitude of 300 feet (91 meters) over an 87-square-mile (225-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Yankee Rowe Power Station and the surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 10 microroentgens per hour (μR/h) and were attributed to naturally-occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based ''benchmark'' exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system

  10. 2006 EM300 Multibeam Sonar Data from Cruise Hi'ialakai HI-06-04 - Pacific Remote Island Areas

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — EM300 multibeam data were collected in 15 March to 8 April 2006 aboard NOAA Ship Hi'ialakai at Jarvis Island, Palmyra Island, and Kingman Island in the Central...

  11. Atividade microbiana do solo em sistemas agroflorestais, monoculturas, mata natural e área desmatada Soil microbial activity in agroforest, monocultures, natural forest and deforested area systems

    Directory of Open Access Journals (Sweden)

    Sebastião Lourenço de Assis Júnior

    2003-02-01

    Full Text Available Este trabalho foi desenvolvido na Unidade Agroflorestal da Companhia Mineira de Metais (CMM, em Vazante, Estado de Minas Gerais, com o objetivo de estudar a atividade microbiana em diferentes ecossistemas, como sistemas agroflorestais (SAFs, monoculturas, área desmatada e mata natural, utilizando os métodos da respirometria no laboratório e da medida não-instantânea da taxa de evolução de CO2 no campo. A atividade biológica apresentou valores acumulados das taxas de respiração do solo, aos 20 dias, de 3,56 a 6,03 meq C-CO2/100 g de solo no laboratório e de 165,16 a 559,37 mg CO2/m-2.h no campo, na área desmatada e na mata nativa, respectivamente. Em ambos os ensaios, a atividade foi maior na mata nativa e nas pastagens, tanto em monocultivo quanto em SAFs. A atividade microbiana foi maior em SAF com arroz e eucalipto do que em arroz em monocultivo, pelo método no campo.This research was developed in the Agroforestry Unit of the "Companhia Mineira de Metais (CMM", Vazante, Minas Gerais, Brazil, to study microbial activity in different ecosystems such as agroforests, monocultures, deforested areas and native forests using the method of respirometry under laboratory conditions and CO2 evaluation rate evolution under field conditions. Biological activity showed accumulated values of respiration rates at 20 days of 3.56 to 6.03 meq C-CO2/100 g of soil in the laboratory, and 165.16 to 559.37 mg CO2/m-2.h in the field, in deforested area and native forest, respectively. Activity was higher in native forest and pasture than in monoculture or agroforestry, in both experiments. Microbial activity was higher in agroforestry with rice and eucalypt than with rice in monoculture, under field conditions.

  12. The PRONUCLEAR role (1976-1986 in the human resource training for the nuclear area in Brazil: science history

    International Nuclear Information System (INIS)

    Schmiedecke, Winston Gomes

    2006-01-01

    In 1975, an agreement between the governments of Brazil and West-Germany was signed for the construction of nuclear power plants in Brazil as well as the extraction, processing and enrichment of uranium. As the result of the first oil crisis and facing the perspective of a continuous world energy crisis, the Brazilian government decided to turn to nuclear power as an alternative supply for the country's energy needs. However, serious limitations were present regarding the transfer of nuclear technology for a third world country. This paper analyzes some aspects of the process involved in the creation of the specialized human resources during the extent of the agreement between Brazil and West Germany. Since its inception, the agreement received harsh criticism from the Brazilian nuclear physics and related fields scientific communities. Because the planning and implementation of the agreement took place during a period of military dictatorship, the decisions relating to the agreement were never debated between the policy makers and the scientific community. Not surprisingly, the agreement received plenty of criticism that ranged from the actual need for nuclear power to technical feasibility and suspicious of possible military uses and even the very policies created to prepare human resources to work in the nuclear area. One of the most important tools of these policies was the Programa de Recursos Humanos para o Setor Nuclear - PRONUCLEAR (Nuclear Sector Human Resources Program), implemented in 1976 and gradually deactivated starting in 1983. (author)

  13. Report on research in progress in the nuclear structure, dynamics area

    International Nuclear Information System (INIS)

    Kodama, T.

    1982-01-01

    The experimental and theoretical studies related to the nuclear dynamics, actually done by the nuclear physical groups in Brazil, are reported. A qualitative division of the several aspects concerning to this subject is shown. (L.C.) [pt

  14. Role of BRNS in the DAE's program in the area of nuclear science and technology

    International Nuclear Information System (INIS)

    Markandeya, S.G.

    2008-01-01

    Full text: Soon after the discovery of fission and recognition of its potential for power production, Atomic Research Commission (ARC) was formed under the Chairmanship of Dr. Homi J. Bhabha, which was later renamed, first as Board of Research in Atomic Energy (BRAE) and subsequently as Board of Research in Nuclear Sciences (BRNS) in late fifties under the Department of Atomic Energy (DAE). The BRNS, right from its inception, has been playing an important role of assisting leading universities, academic and R and D institutions in the country for their participation in the departmental program and also in developing skilled human resources in the country for implementing the DAE's programs. Today BRNS has multiple programs which include; sponsored R and D programs in academic and R and D institutes, conducting/supporting international and national conferences, symposia, seminars, workshops in the advanced thematic areas in nuclear science and technology, building Centres of Excellence by way of equipping laboratories with the state-of-the-art experimental facilities and by way of nurturing the local talent. The program has also effective mechanism to strengthen the DAE-university interface through numerous fellowship schemes which cater to students, research scholars and academic staff in the country .The activities of BRNS have been recently further extended to implement the Prospective Research Funding (PRF) scheme under the current Xlth plan project for research scholars from within the department. Possibilities of establishing linkages with the private R and D houses are also being explored. The present talk will give a quick glimpse of the BRNS activities and illustration of some of the important achievements under its programs. The talk is also aimed at further increasing the awareness about the mechanisms and opportunities for participation in the BRNS activities for the scientists and engineers within and outside the department

  15. Areas control of a nuclear medicine service; Controle de áreas de um serviço de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Islane C.S.; Silva, Iasmim M.S.; Júnior, Cláudio L.R.; Silva, Isvânia S.; Gonzalez, Kethyllém M.; Melo, Francisca A. [Universidade Federal de Pernambuco (UFPE), Recife, PE (Brazil). Dept. de Energia Nuclear; Vieira, Wilson J.; Lopes Filho, Ferdinand de J. [Instituto Federal de Educação, Ciência e Tecnologia de Pernambuco (IFPE), Recife, PE (Brazil); Lima, Fernando R.A. [Centro Regional de Ciências Nucleares do Nordeste (CRCN-NE/CNEN), Recife, PE (Brazil)

    2017-07-01

    The measurement of the exposure rate of the sectors of a nuclear medicine service (NMS), with the purpose of establishing safety to the service workers and the public, classifying the areas according to the monitoring is presented. Following the studies on the classifications of the areas of a Nuclear Medicine service provided by the category regulatory standard, 3.05 CNEN-NN, measures were taken in all sectors of the NMS in order to classify the areas in: Free, controlled and supervised according to with the exposure level. As a measurement instrument, a Geiger-Muller counter of the digital type was used. The results obtained show a correlation with the Brazilian norm satisfactorily, referring to the exposure rate of the studied SMN sectors.

  16. Aedes albopictus em bromélias de solo em Ilhabela, litoral do Estado de São Paulo Aedes albopictus in soil bromeliads in Ilhabela, coastal area of Southeastern Brazil

    Directory of Open Access Journals (Sweden)

    Gisela R A M Marques

    2005-08-01

    Full Text Available OBJETIVO: Analisar a presença de Aedes albopictus em bromélias de solo localizadas em ambientes ecologicamente distintos, em termos de positividade, densidade e volume de água. MÉTODOS: O estudo foi realizado no município de Ilhabela, litoral norte do Estado de São Paulo. Realizaram-se coletas quinzenais, de março de 1998 a julho de 1999, em tanques de bromélias localizadas nos ambientes urbano, periurbano e mata; o conteúdo aquático das plantas foi medido e registrado. O tratamento dos dados baseou-se na análise da freqüência de bromélias com presença de Ae. albopictus (ANOVA, abundância (Kruskal-Wallis e volume de água das bromélias positivas (Teste t de Student. RESULTADOS: A presença e a densidade de Ae. albopictus em bromélias de solo variou com o tipo de ambiente. Os maiores percentuais de positividade (85% e abundância (81% foram observados nas plantas localizadas em ambiente urbano. Constatou-se ainda preferência dos mosquitos pelas bromélias com maiores volumes de água (média de 300 ml. CONCLUSÕES: As diferentes freqüências com que Ae. albopictus foi registrado nos ambientes e suas respectivas densidades mostraram sua capacidade de invasão a novos habitats. Recomenda-se intensificar a vigilância entomológica nessas plantas, dada a sua capacidade em traduzir-se em criadouros permanentes. A presença desse mosquito de importância médica em bromélias em área preservada da Mata Atlântica poderá resultar em agravo à saúde.OBJECTIVE: To analyze the presence of Aedes albopictus in soil bromeliads in ecologically distinct environments in terms of positivity, density and volume of water. METHODS: The study was carried out in the municipality of Ilhabela, North coast of the state of São Paulo, Brazil. Collections were fortnightly performed between March 1998 and July 1999, in containers of bromeliads located in urban, peri-urban and forest environments. The water content in plants was measured and recorded

  17. A study on domino effect in nuclear fuel cycle facilities; Um estudo sobre o efeito domino em instalacoes do ciclo do combustivel nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Bozzolan, Jean-Claude

    2006-07-01

    Accidents caused by domino effect are among the most severe accidents in the chemical and process industry. Although the destructive potential of these accidental scenarios is widely known, little attention has been paid to this problem in the technical literature and a complete methodology for quantitative assessment of domino accidents contribution to industrial risk is still lacking. The present study proposed a systematic procedure for the quantitative assessment of the risk caused by domino effect in chemical plants that are part of nuclear fuel cycle plants. This work is based on recent advances in the modeling of fire and explosion damage to process equipment due to different escalation vectors (heat radiation, overpressure and fragment projection). Available data from literature and specific vulnerability models derived for several categories of process equipment had been used in the present work. The proposed procedure is applied to a typical storage area of a reconversion plant situated in a complex that shelters other nuclear fuel cycle facilities. The top-events and escalation vectors are identified, their consequences estimated and credible domino scenarios selected on the basis of their frequencies. (author)

  18. Advancing Ruggedness of Nuclear Stations By Expanding Defence In Depth in Critical Areas

    International Nuclear Information System (INIS)

    Koshy, Thomas

    2015-01-01

    The nuclear industry continues to rise above the challenges it has faced over the years from external events and internal events. Fukushima event has shed light on a few vulnerabilities that could be overcome by utilizing the current state of technology. Common cause from sea water ingression was not conceived to have the entire electrical power system including AC and DC disabled beyond reasonable recovery. Rather than focusing on the solutions for lessons from Fukushima, it is better to address 'Fukushima type' events and advance the resilience of the NPPs. The effort needs to be on exploring different approaches to overcome such vulnerabilities so that a variety of solutions are available to make appropriate choices on improving NPP ruggedness based on anticipated challenges in the regions. In a technology neutral approach for light water reactors (LWR) there are 4 critical areas that are significant for ensuring nuclear safety. (1) Reactor trip, (2) Depressurization, (3) Emergency Core Cooling, and (4) Containment integrity. The reactor trip had not suffered any significant setbacks in the immediate past but provisions to address Anticipated Transients without Scram (ATWS) were generally included in most designs. While the technology has advanced, software driven/assisted trips are becoming popular and desirable. However, a diverse approach with least probability of potential interference needs to be provided in the control room and remote shutdown area to advance the ruggedness of rector trip. Depressurization is essential for passive as well as active cooling systems and therefore the approaches to de-pressurize should have more than one approach to ensure its success. In the absence of diverse approaches to de-pressurize, it is more important to consider RCS cooling capability during accidents or transients while the reactor is at a higher pressure. In the area of Emergency Core Cooling, the events history demonstrates greater success on diversity

  19. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1991

    Energy Technology Data Exchange (ETDEWEB)

    Chaloud, D.J.; Dicey, B.B.; Mullen, A.A.; Neale, A.C.; Sparks, A.R.; Fontana, C.A.; Carroll, L.D.; Phillips, W.G.; Smith, D.D.; Thome, D.J.

    1992-01-01

    This report describes the Offsite Radiation Safety Program conducted during 1991 by the Environmental Protection Agency`s (EPA`s) Environmental Monitoring Systems Laboratory-Las Vegas. This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of animals, food crops, and humans. Personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each nuclear weapons test to implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any occurrence of radioactivity release. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to current NTS activities. Annual and long-term trends were evaluated in the Noble Gas, Tritium, Milk Surveillance, Biomonitoring, TLD, PIC networks, and the Long-Term Hydrological Monitoring Program.

  20. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1991

    International Nuclear Information System (INIS)

    Chaloud, D.J.; Dicey, B.B.; Mullen, A.A.; Neale, A.C.; Sparks, A.R.; Fontana, C.A.; Carroll, L.D.; Phillips, W.G.; Smith, D.D.; Thome, D.J.

    1992-01-01

    This report describes the Offsite Radiation Safety Program conducted during 1991 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory-Las Vegas. This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of animals, food crops, and humans. Personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each nuclear weapons test to implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any occurrence of radioactivity release. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to current NTS activities. Annual and long-term trends were evaluated in the Noble Gas, Tritium, Milk Surveillance, Biomonitoring, TLD, PIC networks, and the Long-Term Hydrological Monitoring Program

  1. Cytogenetic examination in remote period after the stay in the Semipalatinsk nuclear test site area

    Directory of Open Access Journals (Sweden)

    Nugis V.Yu.

    2015-12-01

    Full Text Available Aim: retrospective cytogenetic indication of doses probably received by individuals during the residence in the region of the Semipalatinsk nuclear test site, at work or service in the Armed Forces on it. Material and methods: the analysis of chromosomal aberrations in peripheral blood lymphocyte cultures of 16 people с using FISH-method. Re-sults. The frequencies of FISH-registered translocations were not significantly different from control values in 7 out of 16 cases; the dose evaluations ranged from 0.20 to 0.75 Sv for the remaining 9 persons. Conclusion. FISH-technique of chromosome aberration analysis allows to make retrospective dose assessment; however it is desirable simultaneously to produce classical analysis also for a more correct interpretation of the results; Detection of single multiaber-rant cells in peripheral blood lymphocyte cultures is characteristic of persons who were in the areas of alpha-emitting radionuclide pollution, what is allowed to talk about radiation damage, but does not allow to make dose assessment.

  2. Development of an area monitor for neutrons using solid state nuclear track detector

    International Nuclear Information System (INIS)

    Zahn, G.S.

    1994-01-01

    An area monitor for neutrons composed of the solid state nuclear track detector (SSNTD) Makrofol DE, together with a (n,α) converter, in the center of a 25 cm diameter polyethylene sphere, is developed. The optimal electrochemical etching conditions for the detection of thermal neutrons by the Makrofol DE using the BN converter are studied, leading to the choice of 55 min, at 30 0 C, under a 44,2 kV.cm -1 electric field with oscillation frequency of 2,0 khz. The response of this system to thermal neutrons, in the optimal conditions, is of 2,76(10)x 10 -3 tr/n. Changing from the BN converter to a 2,73(3)g compressed boric acid tablet this value lowers to 3,88(17)x 10 -4 tr/n. The performance of the whole monitor in the detection of fast neutrons is examined using the BN converter and neutrons from a 241 Am Be source, with a response of 4,4(2)x 10 3 tr.mSv -1 .cm -2 and operational limits between 7(3)μSv and 5,6(2)mSv. The result of the monitoring of the control room of the IPEN Cyclotron accelerator are also presented as a final test for the viability of the practical use of the monitor. (author). 34 refs, 15 figs, 6 tabs, 1 app

  3. Evaluation of early phase nuclear accident clean-up procedures for Nordic residential areas

    International Nuclear Information System (INIS)

    Andersson, K.G.

    1996-12-01

    The work reported was carried out as a part of the EKO-5 project under the framework of the Nordic co-operative NKS programme. The project is aimed at giving guidelines relating to Nordic conditions for the reduction of external doses in the early phase of a major accidental airborne nuclear contamination (essentially with 137 Cs) situation in urban areas. The material in this report describes the expected effects, in terms of immediate dose rate reduction and of reduction of the integrated doses over 70 years, of implementation of the methods which were considered to be feasible for early phase treatment of contaminated urban surfaces. Also given are estimates of the integrated doses if no action were taken. The given estimates were based on the experience obtained through large amounts of in situ measurements on different types of surface, mainly since the Chernobyl accident in 1986. The computer model URGENT, was used to apply the information on the migration of the radioactive material with time, together with the results of Monte Carlo photon transport calculations, for the time-integrated dose estimates. 66 data sheets describe the beneficial effects, costs and disadvantages of application of a feasible method for cleaning in the early phase of a specific type of surface in one of five different urban or suburban environments. These data form the foundation for the recommendations on guidelines, which are the ultimate goal of the EKO-5 project. References are given to recommended supplementary reading. (EG)

  4. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1983

    International Nuclear Information System (INIS)

    Patzer, R.G.; Black, S.C.; Grossman, R.F.; Smith, D.D.

    1984-07-01

    This report covers the routine radiation monitoring activities conducted by the Environmental Monitoring Systems Laboratory-Las Vegas in areas which may be affected by nuclear testing programs of the Department of Energy. This monitoring is conducted to document compliance with standards, to identify trends in environmental radiation, and to provide such information to the public. It summarizes these activities for calendar year 1983. No radioactivity attributable to NTS activities was detectable offsite by the monitoring networks. Using recorded wind data and Pasquill stability categories, atmospheric dispersion calculations based on reported radionuclide releases yield an estimated dose of 5 x 10 -5 man-rem to the population within 80 km of the Nevada Test Site during 1983. World-wide fallout of Kr-85, Sr-90, Cs-137, and Pu-239 detected by the monitoring networks would cause maximum exposure to an individual of less than 0.2 mrem per year. Plutonium and krypton in air were similar to 1982 levels while cesium and strontium in other samples were near the detection limits. An occasional net exposure to offsite residents has been detected by the TLD network. On investigation, the cause of such net exposures has been due to personal habits or occupational activities, not to NTS activities. 29 references, 35 figures, 30 tables

  5. Estimation of thawing cryolithic area with numerical modeling in 3D geometry while exploiting underground small nuclear power plant

    Directory of Open Access Journals (Sweden)

    Melnikov N. N.

    2016-03-01

    Full Text Available The paper presents results on 3D numerical calculation of a thermal task related to assessing a thawing area when placing modules with reactor and steam-turbine facility of a small nuclear power plant in thickness of permafrost rocks. The paper discusses influence of the coefficient of thermal conductivity for large-scaled underground excavations lining and cryolithic area porosity on thawing depth and front movement velocity under different spatial directions

  6. Radioactive characterization of the terrestrial ecosystem in the area of location of the Juragua Nuclear Power Plant

    International Nuclear Information System (INIS)

    Sibello Hernandez, R.Y.; Alonso Hernandez, C.M.; Diaz Asencio, M.; Cartas Aguila, H. A.

    1999-01-01

    In this work the results are exposed obtained by the Laboratory of Environmental Surveillance in the radioactive characterization of the existent terrestrial ecosystem in the area of location of the Juragua Nuclear Power Plants in Cienfuegos, Cuba, starting from 1986 and up to 1993

  7. The economic and structural effects of the Nuclear Research Centre in Karlsruhe on its area

    International Nuclear Information System (INIS)

    Tebbert, H.; Sperling, P.

    The great building activity on the site of the Nuclear Research Centre in Karlsruhe, the setting up and maintenance of technical installations from an experimental setup on a laborytory scale to a prototype nuclear-powered system are of considerable, economic importance for numerous firms in the near and broader vicinity. In 1979, for example orders worth DM 100 million were placed with 850 firms in the town and the rural district of Karlsruhe by the Nuclear Research Centre. (orig.) [de

  8. Geology of the Syncline Ridge area related to nuclear waste disposal, Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    Hoover, D.L.; Morrison, J.N.

    1980-01-01

    The Syncline Ridge area is in the western part of Yucca Flat, Nye Co., Nev. Drill holes, geophysical surveys, mapping, and laboratory studies during 1976 through 1978 were used to investigate argillite in unit J (Mississippian) of the Eleana Formation (Devonian and Mississippian) as a possible nuclear waste repository site. Argillite in unit J has a minimum stratigraphic thickness of at least 700 m. The argillite underlies most of the Syncline Ridge area east of the Eleana Range, and is overlain by Quaternary alluvium and the Tippipah Limestone of Syncline Ridge. At the edges of the Syncline Ridge area, alluvium and volcanic rocks overlie the argillite. The argillite is underlain by more than 1000 m of quartzite, siliceous argillite, and minor limestone in older units of the Eleana Formation. These older units crop out in the Eleana Range. The area is divided into southern, central, and northern structural blocks by two lateral faults. The southern and central blocks either have volumes of argillite too small for a repository site, or have irregular-shaped volumes caused by Mesozoic high-angle faults that make the structure too complex for a repository site. The northern block appears to contain thick argillite within an area of 6 to 8 km 2 . The postvolcanic history of the Syncline Ridge area indicates that the area has undergone less deformation than other areas in Yucca Flat. Most of the late Tertiary and Quaternary deformation consisted of uplift and eastward tilting in the Syncline Ridge area. Preliminary engineering geology investigations indicate that although the competency of the argillite is low, the argillite may be feasible for construction of a nuclear waste disposal facility. Physical, thermal, chemical, and mineralogical properties of the argillite appear to be within acceptable limits for a nuclear waste repository

  9. High incidence of micronuclei in lymphocytes from residents of the area near the Semipalatinsk nuclear explosion test site

    International Nuclear Information System (INIS)

    Tanaka, Kimio; Hoshi, Masaharu; Kamada, Nanao; Tchaijunusova, N.J.; Takatsuji, Toshihiro; Gusev, B.I.; Sakerbaev, A.K.H.

    2000-01-01

    The Semipalatinsk area is highly contaminated with radioactive fallout from 40 years of continuous nuclear testing. The biological effects on human health in this area have not been studied. Significant remaining radioactivities include long-lived radioisotopes of 238, 239, 400 Pu, 137 Cs and 90 Sr. To evaluate the long-term biological effects of the radioactive fallout, the incidence of micronuclei in lymphocytes from residents of the area was observed. Blood was obtained from 10 residents (5 females and 5 males, aged 47 to 55 years old) from each of the 3 areas of Znamenka, Dolon and Semipalatinsk, which are about 50-150 km from the nuclear explosion test site. For micronucleus assay. PHA-stimulated lymphocytes were cultured for 72 h and cytochalasin B was added at 44 h for detecting binuclear lymphocytes. Five thousand binuclear lymphocytes in each resident were scored. The means of micronucleus counts in 1,000 lymphocytes in residents of Semipalatinsk, Dolon and Znamenka were 16.3, 12.6, and 7.80, respectively, which were higher than those of the normal Japanese persons (4.66). These values were equivalent to the results obtained from 0.187-0.47 Gy of chronic exposure to γ-rays at a dose rate of 0.02 cGy/min. The high incidence of micronuclei in residents of the Semipalatinsk nuclear test site area was mainly caused by internal exposure rather than external exposure received for the past 40 years. (author)

  10. Use of the image by nuclear magnetic resonance (nucleography) in obstetrical aspects. Part 1. Emprego da imagem por ressonancia magnetica nuclear (nucleografia) em obstetricia. Parte 1

    Energy Technology Data Exchange (ETDEWEB)

    Lacreta, O [Sao Paulo Univ., SP (Brazil). Faculdade de Medicina

    1987-09-01

    Nuclear magnetic resonance (nucleography) is a new method to study human body. In this paper the physical principles on nuclear magnetic resonance and its applications to the pregnant women are presented. (author).

  11. Euratom research and training in nuclear reactor safety: Towards European research and the higher education area

    International Nuclear Information System (INIS)

    Goethem, G. van

    2004-01-01

    In this invited lecture, research and training in nuclear fission are looked at from a European perspective with emphasis on the three success factors of any European policy, namely: common needs, vision and instruments, that ought to be strongly shared amongst the stakeholders across the Member States concerned. As a result, the following questions are addressed: What is driving the current EU trend towards more research, more education and more training, in general? Regarding nuclear fission, in particular, who are the end-users of Euratom 'research and training' and what are their expectations from EU programmes? Do all stakeholders share the same vision about European research and training in nuclear fission? What are the instruments proposed by the European Commission (EC) to conduct joint research programmes of common interest for the nuclear fission community? In conclusion, amongst the stakeholders in Europe, there seems to be a wide consensus about common needs and instruments, but not about a common vision regarding nuclear. (author)

  12. Etiologia de exantema em crianças em uma área endêmica de dengue Etiology of exanthema in children in a dengue endemic area

    Directory of Open Access Journals (Sweden)

    Delmina de S. Campagna

    2006-10-01

    Full Text Available OBJETIVO: Estudar a etiologia dos casos de exantema com ou sem febre em crianças atendidas no pronto-socorro de um hospital de uma zona endêmica para dengue. MÉTODOS: No período de 21/09/2001 a 20/09/2002, foram inscritas no estudo 95,9% (71/74 das crianças atendidas no pronto-socorro do Hospital Universitário de Campo Grande (MS que apresentassem exantema (percentual de recusa de 4,1%. Após preenchimento do protocolo com os dados das crianças, as mesmas foram submetidas a exame físico seguido da coleta de amostras de sangue para realizar hemograma com contagem de plaquetas e sorologias (IgM e IgG; inicialmente para dengue, rubéola e toxoplasmose e, posteriormente, naqueles casos com resultado negativo, realizou-se sorologia para parvovirose, herpes vírus tipo 6 e sarampo. RESULTADOS: O diagnóstico laboratorial foi confirmado através da pesquisa de anticorpo IgM em 88,7% dos casos investigados: dengue (77,5%, herpes vírus tipo 6 (8,4%, parvovirose (2,8% e diagnóstico inconclusivo em oito pacientes (11,3%. Não foi evidenciada sorologia positiva (IgM para sarampo, rubéola ou toxoplasmose naquela ocasião. As manifestações clínicas mais freqüentes nos pacientes com dengue foram: febre, prurido, prostração, mialgia e prova do laço positiva. Nos pacientes cujo diagnóstico foi dengue, a prova do laço foi positiva em 58,4% (32/55 dos casos, demonstrando diferença estatisticamente significativa quando comparada com o grupo cujo diagnóstico não foi dengue. CONCLUSÕES: Nas crianças com exantema, dengue pode ser a principal enfermidade causal, atentando-se para a epidemiologia do local. É necessário um controle constante da vigilância epidemiológica e sorológica das doenças exantemáticas.OBJECTIVE: To study the etiology of exanthema cases, with or without fever, in children seen in the emergency room of a hospital located in a region where dengue is endemic. METHODS: Enrollment took place between 21/09/2001 and 20

  13. Preparation of neodymium acetate for use in nuclear area and nanotechnology

    Energy Technology Data Exchange (ETDEWEB)

    Queiroz, C.A.S.; Seneda, J.A., E-mail: cqueiroz@ipen.br, E-mail: jaseneda@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil); Filho, W. R. Pedreira, E-mail: walter.pedreira@fundacentro.gov.br [Fundação Jorge Duprat Figueiredo, de Segurança e Medicina do Trabalho (FUNDACENTRO), Sao Paulo, SP (Brazil)

    2017-07-01

    Neodymium and its compounds are being increasingly applied in the manufacture of new materials. In nuclear area neodymium isotopes are used in a variety of scientific applications. Nd-142 has been used to produce short-lived Tm and Yb isotopes. Nd-146 has been suggested to produce Pm-147 and Nd-150 has been used to study double beta decay. Due to the several modern applications using nanomaterials, more and more highly rare earth compounds have been demanded. The researches at IPEN uses the experience gained in rare earth separation for the preparation of some pure acetates, purity > 99.9% for application in nanotechnology research. A simple and economical chemical process to obtaining neodymium acetate of high purity is studied. The raw material in the form of mixed rare earths carbonate comes from Brazilian monazite. It is used the technique of strong cationic exchange resin, proper to water treatment, to the neodymium's fractionation and it is achieved a purity of 99.9% in Nd{sub 2}O{sub 3} and yield greater than or equal 80%, with the elution of rare earths by EDTA solution in pH controlled. The complex of EDTA-neodymium is transformed in neodymium oxide, subsequently the oxide is dissolved in acetic acid to obtain the neodymium acetate. The solid salt was characterized via molecular absorption spectrophotometry, mass spectrometry, thermal analysis, chemical analysis and X ray diffraction. In summary the analytical data collected allowed to conclude that the stoichiometric formula for the neodymium acetate prepared is Nd(CH {sub 3}COOH)3.1.5H{sub 2}O. (author)

  14. Microbial degradation processes in radioactive waste repository and in nuclear fuel storage areas

    International Nuclear Information System (INIS)

    Wolfram, J.H.; Rogers, R.D.; Gazso, L.G.

    1997-01-01

    The intent of the workshop organizers was to convene experts in the fields of corrosion and spent nuclear fuels. The major points which evolved from the interaction of microbiologists, material scientists, and fuel storage experts are as follows: Corrosion of basin components as well as fuel containers or cladding is occurring; Water chemistry monitoring, if done in the storage facility does not take into account the microbial component; Microbial influenced corrosion is an area that many have not considered to be an important contributor in the aging of metallurgical materials especially those exposed to a radiation field; Many observations indicate that there is a microbial or biological presence in the storage facilities but these observations have not been correlated with any deterioration or aging phenomena taking place in the storage facility; The sessions on the fundamentals of microbial influenced corrosion and biofilm pointed out that these phenomena are real, occurring on similar materials in other industries and probably are occurring in the wet storage of spent fuel; All agreed that more monitoring, testing, and education in the field of biological mediate processes be performed and financially supported; Loosing the integrity of fuel assemblies can only cause problems, relating to the future disposition of the fuel, safety concerns, and environmental issues; In other rad waste scenarios, biological processes may be playing a role, for instance in the mobility of radionuclides in soil, decomposition of organic materials of the rad waste, gas production, etc. The fundamental scientific presentations discussed the full gamut of microbial processes that relate to biological mediated effects on metallic and non-metallic materials used in the storage and containment of radioactive materials

  15. Systematic approach for assessment of accident risks in chemical and nuclear processing; Abordagem sistematica para avaliacao de riscos de acidentes em instalacoes de processamento quimico e nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Senne, Junior, Murillo

    2003-07-15

    The industrial accidents which occurred in the last years, particularly in the 80's, contributed a significant way to draw the attention of the government, industry and the society as a whole to the mechanisms for preventing events that could affect people's safety and the environment quality. Techniques and methods extensively used the nuclear, aeronautic and war industries so far were adapted to performing analysis and evaluation of the risks associated to other industrial activities, especially in the petroleum, chemistry and petrochemical areas. The risk analysis in industrial facilities is carried out through the evaluation of the probability or frequency of the accidents and their consequences. However, no systematized methodology that could supply the tools for identifying possible accidents likely to take place in an installation is available in the literature. Neither existing are methodologies for the identification of the models for evaluation of the accidents' consequences nor for the selection of the available techniques for qualitative or quantitative analysis of the possibility of occurrence of the accident being focused. The objective of this work is to develop and implement a methodology for identification of the risks of accidents in chemical and nuclear processing facilities as well as for the evaluation of their consequences on persons. For the development of the methodology, the main possible accidents that could occur in such installations were identified and the qualitative and quantitative techniques available for the identification of the risks and for the evaluation of the consequences of each identified accidents were selected. The use of the methodology was illustrated by applying it in two case examples adapted from the literature, involving accidents with inflammable, explosives, and radioactive materials. The computer code MRA - Methodology for Risk Assessment was developed using DELPHI, version 5.0, with the purpose of systematizing

  16. Systematic approach for assessment of accident risks in chemical and nuclear processing; Abordagem sistematica para avaliacao de riscos de acidentes em instalacoes de processamento quimico e nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Senne Junior, Murillo

    2003-07-15

    The industrial accidents which occurred in the last years, particularly in the 80's, contributed a significant way to draw the attention of the government, industry and the society as a whole to the mechanisms for preventing events that could affect people's safety and the environment quality. Techniques and methods extensively used the nuclear, aeronautic and war industries so far were adapted to performing analysis and evaluation of the risks associated to other industrial activities, especially in the petroleum, chemistry and petrochemical areas. The risk analysis in industrial facilities is carried out through the evaluation of the probability or frequency of the accidents and their consequences. However, no systematized methodology that could supply the tools for identifying possible accidents likely to take place in an installation is available in the literature. Neither existing are methodologies for the identification of the models for evaluation of the accidents' consequences nor for the selection of the available techniques for qualitative or quantitative analysis of the possibility of occurrence of the accident being focused. The objective of this work is to develop and implement a methodology for identification of the risks of accidents in chemical and nuclear processing facilities as well as for the evaluation of their consequences on persons. For the development of the methodology, the main possible accidents that could occur in such installations were identified and the qualitative and quantitative techniques available for the identification of the risks and for the evaluation of the consequences of each identified accidents were selected. The use of the methodology was illustrated by applying it in two case examples adapted from the literature, involving accidents with inflammable, explosives, and radioactive materials. The computer code MRA - Methodology for Risk Assessment was developed using DELPHI, version 5.0, with the purpose of

  17. Quantification of tomography images for dose calculation for diagnosis and therapy in nuclear medicine; Quantificacao de imagens tomograficas para calculo de dose em diagnose e terapia em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Massicano, Felipe

    2010-07-01

    The nuclear medicine area has an increasing slope in the therapy of diseases, particularly in the treatment of radiosensitive tumors. Due to the high dose levels in radionuclide therapy, it is very important the accurate quantify of the dose distribution to avoid deleterious effects on healthy tissues. In Brazil, the internal dosimetry system used is the MIRD (Medical Internal Radiation Dose) based on a reference model that does not have adequate patient data to obtain a dose accurate assessment in therapy. However, in recent years, internal radionuclide dosimetry evaluates the spatial dose distribution base ad on information obtained from CT and SPECT or PET images together with the using of Monte Carlo codes. Those systems are called patient-specific dosimetry systems. In the Nuclear Engineering Center at IPEN, this methodology is in development. When the CT images are inserted into the Monte Carlo code MCNP5 through of use of a interface software called SCMS the dosimetry can be accomplished using patient-specific data, resulting in a more accurate energy deposition in organs of interest. This work aim to contribute with the development of part of that patient-specific dosimetry for therapy. To achieve this goal we have proposed three specific objectives: (1) Development of a software to convert images from Computed Tomography (CT) in the tissue parameters ({rho}, {omega}({iota})); (2) Development of a software to perform attenuation correction in nuclear medicine tomographic images (SPECT or PET) and to provide the map of relative activity and (3) Provide data to the SCMS code by these two software. The software developed for the rst specific objective was the Image Converter Computed Tomography (ICCT), which obtained a good accuracy to determine the density and the tissue composition; the elements that had high variation were carbon and oxygen. Fortunately, this variation for the energy range used in radionuclide therapy is not detrimental to the dose

  18. Aplicativo para dosimetria interna usando a distribuição biocinética de fótons baseada em imagens de medicina nuclear

    Directory of Open Access Journals (Sweden)

    Viriato Leal Neto

    2014-10-01

    Full Text Available Objetivo: Este artigo apresenta uma forma de se obterem estimativas de dose em pacientes submetidos a tratamentos radioterápicos a partir da análise das regiões de interesse em imagens de medicina nuclear. Materiais e Métodos: Foi desenvolvido o software denominado DoRadIo (Dosimetria das Radiações Ionizantes, que recebe as informações sobre os órgãos fontes e o órgão alvo e retorna resultados gráficos e numéricos. As imagens de medicina nuclear utilizadas foram obtidas de catálogos disponibilizados por físicos médicos. Nas simulações utilizaram-se modelos computacionais de exposição constituídos por fantomas de voxels acoplados ao código Monte Carlo EGSnrc. O software foi desenvolvido no Microsoft Visual Studio 2010 com o modelo de projeto Windows Presentation Foundation e a linguagem de programação C#. Resultados: Da aplicação das ferramentas foram obtidos: o arquivo para otimização das simulações Monte Carlo utilizando o EGSnrc, a organização e compactação dos resultados dosimétricos com todas as fontes, a seleção das regiões de interesse, a contagem da intensidade dos tons de cinza nas regiões de interesse, o arquivo das fontes ponderadas e, finalmente, todos os resultados gráficos e numéricos. Conclusão: A interface de usuários pode ser adaptada para uso em clínicas de medicina nuclear como ferramenta computacional auxiliar na estimativa da atividade administrada.

  19. U.S. and Russian Collaboration in the Area of Nuclear Forensics

    Energy Technology Data Exchange (ETDEWEB)

    Kristo, M J

    2007-10-22

    Nuclear forensics has become increasingly important in the fight against illicit trafficking in nuclear and other radioactive materials. The illicit trafficking of nuclear materials is, of course, an international problem; nuclear materials may be mined and milled in one country, manufactured in a second country, diverted at a third location, and detected at a fourth. There have been a number of articles in public policy journals in the past year that call for greater interaction between the U. S. and the rest of the world on the topic of nuclear forensics. Some believe that such international cooperation would help provide a more certain capability to identify the source of the nuclear material used in a terrorist event. An improved international nuclear forensics capability would also be important as part of the IAEA verification toolkit, particularly linked to increased access provided by the additional protocol. A recent study has found that, although international progress has been made in securing weapons-usable HEU and Pu, the effort is still insufficient. They found that nuclear material, located in 40 countries, could be obtained by terrorists and criminals and used for a crude nuclear weapon. Through 2006, the IAEA Illicit Trafficking Database had recorded a total of 607 confirmed events involving illegal possession, theft, or loss of nuclear and other radioactive materials. Although it is difficult to predict the future course of such illicit trafficking, increasingly such activities are viewed as significant threats that merit the development of special capabilities. As early as April, 1996, nuclear forensics was recognized at the G-8 Summit in Moscow as an important element of an illicit nuclear trafficking program. Given international events over the past several years, the value and need for nuclear forensics seems greater than ever. Determining how and where legitimate control of nuclear material was lost and tracing the route of the material from

  20. U.S. and Russian Collaboration in the Area of Nuclear Forensics

    International Nuclear Information System (INIS)

    Kristo, M J

    2007-01-01

    Nuclear forensics has become increasingly important in the fight against illicit trafficking in nuclear and other radioactive materials. The illicit trafficking of nuclear materials is, of course, an international problem; nuclear materials may be mined and milled in one country, manufactured in a second country, diverted at a third location, and detected at a fourth. There have been a number of articles in public policy journals in the past year that call for greater interaction between the U. S. and the rest of the world on the topic of nuclear forensics. Some believe that such international cooperation would help provide a more certain capability to identify the source of the nuclear material used in a terrorist event. An improved international nuclear forensics capability would also be important as part of the IAEA verification toolkit, particularly linked to increased access provided by the additional protocol. A recent study has found that, although international progress has been made in securing weapons-usable HEU and Pu, the effort is still insufficient. They found that nuclear material, located in 40 countries, could be obtained by terrorists and criminals and used for a crude nuclear weapon. Through 2006, the IAEA Illicit Trafficking Database had recorded a total of 607 confirmed events involving illegal possession, theft, or loss of nuclear and other radioactive materials. Although it is difficult to predict the future course of such illicit trafficking, increasingly such activities are viewed as significant threats that merit the development of special capabilities. As early as April, 1996, nuclear forensics was recognized at the G-8 Summit in Moscow as an important element of an illicit nuclear trafficking program. Given international events over the past several years, the value and need for nuclear forensics seems greater than ever. Determining how and where legitimate control of nuclear material was lost and tracing the route of the material from

  1. The IAEA Response and Assistance Network (RANET) and the New Nuclear Installation Assessment and Advice Functional Area

    Energy Technology Data Exchange (ETDEWEB)

    Kenny, P.; Chaput, J., E-mail: P.Kenny@iaea.org [International Atomic Energy Agency (IAEA), Department of Nuclear Safety and Security, Wagramer Strasse 5, P.O. Box 100, 1400 Vienna (Austria)

    2014-10-15

    Full text: The Incident and Emergency Centre (IEC) of the International Atomic Energy Agency (IAEA) is the global focal point for international preparedness and response to nuclear and radiological safety or security related incidents, emergencies, threats or events of media interest. The Convention on Assistance in Case of a Nuclear Accident or Radiological Emergency (Assistance Convention) and the Convention on Early Notification of a Nuclear Accident (Early Notification Convention) are the prime legal instruments that establish an international framework to facilitate the exchange of information and the prompt provision of assistance in the event of a nuclear accident or radiological emergency. They place specific obligations on the Parties and the IAEA, with the aim of minimizing consequences for health, property and the environment. Parties to the Assistance Convention have agreed to cooperate with each other and with the IAEA to facilitate prompt provision of assistance in case of a nuclear or radiological emergency, in order to mitigate its consequences. As part of the IAEA’s strategy for supporting practical implementation of the Assistance Convention and in order to coordinate a global response, the IEC manages the IAEA’s Response and Assistance Network (RANET). RANET aims to facilitate assistance in case of a nuclear or radiological incident or emergency in a timely and effective manner on a regional basis. States Parties shall, within the limits of their capabilities, identify and notify the Agency of experts, equipment and materials which could be made available for the provision of assistance and register these capabilities in RANET. These capabilities are registered in eight difference Functional Areas which are grouped by the type of assistance that could be provided. Experience gained from past emergencies and based on feedback and direction clearly received from Member States under the IAEA Action Plan on Nuclear Safety resulted in the

  2. Periodical public opinion survey on nuclear energy. Inhabitants living in the Tokyo metropolitan area

    International Nuclear Information System (INIS)

    Shinoda, Yoshihiko; Tsutida, Shouji; Kimura, Hiroshi

    2014-01-01

    Fukushima Daiichi nuclear power plant accident (Fukushima accident) has brought about a great change in many people's perceptions about nuclear power plant safety. When discussing future energy options for Japan, it is important to have a full grasp of the attitude of a large number of people towards nuclear energy. The Atomic Energy Society of Japan has conducted annual questionnaire survey of 500 adults who live within 30 kilometers of Tokyo Station. The aim of this survey is to assess trends in public attitude towards nuclear energy. The authors that designed the questionnaire entries of this survey have been managing questionnaire data as members of the Data Management Working Group under the Social and Environmental Division of the Atomic Energy Society of Japan. We confirmed the change in public attitude towards nuclear energy through this periodical survey after the Fukushima accident. In particular, public concerns about the use of nuclear energy increased after the Fukushima accident, and many people have raised doubts over the use of nuclear energy in the future. (author)

  3. Determination of radionuclides. Fingerprint determination on protection clothing from the controlled areas in nuclear facilities

    International Nuclear Information System (INIS)

    Scholand, Soeren

    2014-01-01

    ENS (Euro Nuclear Services) in Coevorden, Netherlands, is decontaminating und providing protection clothing for the personnel in nuclear facilities. The capacity of the laundry is about 750 kg/h. The clean laundry section is cleaning non-contaminated or very low contaminated articles, i.e. socks or underwear. Fingerprint is defined as the activity of certain radionuclides that differs in the different nuclear facilities. For the reception inspection the dose rate measured with scintillation detectors is compared with the customer specific fingerprint. The total activity is usually 2000 Bq/g. The dose rate limit is 0.3 mSv/h.

  4. Fire protection equipment in the area of control of the Neckar Community Nuclear Power Station

    International Nuclear Information System (INIS)

    Bernhardt, S.; Grauf, E.

    1976-01-01

    In the Neckar Community Nuclear Power Station - an 805 MW pressurised water reactor shortly to reach the stage of nuclear operation - fire protection measures have been realised to an extent hitherto uncommon in German nuclear power plants. The reason is to be sought from the authorities who have become more sensitive because of a fire in a reactor vessel during the construction stage and the fire at Browns Ferry and have consequently become extremely expert. Apart from the fire regulations hitherto normal further subregulations have been created in order to be able to make better provision of extinguishing devices against fire hazards. (orig.) [de

  5. Brazilian spotted fever in cart horses in a non-endemic area in Southern Brazil Febre maculosa brasileira em cavalo de carroceiro em área não-endêmica no Sul do Brasil

    Directory of Open Access Journals (Sweden)

    Marta Cristina Diniz de Oliveira Freitas

    2010-06-01

    Full Text Available Brazilian Spotted Fever (BSF is an often fatal zoonosis caused by the obligate intracellular bacterium Rickettsia rickettsii. The disease is generally transmitted to humans by Amblyomma spp. ticks. Serological evidence of past infection by R. rickettsii has been reported in horses, but the pathogenicity of R. rickettsii in horses remains unknown. Cart horses are still widely used in urban and urban fringe areas in Brazil, and these animals may constitute suitable sentinels for BSF human in these areas, for example, in Sao Jose dos Pinhais, where the first BSF human case in the state of Parana was diagnosed. Serum samples were randomly obtained from 75 cart horses between April 2005 and June 2006 and were tested by means of the indirect immunofluorescence assay (IFA for antibodies against rickettsia of the spotted fever group. A total of 9.33% of the animals were considered positive, with titers ranging from 64 to 1,024. These results indicate the presence of the agent in such areas, although at low rates.A febre maculosa brasileira (FMB é uma zoonose, muitas vezes fatal, causada pela bactéria intracelular obrigatória Rickettsia rickettsii. A doença é transmitida para humanos pelo carrapato Amblyomma spp. Sorologia positiva por R. rickettsii foi relatada em cavalos, entretanto a patogenia de R. rickettsii em cavalos é desconhecida. Cavalos de carroceiros ainda são largamente utilizados em áreas urbanas e peri-urbanas no Brasil e estes animais podem representar sentinelas ideais para FMB nestas áreas, como exemplo, São José dos Pinhais, onde o primeiro caso humano de FMB foi descrita no Paraná. Amostras de soro foram obtidas aleatoriamente de 75 cavalos de carroceiros entre abril de 2005 e junho de 2006 e testados pela reação de imunofluorescência indireta (RIFI com anticorpos contra riquétsias do grupo da febre maculosa. Um total de 9,33% dos animais foi considerado positivo, com títulos entre 64 e 1.024. Estes resultados indicam

  6. Clinical pattern of severe <em>Plasmodium falciparumem> malaria in Sudan in an area characterized by seasonal and unstable malaria transmission

    DEFF Research Database (Denmark)

    Giha, H A; Elghazali, G; A-Elgadir, T M E

    2005-01-01

    A hospital-based study was carried out in Gedarif town, eastern Sudan, an area of markedly unstable malaria transmission. Among the 2488 diagnosed malaria patients, 4.4% fulfilled the WHO criteria for severe malaria, and seven died of cerebral malaria. The predominant complication was severe mala...

  7. Foraging range, habitat use and minimum flight distances of East Atlantic Light-bellied Brent Geese <em>Branta bernicla hrota em>in their spring staging areas

    DEFF Research Database (Denmark)

    Clausen, Kevin Kuhlmann; Clausen, Preben; Hounisen, Jens Peder

    2013-01-01

    Global Positioning System (GPS) satellite telemetry was used to determine the foraging range, habitat use and minimum flight distances for individual East Atlantic Light-bellied Brent Geese Branta bernicla hrota at two spring staging areas in Denmark. Foraging ranges (mean ± s.d. = 53.0 ± 23.4 km...

  8. L'area faunistica del camoscio appenninico (<em>Rupicapra pyrenaica ornataem> di Lama dei Peligni. Evoluzione del nucleo e problemi gestionali

    Directory of Open Access Journals (Sweden)

    L. Gentile

    2003-10-01

    Full Text Available L'Area Faunistica del Camoscio appenninico di Lama dei Peligni (CH nel Parco Nazionale della Majella è stata istituita nel 1990 con lo scopo principale di fungere da serbatoio di animali da utilizzare per operazioni di rinforzo della popolazione di Camosci in natura. Inoltre è stata ed è un notevole strumento per sensibilizzare la popolazione ed il pubblico alla conservazione della specie nonché una forte attrazione turistica per l'intera Valle dell'Aventino nel Parco Nazionale della Majella. L'Area Faunistica è ubicata nei pressi del centro abitato di Lama dei Peligni (CH sul versante Orientale della Majella ad un'altitudine che va dai 750 agli 850 m s.l.m. ed ha un'astensione complessiva di 4,2 ettari. Nel corso degli anni è stato necessario suddividere il recinto in 4 subrecinti per poter disporre di spazi separati utili per la gestione sanitaria del nucleo di animali ospitati. Inizialmente la responsabilità tecnica amministrativa è stata curata dal Parco Nazionale d'Abruzzo in collaborazione con il WWF Italia, successivamente è stata curata dalla Riserva Regionale "Majella Orientale" per passare dal 2000 all'Ente Parco Nazionale della Majella. L'area faunistica di Lama dei Peligni è stata attivata con l'immissione di un maschio prelevato in natura dalla popolazione della Val di Rose nel Parco Nazionale d'Abruzzo, Lazio e Molise e 5 femmine provenienti dal'Area Faunistica di Bisegna nel medesimo Parco. Nel periodo dal 1990 al 2002 sono nati 37 camosci e ne sono deceduti 20. Inoltre si sono verificati 14 rientri di animali provenienti dalla popolazione in natura e dall'Area Faunistica sono stati reimmessi 25 capi sul massiccio della Majella. L'Area di Lama dei Peligni ha consentito l'attivazione di un'ulteriore Area Faunistica nel Parco Nazionale del Gran Sasso Monti della Laga fornendo 1 femmina. Lo scopo principale del presente lavoro è di analizzare criticamente i dati raccolti in un database e di individuare un protocollo di

  9. Manpower and areas of activity in the nuclear research centers in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Miessner, H.

    1984-12-01

    A survey is presented of tasks and functions of the nuclear research centers, which belong to the 13 big research establishments in the Federal Republic of Germany. The central R+D-activities in the nuclear field (high temperature reactor, fast breeder, uranium enrichment, reprocessing, waste handling, nuclear safety, nuclear fusion, fusion technology, plasma physics and technology) and the manpower assigned to these activities are described. Future developments in R+D and in manpower are discussed. An outline is given of cooperation established with industry, universities and other institutions. The number of staff and its composition in terms of education and qualification are indicated. Staff mobility, especially transfer to industry, manpower development of junior staff and training efforts are discussed. (orig.) [de

  10. Virtual reality technology used to estimate radiation doses in nuclear installations; Utilizacao de ambientes virtuais na estimativa de dose de radiacao em instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Augusto, Silas Cordeiro

    2008-03-15

    The physical integrity of people when walking in places subjected to radiation can be preserved by following some rules. Among these rules are safe limits of radiation level, proximity of radiation sources, time of exposition to radiation sources, and a combination of these factors. In this way, previous training and simulations of operation proceedings to be executed in places subjected to radiation help to better prepare the course in such places, minimizing the absorbed dose. On the other hand, virtual reality is a technology applicable in several areas, enabling the training and simulation of real places and hypothetical scenarios, with a good level of realism, but without danger if compared to the same activities in the real world. As a virtual environment does not presents any health risks, it is possible to train workers beforehand to several operation or maintenance scenarios. In this virtual environment, the dose tax distribution can be visualized, and the dose absorbed by the worker, represented and simulated in the virtual environment by a virtual character (avatar) can be shown. Therefore, the tasks to be done can be better planned, evaluating the workers actions and the performance so to reduce failures and health risks. Finally, this work presents a tool to build and navigate in virtual environments, enabling the training of activities in nuclear facilities. To that end is proposed a methodology to modify and adapt a free game engine. (author)

  11. DNA damage, acetylcholinesterase activity and lysosomal stability in native and transplanted mussels (<em>Mytilus edulisem>) in areas close to coastal chemical dumping sites in Denmark

    DEFF Research Database (Denmark)

    Rank, J.; Lehtonen, K. K.; Strand, J.

    2007-01-01

    of chemical pollution complex, as seen especially in the variability in results on DNA damage, and also in regard to AChE activity. These investigations further stress the importance of understanding the effects of natural factors (salinity, temperature, water levels, rain and storm events) in correct......Biomarkers of genotoxicity (DNA damage, measured as tail moment in the Comet assay), neurotoxicity (acetylcholinesterase inhibition, AChE) and general stress (lysosomal membrane stability, LMS) were studied in native and transplanted blue mussels (Mytilus edulis) in coastal areas of western Denmark...... potentially affected by anthropogenic pollution originating from chemical dumping sites. The results indicate responses to pollution in all the biomarkers applied at the suspected areas, but the results were not consistent. Seasonal fluctuations in exposure situations at the study sites make interpretation...

  12. Birth defects in perinatal infants in areas contiguous to Hongyanhe Nuclear Power Plant before its normal operation

    International Nuclear Information System (INIS)

    Zhou Ling; Yin Zhihua; Han Zhonghui

    2011-01-01

    Objective: To understand the status of birth defects among the perinatal infants in the areas contiguous to Hongyanhe nuclear power plant before its normal operation, so as to provide background information for the evaluation of the impact of nuclear power plant on birth defects. Methods: From 1 October 1995 to 30 September 2009 the midwifery units at second class and above of Wafangdian City were asked to be in charge of recording the birth defects among the perinatal infants born during this period within the range of 50 km around the Hongyanhe nuclear power plant. Results: The total number of birth defects was 697, and the maternal number Was 83779. The average defect rate Was 83.20/10 4 . There were significant differences in the birth defect rate among different years (χ 2 =39.54, P<0.05), however, without linear trend therein,and among the survey areas (χ 2 =15.36, P<0.05) as well. The top five birth defects were congenital heart disease (148 cases), cleft lip with cleft palate (67 cases), congenital hydrocephalus (63 cases), and spina bifida (37 cases) and cleft lip (36 cases). Conclusions: The birth defect rate within the range of 50 km around the Hongyanhe nuclear power plant is lower than that of the region of Liaoning Province and the national rate of birth defects. (authors)

  13. A guide to countermeasures for implementation in the event of a nuclear accident affecting nordic food-producing areas

    International Nuclear Information System (INIS)

    Andersson, K.G.; Roed, J.; Rantavaara, A.; Rosen, K.; Salbu, B.; Skipperud, L.

    2000-08-01

    State-of-the-art information on methods for management of nuclear accidents affecting food-producing areas has been reviewed, evaluated and transposed to reflect conditions relevant to the Nordic countries. This data, describing in detail the various method-specific costs and benefits, is reported in a well-arranged format facilitating analyses in connection with decision-making. Guidance, recommendations and examples are given as to how the individual data sheets may be used in emergency preparedness planning. (au)

  14. Condiciones de vida en zonas palúdicas de Antioquia (Colombia, 2005 Condições de vida em zonas palúdicas de Antioquia (Colômbia, 2005 Living conditions in Antioquia's (Colombia paludic areas, 2005

    Directory of Open Access Journals (Sweden)

    Jaime Carmona Fonseca

    2010-07-01

    ílias de meninos palúdicos em duas zonas de Antioquia. Metodologia. Desenho descritivo de corte transversal. Descrevese e analisa um conjunto de variáveis socioeconômicas que expressam as condições de vida dessas famílias, em 2004-2005. Resultados. 88 famílias dos municípios de Turvo e O Bagre, o 58% viviam em zona. Em general, as variáveis analisadas apresentam diferença estatisticamente significativa por município e zona (piores condições: Turvo-rural; menos más: O Bagre-urbano. Os rasgos familiares mais frequentes foram: famílias nucleares típicas (66%, com uma média de 7,1 membros. Habitam ranchos/tugúrios o 29%, contam com serviço sanitário intradomicilio o 42%, atiravam o lixo em campo aberto o 31%. O 69% das moradias têm Peri - domicilio com vegetação e outro 66% tem água estancada/corrente. O pai trabalhava em 64%, o trabalho era instável em 59% dos casos; as ocupações mais comuns foram de agricultor (53%, mineiro (13% e jornaleiro (12%. O rendimento monetário mensal médio era de só $244 000. Teve 58% das famílias com fontes estáveis de alimentos. O consumo de carnes/vísceras animais foi menor de uma 1 vez/semana, leite e ovos de 2-3 vezes/ semana, frutas ricas em carotenos provitamina A não se consumiam. Os alimentos consumidos tinham alta probabilidade de satisfazer os requerimentos familiares de VITAMINA A em grau alto (45%. Conclusão. As condições de vida das famílias que residem em Turbo e El Bagre são muito deficientes e é elevada a quantidade de famílias com necessidades básicas não satisfeitas. Há importantes diferenças entre os municípios de estudo e entre a zona urbana e rural. A situação de má qualidade de vida nestas regiões maláricas supera amplamente o referido pelas médias para o departamento de Antioquia e para a Colômbia.Objective. To explore the paludic children families living conditions in two different areas of Antioquia. Methodology. Transversal cut, descriptive design. A group of

  15. Development of sealed radioactive sources immobilized in epoxy resin for verification of detectors used in nuclear medicine; Desenvolvimento de fontes radioativas seladas imobilizadas em resina epoxi para verificacao de detectores utilizados em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Tiezzi, Rodrigo

    2016-07-01

    The radioactive sealed sources are used in verification ionization chamber detectors, which measure the activity of radioisotopes used in several areas, such as in nuclear medicine. The measurement of the activity of radioisotopes must be made with accuracy, because it is administered to a patient. To ensure the proper functioning of the ionization chamber detectors, standardized tests are set by the International Atomic Energy Agency (IAEA) and the National Nuclear Energy Commission using sealed radioactive sources of Barium-133, Cesium-137 and Cobalt-57. The tests assess the accuracy, precision, reproducibility and linearity of response of the equipment. The focus of this work was the study and the development of these radioactive sources with standard Barium-133 and Cesium-137,using a polymer, in case commercial epoxy resin of diglycidyl ether of bisphenol A (DGEBA) and a curing agent based on modified polyamine diethylenetriamine (DETA), to immobilize the radioactive material. The polymeric matrix has the main function of fix and immobilize the radioactive contents not allowing them to leak within the technical limits required by the standards of radiological protection in the category of characteristics of a sealed source and additionally have the ability to retain the emanation of any gases that may be formed during the manufacture process and the useful life of this artifact. The manufacturing process of a sealed source standard consists of the potting ,into bottle standardized geometry, in fixed volume of a quantity of a polymeric matrix within which is added and dispersed homogeneously to need and exact amount in activity of the radioactive materials standards. Accordingly, a study was conducted for the choice of epoxy resin, analyzing its characteristics and properties. Studies and tests were performed, examining the maximum miscibility of the resin with the water (acidic solution, simulating the conditions of radioactive solution), loss of mechanical and

  16. United States assistance to Kazakstan in the area of nuclear material security

    International Nuclear Information System (INIS)

    Tittemore, G.; Mitchell, W.

    1996-01-01

    The US has agreed to pursue cooperative nuclear Material Protection, Control and Accounting (MPC and A) programs with the Republic of Kazakstan. As part of this cooperation, a state system of control accounting and physical protection for nuclear materials is being developed. The US Department of Energy is providing assistance at the four nuclear sites in the Republic to enhance MPC and A systems, techniques, hardware, software, procedures, and training. US survey teams, which include both material control and accounting (MC and A) and physical protection experts, have visited four nuclear sites in Kazakstan. MPC and A assistance is being provided to the Ulba State Holding Company, the Institute of Atomic Energy at Kurchatov City and Ala Tau, and the Mangyshlak Atomic Energy Complex (MAEC) BN-350 nuclear power plant in Aktau. At these sites, the facility staffs and DOE technical teams are working together to identify conditions not completely conforming with accepted international standards, as well as potential enhancements to correct such conditions. Design packages for enhancements at each of these facilities are prepared in collaboration with Kazakstani specialists. After agreement is reached on the specifications by the US and Kazakstan, MPC and A equipment is procured and installed. This paper summarizes the approach to the cooperative programs at these facilities, program status, and future plans

  17. Activities of the IAEA Nuclear Energy Department in the area of fuel engineering

    International Nuclear Information System (INIS)

    Bychkov, A.; ); Inozemtsev, V.; )

    2012-01-01

    The IAEA presentation provides an outlook on the current status and projections of nuclear power development in the world taking into account the affect of the Fukushima accident, as well as information about the IAEA Action Plan on Nuclear Safety that was unanimously enforced by 151 Member States at the IAEA General Conference in September 2011. Details are given about the implementation tools of the sub-programme 'Nuclear Power Reactor Fuel Engineering': Technical Meetings, Coordinated Research Projects, and Expert Reviews. This information about recent, on-going and planned IAEA activities related to fuel R and D, design, manufacturing, in-reactor behaviour and operational experience will be useful for specialists interested in corresponding publications or for those planning participation in the IAEA projects. Particular emphasis is made on CQCNF priority subjects, including preparation of the IAEA Nuclear Energy Series Guide on Quality and Reliability of Fuel for Water-Cooled Power Reactors, where the expert group from the Nuclear Fuel Complex in Hyderabad was among the key contributors. (author)

  18. Harmonizing nuclear safety practices in Europe: WENRA activities in the area of waste management

    International Nuclear Information System (INIS)

    Theis, St.; Dandrieux, G.; Feron, F.

    2011-01-01

    The Western European Nuclear Regulators Association (WENRA) was created in 1999. It originally consisted of the heads of the nuclear safety authorities of the member countries of the European Union (E.U.), plus Switzerland. The original objectives of the Association were: -) to develop a common approach to nuclear safety and regulation, in particular within the E.U.; -) to provide the E.U. with an independent capability to examine nuclear safety and regulation in candidate countries; -) to evaluate and achieve a common approach to nuclear safety and regulatory issues which arise. For the detailed work WENRA set up two working groups, for reactor safety (RHWG: reactor harmonization working group) and a little later for waste and decommissioning (WGWD: working group on waste and decommissioning). The basis for all WENRA work is the WENRA policy statement which as a major promoter of developments contains a self commitment of all WENRA member states to implement without undue delay harmonized requirements produced by the working groups after approval of the WENRA plenary. First WENRA publications receiving much public interest were mainly dedicated to the safety of power reactor, and more recently on new reactors and on long term operation of currently operating reactors. (authors)

  19. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1981

    International Nuclear Information System (INIS)

    Black, S.C.; Grossman, R.F.; Mullen, A.A.; Potter, G.D.; Smith, D.D.; Hopper, J.L.

    1982-08-01

    This report, prepared in accordance with the guidelines in DOE/E-0023 (DOE 1981), covers the program activities conducted around Nevada Test Site (NTS) for calendar year 1981. It contains descriptions of pertinent features of the NTS and its environs, summaries of the dosimetry and sampling methods, analytical procedures, and the analytical results from environmental measurements. Where applicable, dosimetry and sampling data are compared to appropriate guides for external and internal exposures of humans to ionizing radiation. The monitoring networks detected no radioactivity in the various media which could be attributed to US nuclear testing. Small amounts of fission products were detected in air samples as a result of the People's Republic of China nuclear test and atmospheric krypton-85 increased, following the trend beginning in 1960, due to increased use of nuclear technology. Strontium-90 in milk and cesium-137 in meat samples continued the slow decline as observed for the last several years

  20. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1981

    Energy Technology Data Exchange (ETDEWEB)

    Black, S.C.; Grossman, R.F.; Mullen, A.A.; Potter, G.D.; Smith, D.D.; Hopper, J.L. (comps.)

    1982-08-01

    This report, prepared in accordance with the guidelines in DOE/E-0023 (DOE 1981), covers the program activities conducted around Nevada Test Site (NTS) for calendar year 1981. It contains descriptions of pertinent features of the NTS and its environs, summaries of the dosimetry and sampling methods, analytical procedures, and the analytical results from environmental measurements. Where applicable, dosimetry and sampling data are compared to appropriate guides for external and internal exposures of humans to ionizing radiation. The monitoring networks detected no radioactivity in the various media which could be attributed to US nuclear testing. Small amounts of fission products were detected in air samples as a result of the People's Republic of China nuclear test and atmospheric krypton-85 increased, following the trend beginning in 1960, due to increased use of nuclear technology. Strontium-90 in milk and cesium-137 in meat samples continued the slow decline as observed for the last several years.

  1. An aerial radiological survey of the Seabrook Nuclear Station and surrounding area, Seabrook, New Hampshire, July 1988

    International Nuclear Information System (INIS)

    1989-09-01

    An aerial radiological survey was conducted over the Seabrook Nuclear Station, Seabrook, New Hampshire, during the period 6 July through 14 July 1988. The purpose of the 247-square-kilometer (96-square-mile) survey was to document the terrestrial gamma environment of the station and surrounding area. An exposure rate contour map at 1 meter above ground level (AGL) was constructed from the gamma data and overlaid on an aerial photograph and map of the area. Exposure rates measured in the area typically ranged form 9 to 12 microroentgens per hour (μR/h). In areas where water shielded the earth, lower exposure rates were measured. Ground-based exposure rate measurements and soil samples were obtained to support the aerial data. Oblique aerial photographs of the station were also acquired during the survey. 9 refs., 5 figs., 1 tab

  2. The sixth Euratom framework programme 2003-2006: a driving force for the construction of the Nuclear European Research Area

    International Nuclear Information System (INIS)

    Fernandez-Ruiz, P.; Forsstroem, H.; Goethem, G. van

    2005-01-01

    At the Lisbon 2000 summit, a strategic goal was proposed for the European Union: 'to become the most competitive knowledge-based economy with more and better employment and social cohesion by 2010'. Overall, in particular in the community of nuclear fission research, this EC initiative was well accepted by the main stakeholders. In Europe, the main stakeholders (i.e. suppliers and/or demanders) of nuclear research are actually: the research organisations (with mixed public/private funding), the manufacturing industry (or vendors), the utilities (or engineering companies), the regulatory bodies (or technical safety organisations) and the academia (or universities). In response to the Lisbon 2000 objectives, Commissioner P. BUSQUIN launched the concept of European Research Area (ERA) which sets also the frame for the FP-6. In this invited lecture, research and training in nuclear fission are looked at from a nuclear ERA perspective with emphasis on the three success factors of any European integration policy, namely: needs, vision and instruments, that ought to be strongly shared amongst the stakeholders in the EU-25. The following questions are addressed. What is driving the current EU trend towards more research, more education and more training in general? Regarding nuclear fission, in particular, who are the end-users of Euratom 'research and training' and what are their expectations (needs) from EU programmes? Do all stakeholders share the same vision about European research and training in nuclear fission? What are the instruments proposed by the Commission to the end-users to conduct joint research programmes? The above questions are all linked to nuclear knowledge management. It is shown that, in Community research, production of knowledge remains the most important objective, be it to generate products or services. However, dissemination/transfer (e.g. education and training) and exploitation (e.g. innovation) of knowledge become equally important as

  3. Primi dati radiotelemetrici sul comportamento di dispersione della Volpe (<em>Vulpes vulpesem> in un'area costiera del Friuli-Venezia Giulia

    Directory of Open Access Journals (Sweden)

    F. Roppa

    2003-10-01

    Full Text Available Nel 2001 e 2002 in provincia di Gorizia (loc. Isola della Cona, Riserva Naturale Regionale Foce dell?Isonzo due giovani maschi di volpe sono stati marcati con radiocollari, al fine di raccogliere dati sulla loro dispersione. L?area di studio, di circa 20 km², presenta zone boscose, boscaglie golenali, prati umidi, canneti e barene, inserite, comunque, in un territorio soggetto ad agricoltura intensiva. Gli animali sono stati seguiti per 12 ore/notte nella prima fase e successivamente per 12 ore/settimana, suddivise in 3 turni tali da coprire l?intero arco della notte. La posizione è stata rilevata ogni 20 min. Il primo individuo (M1 è stato seguito dal 15.11.01 al 10.12.01 per 140 ore; il secondo (M2 dal 14.06.02 al 22.03.03 per 580 ore; la dispersione è iniziata il 17.11.01 per M1 e il 10.11.02 per M2. Entrambi hanno attraversato il fiume Isonzo, in un tratto ampio 145 m, in direzione Sud/Est, raggiungendo una zona agricola. In seguito non hanno mostrato la tendenza a tornare indietro, probabilmente a causa della presenza di un maschio territoriale. Durante il giorno non si sono verificati spostamenti apprezzabili. La massima area coperta per notte (metodo del Minimo Poligono Convesso è stata di 10,7 km² per M1 (settima notte e di 5,1 km² per M2 (diciassettesima notte. I punti più distanti raggiunti in linea d?aria rispetto a quello di attraversamento del fiume sono stati di 9,2 km per M1 e di 9,9 km per M2. La direzione e alcune delle traiettorie percorse sono risultate sovrapponibili per i due individui. Le convergenze di eventi che emergono dai risultati, raccolti a distanza di un anno, suggeriscono una certa obbligatorietà nei percorsi che potrebbe essere dovuta sia alla struttura territoriale che alla densità della popolazione di volpi (stimata tramite conteggio delle tane attive in 10-12 individui in periodo primaverile e in 27-30 individui in periodo autunnale. Si ipotizza una certa stabilità dei territori degli individui

  4. Development of a tornado wind speed hazard model for limited area (TOWLA) for nuclear power plants at a coastline

    International Nuclear Information System (INIS)

    Hirakuchi, Hiromaru; Nohara, Daisuke; Sugimoto, Soichiro; Eguchi, Yuzuru; Hattori, Yasuo

    2016-01-01

    It is necessary for Japanese electric power companies to assess tornado risks on the nuclear power plants according to a new regulation in 2013. The new regulatory guide recommends to select a long narrow strip area along a coast line with the width of 5 km to the seaward and landward sides as a target area of tornado risk assessment, because most of Japanese tornados have been reported near the coast line, where all of Japanese nuclear power plants are located. However, it is very difficult to evaluate a tornado hazard along a coast line, because there is no available information of F-scale and damage length/width on tornadic waterspouts. The purpose of this study is to propose a new tornado wind hazard model for limited area (TOWLA), which can be apply to a long narrow strip area along a coastline. In order to consider tornadic waterspouts moved inland, we evaluate the number of waterspouts entering/passing the targeting area, and add them to the total number of the tornado occurred in the area. A characteristic of the model is to use 'segment lengths' instead of damage lengths. The segment length is a part of the tornado foot print in the long narrow strip area. We show two methods for segment length computation. One is based on tornado records; latitude and longitude of tornado genesis and dissipation locations. The other is to compute the expected segment length based on the geometrical relationship among the damage length, area width, and directional characteristics of tornado movement. The new model can also consider the variation of tornado intensity along the path length and across the path width. (author)

  5. Effects of a power shortage in the Tokyo metropolitan area on awareness of nuclear power generation and power savings behavior

    International Nuclear Information System (INIS)

    Kitada, Atsuko

    2004-01-01

    The shutdown of a number of nuclear power stations of the Tokyo Electric Power Company in the summer of 2003 caused a power shortage problem in the Tokyo Metropolitan area. To examine the effects of the power shortage, in September 2003 a survey was conducted in the service areas of the Kansai Electric Power Company (Kansai region) and the Tokyo Electric Power Company (Kanto region). This survey was part of a wider opinion survey begun in 1993 concerning nuclear power generation. The results of the September 2003 survey are as follows: The degree of recognition of the power shortage problem in the Metropolitan area was high, with 40% of respondents in the Kansai region and nearly 70% in the Kanto region understanding that the shortage was caused by the shutdown of several nuclear power station. The overall awareness of nuclear power generation was little affected in both the Kansai and Kanto regions, though the sense of a shortage of the generating capacity had been raised slightly. Once respondents knew about the power shortage problem, they estimated the likelihood of an occurrence of large-scale service interruption to be low, nearly at an even chance, and they had been only slightly worried about it, essentially viewing the problem optimistically. In the Kanto region, where public relations activities for power savings had been actively pursued, the frequency of experiencing exposure to such public relations activities was remarkably higher than in the Kansai region. The relation between exposure to public relations activities for power savings and power savings behavior was analyzed using quantification method II. Analysis results suggest that public relations activities for power savings in the Kanto region had the effect of urging power savings behavior. However, the difference in the rate of putting power savings behavior into practice was small between the Kanto and Kansai regions, indicating that public relation activities for power savings in the Kanto

  6. Projected Eastern Slovakia nuclear power plant and its effect on the area settlement structure

    International Nuclear Information System (INIS)

    Uvirova, E.

    1986-01-01

    The current situation of and expected changes in the settlement of the Kecerovce locality, where the Eastern Slovakia nuclear power plant will be sited, are discussed. The estimated requisition of agricultural soil and of forests is considered and the questions are outlined of the resettlement of the population in the power plant protective zone. (M.D.). 6 tabs., 4 refs

  7. Application of nuclear-physical methods for studies in the solid state physics area

    International Nuclear Information System (INIS)

    Gorlachrv, I.D.; Knyazev, B.B.; Platov, A.B.

    2004-01-01

    The set of nuclear-physical methods developed on the heavy ion accelerator at the Institute of Nuclear Physics of the National Nuclear Center of the Republic of Kazakhstan allows to conduct an examination of elementary content as well as to obtain the elements distribution in a sample in their depth and surface. This information could be very important for study of samples wide range integral parameters and the characteristics of sputtered layers and implanted films. The beam analysis methods, as well as Rutherford backscattering methods (RBS), nuclear reaction analysis (NRA), proton-induced X-ray emission analysis (PIXE) are included in the complex structure. Besides for expand an analyzed elements range and precision increase for quantitative characteristics of elementarily content of samples the X-ray florescent analysis method with isotope excitation (RFA) is using in the capacity complementary PIXE method. Modernization of proton beam transportation system at the heavy ion accelerator allows to develop a new analytical trend - combination of the proton micro-probe with PIXE analysis. In this case the information about examined sample elementary content is within size field ∼10 μm. The beam scanning by the surface is allowing to obtain the elements distribution by the two spatial coordinates connected with the surface. This information may be useful in the case of an existence of a micro-inclusions in the sample

  8. Computed tomography, nuclear medicine, ultrasound. Advanced diagnostic imaging for problematic areas in paediatric otolaryngology

    International Nuclear Information System (INIS)

    Noyek, A.M.; Friedberg, J.; Fitz, C.R.; Greyson, N.D.; Gilday, D.; Ash, J.; Miskin, M.; Rothberg, R.

    1982-01-01

    This presentation considers the diagnostic role of three major advanced imaging modalities in paediatric otolaryngology: computed tomography, nuclear medicine and ultrasound. These techniques allow for both more specific diagnosis, and for more precise understanding of the natural history of diagnoses already rendered. (Auth.)

  9. Liabilities for the decommissioning and disposal in the nuclear area. Analysis and concept of reformation

    International Nuclear Information System (INIS)

    Meyer, Bettina

    2012-01-01

    The contribution under consideration examines the adequacy of the reserves for decommissioning / dismantling and disposal in order to finance long-term tasks. A reform concept is presented. The two key components of the reformation are the establishment of a public fund for the long-term obligations and a stronger insolvency protection of medium-term nuclear liabilities.

  10. Management of a science and technology popularization project in the nuclear area

    International Nuclear Information System (INIS)

    Soares, Wellington Antonio; Maretti Junior, Fausto

    2007-01-01

    The goal of this paper is to show the management results of the 2005-2007 project 'Nuclear energy: itinerant expositions' sponsored by the Foundation for Research Support of Minas Gerais (FAPEMIG), a state agency, in a science and technology popularization program. The project coordinated by the Nuclear Technology Development Center (CDTN/CNEN) in partnership with the Minas Commerce Association (ACMinas) was designed to students from public high school of the Belo Horizonte metropolitan region. It consisted of an exposition and a previous talk motivating the audience to the nuclear technology in connection with subjects taught at schools, like physics, chemistry, biology, mathematics, history, etc. Small scale models of nuclear and radioactive installations, irradiated food and fruits samples and colored gems by gamma rays were presented at the stand exposition. Designing, performing and evaluating the project required the following activities: searching of information on the target public, infrastructure mounting, team training, multimedia material elaboration, strategy for dealing with the students, talk presentation, distribution of booklet on nuclear themes, reception at the exposition, interviews with students and teachers by journalists, evaluation of the project by the schools, evaluation of the project by some students three months after the event and also reporting the project to the media. About forty people of CDTN took part in the project that reached thirty high schools and encompassed about 11,000 students. About five hundred state high school teachers of chemistry, physics and biology were reached by the experience of the project in a specialization course given by a local university. Only high approval was received by the project in the returned questionnaires. (author)

  11. Management of a science and technology popularization project in the nuclear area

    Energy Technology Data Exchange (ETDEWEB)

    Soares, Wellington Antonio; Maretti Junior, Fausto [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)]. E-mail: soaresw@cdtn.br; fmj@cdtn.br

    2007-07-01

    The goal of this paper is to show the management results of the 2005-2007 project 'Nuclear energy: itinerant expositions' sponsored by the Foundation for Research Support of Minas Gerais (FAPEMIG), a state agency, in a science and technology popularization program. The project coordinated by the Nuclear Technology Development Center (CDTN/CNEN) in partnership with the Minas Commerce Association (ACMinas) was designed to students from public high school of the Belo Horizonte metropolitan region. It consisted of an exposition and a previous talk motivating the audience to the nuclear technology in connection with subjects taught at schools, like physics, chemistry, biology, mathematics, history, etc. Small scale models of nuclear and radioactive installations, irradiated food and fruits samples and colored gems by gamma rays were presented at the stand exposition. Designing, performing and evaluating the project required the following activities: searching of information on the target public, infrastructure mounting, team training, multimedia material elaboration, strategy for dealing with the students, talk presentation, distribution of booklet on nuclear themes, reception at the exposition, interviews with students and teachers by journalists, evaluation of the project by the schools, evaluation of the project by some students three months after the event and also reporting the project to the media. About forty people of CDTN took part in the project that reached thirty high schools and encompassed about 11,000 students. About five hundred state high school teachers of chemistry, physics and biology were reached by the experience of the project in a specialization course given by a local university. Only high approval was received by the project in the returned questionnaires. (author)

  12. Planejamento ambiental de áreas verdes: estudo de caso em Campinas–SP. Environmental planning of urban green areas: case study Campinas–SP.

    Directory of Open Access Journals (Sweden)

    Elaine Cristina Cardoso FIDALGO

    2007-06-01

    Full Text Available Este trabalho teve como objetivo selecionare estruturar indicadores de acordo com metasdefinidas para um planejamento das áreas verdes edesenvolver uma proposta metodológica para umordenamento territorial, por meio de análise espacial.Os indicadores foram selecionados de forma aidentificar áreas verdes no distrito sede do municípiode Campinas, SP, Brasil, que garantissem a proposiçãode alternativas de conservação da biodiversidade, odesenvolvimento de programas de educação ambientale a possibilidade de recreação. Os indicadores foramponderados, espacializados e integrados, resultando,em uma primeira etapa, em dois mapas de síntese:o primeiro, indicando as áreas prioritárias para aimplantação de áreas verdes de acordo com oselementos antrópicos; e o segundo, as áreas prioritáriasde acordo com os elementos naturais. A integração dosdois mapas gerados resultou no mapa de áreas prioritáriasà implantação de áreas verdes. A espacialização dosindicadores permitiu identificar a distribuição desigualde áreas verdes para a população, uma vez que seconcentram nos locais onde está a população de maiorrenda. A estratégica metodológica adotada permitiu a identificação e hierarquização das áreas prioritárias à implantação de áreas verdes no município.This work aims to select and to organizeindicators according to the defined goals for theurban green areas planning, and to develop amethodological proposal to territorial ordering,using spatial analysis. It was developed inCampinas city (urban district, São Paulo state,Brazil. The indicators were selected according tothe information needed to identify urban greenareas to biodiversity conservation, environmentaleducation programs, and recreation. The indicatorswere weighted, spacialized and integrated. In afirst stage, it resulted in two synthesis maps, thefirst showing the priority areas to establish urbangreen areas according to the human elements, andthe

  13. Scelta dell'habitat del tasso (<em>Meles melesem> in un'area dell'Oltrepò pavese

    Directory of Open Access Journals (Sweden)

    Valentina Rigo

    2003-10-01

    Full Text Available Il presente studio è parte di una ricerca promossa dal Centro Studi Faunistica dei Vertebrati della SISN. Il progetto è iniziato nel 1999 ed è ancora in corso. L'area di studio (161 Km² si trova nella zona collinare dell'Oltrepò ed è compresa, sul reticolato cartografico UTM, tra i Km 4972 e 4960 Nord, e i Km 1505 e 1520 Est. Lo scopo principale della ricerca era di valutare l'importanza delle caratteristiche ambientali nella scelta e selezione dell'habitat del tasso, relativamente al posizionamento delle tane. Nel periodo di studio sono stati rilevati i dati ambientali su 23 punti tana (pt e 28 punti casuali (pc, successivamente inseriti in un GIS dal quale, attraverso l'analisi di carte tematiche digitalizzate, sono state ricavate diverse altre informazioni (uso del suolo, geologia, litologia, sviluppo dei corsi d'acqua, delle strade e dei centri abitati considerando aree di raggio 300 e 600 m intorno ai pt e pc. I dati raccolti sono stati oggetto d'analisi statistiche con test di confronto fra pt e pc, indice di selezione di Manly e tecniche classificatorie multivariate (regressione logistica. Le tane di tasso sono prevalentemente scavate in luoghi protetti, caratterizzati da un'elevata copertura. La differenza tra gli ambienti nei quali sono situate le tane e quelli relativi ai punti casuali si è rivelata estremamente significativa (Χ²=18.20; d.f.=1; p<0.001. L'indice di Manly indica una forte selezione per i boschi di latifoglie, quasi tutte le tane, infatti, si trovano in ambienti boschivi caratterizzati da una elevata copertura sia delle fronde degli alberi (Χ²=8.02; d.f.=2; p=0.018 che degli arbusti (Χ²=10.85; d.f.=2; p=0.004; sono invece evitati ambienti caratterizzati da un elevato sviluppo delle attività antropiche e che presentino una copertura minima o del tutto assente come campi coltivati, frutteti, zone a prato, ecc. Preferiti sono risultati i versanti esposti a sud rispetto alle altre esposizioni (Χ²=11.566; d

  14. Evaluation of maximum absorbed dose for accompanying patients in nuclear medicine establishments; Avaliacao da dose maxima absorvida por acompanhantes de pacientes em servicos de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Cabral, Geovanna; Amaral, Ademir; Hazin, Clivis A. [Pernambuco Univ., Recife, PE (Brazil). Dept. de Energia Nuclear; Lima, Ricardo A.; Nogueira, Maria S. [Centro Regional de Ciencias Nucleares (CRCN), Recife, PE (Brazil); Lopes, Ferdinand [Centro de Medicina Nuclear de Pernambuco (CEMUPE), Recife, PE (Brazil); Guimaraes, Maria Ines C.C. [Sao Paulo Univ., SP (Brazil). Centro de Medicina Nuclear

    2001-07-01

    In nuclear medicine, radioisotopes are bound to various pharmaceuticals for use in diagnostic and therapeutic applications. These unsealed sources are administered in various forms to patients, who remain radioactive for hours or days, and represent a source of potential radiation exposure for others. Thus, in nuclear medicine departments, radiation protection of workers and members of the public (especially persons accompanying patients) must consider this exposure. In this study, thermoluminescent dosimeters were given to various persons who were accompanying patients in two nuclear medicine departments in Recife, Pernambuco State, Brazil. Exposure results are given, and issues regarding exposure conditions and times for members of the public in these departments are discussed. (author)

  15. Preliminary geological study in kabupaten Pamekasan area to support the selection of candidate site of nuclear desalination plant

    International Nuclear Information System (INIS)

    Ngadenin; Lilik Subiantoro; Kurnia Setiawan Widana

    2014-01-01

    The area around the southern coast Pamekasan is one of the candidates for the alternatives location of nuclear desalination plant site. In 1949 around Sampang Madura ever tectonic earthquake measuring 5 on the Richter scale with its epicenter on land. Tectonic earthquake with epicenter on land is likely related to the presence of active faults on the Madura island. Location prospective nuclear desalination plant site should be away or free of active faults. The study aimed to obtain geological information and find out the characteristics of tectonics including active fault to support site studies of nuclear desalination plant on the island of Madura. The method used is the geological mapping scale, 1 : 50,000. Lithology in the area along the south coast district Pamekasan is alluvium Holocene age and conglomerate units of Pleistocene age. There were no indications of active faults in the region. Candidates site at this location is less attractive in terms of geotechnical foundation as can be ascertained bedrock will be found sufficient in that building construction will require expensive. (author)

  16. Airborne and truck-borne ``radiation footprints`` of areas producing, storing, using or being exposed to nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Pavlik, B; Bottos, F [Picodas Group Inc., Richmond Hill, ON (Canada); Cuneen, P J [World Geoscience Corp. Ltd., Perth (Australia); Jurza, P; Hoeschl, V [Picodas Prague s.r.o., Prague (Czech Republic)

    1997-11-01

    The paper discusses the use of advanced Airborne Gamma Ray Spectrometer for environmental assessment of nuclear radiation in areas exposed to radioactive materials. The use of high capacity real time processors operating in parallel mode packaged into one mechanical enclosure together with navigation, allows implementation of highly sophisticated proprietary algorithms to produce results in absolute physical units. Airborne footprinting provides rapid, well defined spatial images of natural and manmade radioactive contamination. Integrated GPS guidance systems provides instant position information related to the internal geographical data base. Short time span of data acquisition provides consistent data. Airborne acquisition of data guarantees good spatial resolution. Airborne measurements are calculated via special algorithms in absolute units and related to the individual radioactive nuclei on the ground in real time. Full raw and calculated data recording is provided including the position coordinates. More precise results may be achieved via post flight processing. Principles of ground contamination estimates measured from the air and the sensitivities for different radioactive nuclei are also discussed. Results from an Ontario Hydro (Canada) test over a nuclear power plant, an Atom bomb blast measurements in Maralinga (Australia), after 40 years, and a Nuclear power plant in Slovakia and Uranium mining area in Germany are presented and discussed. (author). 6 refs, 1 fig.

  17. Airborne and truck-borne ''radiation footprints'' of areas producing, storing, using or being exposed to nuclear materials

    International Nuclear Information System (INIS)

    Pavlik, B.; Bottos, F.; Cuneen, P.J.; Jurza, P.; Hoeschl, V.

    1997-01-01

    The paper discusses the use of advanced Airborne Gamma Ray Spectrometer for environmental assessment of nuclear radiation in areas exposed to radioactive materials. The use of high capacity real time processors operating in parallel mode packaged into one mechanical enclosure together with navigation, allows implementation of highly sophisticated proprietary algorithms to produce results in absolute physical units. Airborne footprinting provides rapid, well defined spatial images of natural and manmade radioactive contamination. Integrated GPS guidance systems provides instant position information related to the internal geographical data base. Short time span of data acquisition provides consistent data. Airborne acquisition of data guarantees good spatial resolution. Airborne measurements are calculated via special algorithms in absolute units and related to the individual radioactive nuclei on the ground in real time. Full raw and calculated data recording is provided including the position coordinates. More precise results may be achieved via post flight processing. Principles of ground contamination estimates measured from the air and the sensitivities for different radioactive nuclei are also discussed. Results from an Ontario Hydro (Canada) test over a nuclear power plant, an Atom bomb blast measurements in Maralinga (Australia), after 40 years, and a Nuclear power plant in Slovakia and Uranium mining area in Germany are presented and discussed. (author)

  18. Atmospheric Dispersion Modeling of 137Cs generated from Nuclear Spent Fuel under Hypothetic Accidental Condition in the BNPP Area

    Science.gov (United States)

    Lee, Jongkuk; Lee, Kwan-Hee; Yook, Daesik; Kim, Sung Il; Lee, Byung Soo

    2016-04-01

    This study presents the results of atmosphere dispersion modeling using CALPUFF code that are based on computational simulation to evaluate the environmental characteristics of the Barakah nuclear power plant (BNPP) in west area of UAE. According to meteorological data analysis (2012~2013), the winds from the north(7.68%) and west(9.05%) including NNW(41.63%), NW(28.55%), and WNW(6.31%) winds accounted for more than 90% of the wind directions. East(0.2%) and south(0.6%) direction wind, including ESE(0.31%), SE(0.38%), and SSE(0.38%) were rarely distributed during the simulation period. Seasonal effects were not showed. However, a discrepancy in the tendency between daytime and night-time was observed. Approximately 87% of the wind speed was distributed below 5.4m/s (17%, 47% and 23% between the speeds of 0.5-1.8m/s 1.8-3.3m/s and 3.3-5.4m/s, respectively) during the annual period. Seasonal wind speed distribution results presented very similar pattern of annual distribution. Wind speed distribution of day and night, on the other hand, had a discrepancy with annual modeling results than seasonal distribution in some sections. The results for high wind speed (more than 10.8m/s) showed that this wind blew from the west. This high wind speed is known locally as the 'Shamal', which occurs rarely, lasting one or two days with the strongest winds experienced in association with gust fronts and thunderstorms. Six variations of cesium-137 (137Cs) dispersion test were simulated under hypothetic severe accidental condition. The 137Cs dispersion was strongly influenced by the direction and speed of the main wind. From the test cases, east-south area of the BNPP site was mainly influenced by 137Cs dispersion. A virtual receptor was set and calculated for observation of the 137Cs movement and accumulation. Surface roughness tests were performed for the analysis of topographic conditions. According to the surface condition, there are various surface roughness length. Four types

  19. Estimation of radiation exposed area by the nuclear accident occurred at Tokai village using ESR measurements of household sugar

    International Nuclear Information System (INIS)

    Kuzuya, Masayuki; Kondo, Shinichi; Ito, Kousuke; Sawa, Takashi

    2001-01-01

    The area of radiation exposure by the nuclear accident occurred at Tokai village in 1999 was estimated by the ESR measurement of 95 household sugar samples collected from the accident area. These samples were roughly classified into three types of sugar, fine white sugar, fine brown sugar and coarse brown sugar. The control fine white sugar showed no radical in the ESR spectrum, while those of fine brown sugar and coarse brown sugar showed the presence of a small amount of radicals. It was also shown that, among these three kinds of sugar, the radical concentration of fine white sugar sampled from wooden houses at the area similar to each other did not vary much with the samples, while those of fine brown sugar and coarse brown sugar varied to a considerable extent. Thus, the fine white sugar is considered to be more suitable for the estimation of the level of radiation exposure. The radical concentration of each fine white sugar sample was plotted against the distance from the site of the nuclear accident with a correction of the difference in the shielding effect between concrete houses and wooden houses. The samples obtained at more than 2 km north of the site of nuclear accident showed no ESR spectral signal to a detectable extent. On the other hand, the ESR spectra were observed from the samples obtained within 10 km south and 4 km west of the accident site. These results suggest that the radiation exposure by the contaminant blown by the northeast wind blowing on the day of the accident may occur at the south and west areas. (author)

  20. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

    This document proposes a presentation and discussion of the main notions, issues, principles, or characteristics related to nuclear energy: radioactivity (presence in the environment, explanation, measurement, periods and activities, low doses, applications), fuel cycle (front end, mining and ore concentration, refining and conversion, fuel fabrication, in the reactor, back end with reprocessing and recycling, transport), the future of the thorium-based fuel cycle (motivations, benefits and drawbacks), nuclear reactors (principles of fission reactors, reactor types, PWR reactors, BWR, heavy-water reactor, high temperature reactor of HTR, future reactors), nuclear wastes (classification, packaging and storage, legal aspects, vitrification, choice of a deep storage option, quantities and costs, foreign practices), radioactive releases of nuclear installations (main released radio-elements, radioactive releases by nuclear reactors and by La Hague plant, gaseous and liquid effluents, impact of releases, regulation), the OSPAR Convention, management and safety of nuclear activities (from control to quality insurance, to quality management and to sustainable development), national safety bodies (mission, means, organisation and activities of ASN, IRSN, HCTISN), international bodies, nuclear and medicine (applications of radioactivity, medical imagery, radiotherapy, doses in nuclear medicine, implementation, the accident in Epinal), nuclear and R and D (past R and D programmes and expenses, main actors in France and present funding, main R and D axis, international cooperation)

  1. Proposal for the decision making in sensitive technology: application to the nuclear area

    International Nuclear Information System (INIS)

    Silva, Eduardo Ramos Ferreira da

    2007-01-01

    In a previous article, a correlation is made among the phases of the nuclear technology development and the decision making processes, showing that from the 70's decade, such processes are connected to the national security doctrines, influenced by the Brazilian War College. In this paper it is shown the developed model for the decision making when the sensitive technologies are involved that in our special case will be specific oriented to the nuclear technology. An assessment are made for such decisions must having the the population approval, showing the main existent obstacles and how the present model, although defined at the end of the year 2003, will not be succeeded in a short period of time. It is mainly shown that the linear models must be abandoned, essential since the Word War II, for a holistic model more realistic with a new global state of affairs

  2. Description of recipient areas related to final storage of unreprocessed spent nuclear fuel

    International Nuclear Information System (INIS)

    Sundblad, B.; Bergstroem, U.

    1983-02-01

    A comprehensive study of recipient areas in Fjaellveden, Voxnan, Gideaa and Kamlungekoelen is accomplished. Besides general conditions in Finnsjoen and Sternoe are discussed. The recipient areas are defined and their climate, hydrology, bedrock, soil, vegetation, land use and yield from arable land are described as well as the yield of fish for the surface water of interest. The potential exposure pathways and model system at the different areas are defined. Long-term variations of geology, climate, hydrology, land-use, acidification and evolution are described. The possible development of the recipient areas is also discussed. (Authors)

  3. Diversidade de fungos micorrízicos arbusculares em área de Caatinga, PE, Brasil Diversity of arbuscular mycorrizal fungi in an area of Caatinga, PE, Brazil

    Directory of Open Access Journals (Sweden)

    Catarina Maria Aragão de Mello

    2012-12-01

    Full Text Available O objetivo deste trabalho foi o de determinar a infectividade, a riqueza de FMA e a condição micorrízica da vegetação em área de Caatinga não antropizada. Coleta de solo e raízes foi realizada em Triunfo/PE. Raízes foram examinadas para determinação da colonização micorrízica. O número mais provável (NMP de propágulos infectivos de FMA foi estimado por diluições sucessivas do solo e a utilização de milho (Zea mays L. como planta isca. Glomerosporos foram quantificados e preparados em lâminas, para identificação das espécies. As plantas apresentaram-se pouco colonizadas (média The objective of this work was to determine the infectivity and richness of AMF and the mycorrhizal conditions of the vegetation in a preserved area of Caatinga. Soil and root samples were taken in two subareas in the municipality of Triunfo, PE. The roots were stained with Trypan blue, and observed with a microscope to determine if colonization of mycorrhizal fungi was present. Glomerospores were extracted from soil, counted, mounted on microscope slides and the AMF species were identified. The plants from the area showed < 10% colonization. The number of glomerospores (<1 g-1 soil did not differ between the subareas although in one area the amount of P in the soil was three times higher than in the other. The number of AMF propagules varied from 64 to 70 cm-3 in the soil. Sixteen taxa of AMF were registered and Glomus was the most representative genus, with seven species. Pacispora boliviana is reported for the first time in Brazil. The high amount of P probably contributes to the low values of propagules, colonization, infectivity and richness of AMF in the area. AMF have been commonly found in the Brazilian semiarid region and species of Glomus are predominant in this environment.

  4. IAEA activities in the area of nuclear power reactor fuel engineering

    International Nuclear Information System (INIS)

    Inozemtsev, V.

    2013-01-01

    IAEA Programme on Nuclear Fuel Cycle and Materials for 2013-2015 A review of Coordinated Research Projects in 2005-2015 as well as FUMEX project as a part of the fuel modelling IAEA programme is given. SMoRE (Accelerator Simulation and Theoretical Modelling of Radiation Effects) objectives: enhancement of simulation capabilities of accelerators for materials testing; contribution for better physical understanding of high-dose radiation effects are presented

  5. Application of diagnosis and monitoring area contaminated by petroleum derivatives; Aplicacao da tecnica de caminhamento eletrico em area contaminada por derivados de petroleo

    Energy Technology Data Exchange (ETDEWEB)

    Moreira, Cesar Augusto [Pos-graduacao em Geociencias em Meio Ambiente, IGCE - UNESP, Rio Claro, SP (Brazil)], E-mail: cesargeologia@yahoo.com.br; Dourado, Joao Carlos; Braga, Antonio Celso de Oliveira [Dept. de Geologia Aplicada, IGCE - UNESP, Rio Claro, SP (Brazil)], E-mails: jdourado@rc.unesp.br, acobraga@rc.unesp.br

    2006-07-15

    Geophysical methods are useful technic of geological investigation, thoroughly employed to diagnosis and monitoring contaminated areas, in conjunction with direct techniques of investigation such as chemical analyses. Among these, electric resistivity is more usually used in studies of contaminants in soil and groundwater, due to the high contrast of electric properties between the soil and the pollutant types frequently found, essentially constituted of composed organic and inorganic. Geophysical studies in impacted areas by petroleum products may be describe by anomalies of both low resistivity and high resistivities, confirmed as contaminant by chemical analyses. This apparent contradiction can reflect processes of degradation of the contaminants, directly associated with its residence time in the soil, through the generation of by-products that change the physical properties of the soil and groundwater, principally for the mineral dissolution by action of organic acids and by formation of minerals of oxides and hydroxides minerals. Natural attenuation defines a series of physical, chemical and biological processes that allow the degradation, dispersion and dilution of contaminants in a natural form, in other words, free from human intervention. This paper presents the application of electrical profiling technique in a contaminated industrial area for benzene, toluene, xylene, 1,2 dichloroethene and inorganic salts and it discusses the physical alterations of the contaminated soil through the obtained results, under the optics of the Natural Attenuation in course in the area of study. (author)

  6. Identification of uranium signatures in swipe samples on verification of nuclear activities for nuclear safeguards purposes; Identificacao de assinaturas de uranio em amostras de esfregacos (swipe samples) para verificacao de atividades nucleares para fins de salvaguardas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Pestana, Rafael Cardoso Baptistini

    2013-07-01

    The use of environmental sampling for safeguards purposes, has been applied by the International Atomic Energy Agency–IAEA since 1996 and are routinely used as a complementary measure to strengthen the traditional nuclear safeguards procedures. The aim is verify if the states signatory to the safeguards agreements are not diverging their peaceful nuclear activities for undeclared nuclear activities. This work describes a new protocol of collect and analysis of the swipe samples for identification of nuclear signatures that may be related to the nuclear activities developed in the inspected facility. This work was used as a case of study a real uranium conversion plant of the nuclear fuel cycle of IPEN. The strategy proposed uses different analytical techniques, such as alpha radiation meter, SEM-EDX and ICP-MS to identify signatures of uranium adhered to the swipe samples. In the swipe samples analysis, it was possible to identify particles of UO{sub 2}F{sub 2} and UF4 through the morphological comparison and semi-quantitative analyses performed by SEM-EDX technique. In this work, methods were used that as a result has the average isotopic composition of the sample, in which the enrichment ranged from 1.453 ± 0.023 to 18.24 % ± 0.15 % in the {sup 235}U isotope. Through these externally collections, a non-intrusive sampling, it was possible to identify enriched material handling activities with enrichment of 1.453 % ± 0.023 % to 6.331 ± 0.055 % in the isotope {sup 235}U, as well as the use of reprocessed material, through the identification of the {sup 236}U isotope. The uncertainties obtained for the n({sup 235}U)/n({sup 238}U) ratio varied from 0.40% to 0.86 % for the internal swipe samples. (author)

  7. Nuclear emergency planning and response in industrial areas. Results of a qualitative study in 9 industrial companies

    International Nuclear Information System (INIS)

    Pauwels, N.; Hardeman, F.; Soudan, K.

    1998-11-01

    Substantial economic losses and potential dangerous situations may result when industrial companies unexpectedly have to shut down their activities in an abrupt way. With respect to the industrial companies located in the Antwerp harbour region, the reason for such an unplanned shut-down could be the decision to (preventively) evacuate their workers, or to have them sheltered, in case of an alarm situation at a nearby nuclear power plant of Doel or in any other adjacent industrial factory. Between January and August 1998, the prevention advisors of nine industrial companies have been interviewed to gain insight in the scale and relative importance of several economic costs and practical difficulties that may arise. Moreover, the appropriateness of the existing nuclear emergency response decision structure and intervention philosophy was investigated. The main conclusions drawn from the interviews are reported. Recommendations are made to increase the efficiency of implementing countermeasures in industrial areas

  8. Nuclear emergency planning and response in industrial areas. Results of a qualitative study in 9 industrial companies

    Energy Technology Data Exchange (ETDEWEB)

    Pauwels, N.; Hardeman, F.; Soudan, K

    1998-11-01

    Substantial economic losses and potential dangerous situations may result when industrial companies unexpectedly have to shut down their activities in an abrupt way. With respect to the industrial companies located in the Antwerp harbour region, the reason for such an unplanned shut-down could be the decision to (preventively) evacuate their workers, or to have them sheltered, in case of an alarm situation at a nearby nuclear power plant of Doel or in any other adjacent industrial factory. Between January and August 1998, the prevention advisors of nine industrial companies have been interviewed to gain insight in the scale and relative importance of several economic costs and practical difficulties that may arise. Moreover, the appropriateness of the existing nuclear emergency response decision structure and intervention philosophy was investigated. The main conclusions drawn from the interviews are reported. Recommendations are made to increase the efficiency of implementing countermeasures in industrial areas.

  9. The internationalization of nuclear industry: state and capital in atomic relations; A internacionalizacao da industria nuclear: estado e capital em relacoes atomicas

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira Junior, Evaristo Santiago

    1986-03-15

    This paper analyzes the causes and scope of the nuclear energy diffusion process in the capitalist world. It also aims at explaining Brazil's role in this process. The study contemplates two main concepts that are, here, considered to be driving and directing vectors: the World Capital and the Capitalist State. According to the expanded reproduction logic, World Capital forms the world nuclear productive subsystem, which commands and directs, in this process, hundreds (or thousands) of productive units, regardless of their geographical location, nationality or capital control. Thru the utilization of available public intervention tools, the Capitalist state has favored the formation of the world nuclear productive subsystem, thus guiding the accumulation process in the interior of this system. Therefore, the conclusion of the Nuclear Cooperation Agreement between Brazil and Germany and the resultant establishment of the Brazilian Nuclear Program (following the authoritarian model of public administration), is well fitted in the general dynamics of subordination/articulation of the Brazilian economy to the world economy and, particularly, to the world nuclear productive subsystem. (author)

  10. The internationalization of nuclear industry: state and capital in atomic relations; A internacionalizacao da industria nuclear: estado e capital em relacoes atomicas

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Junior, Evaristo Santiago

    1986-03-15

    This paper analyzes the causes and scope of the nuclear energy diffusion process in the capitalist world. It also aims at explaining Brazil's role in this process. The study contemplates two main concepts that are, here, considered to be driving and directing vectors: the World Capital and the Capitalist State. According to the expanded reproduction logic, World Capital forms the world nuclear productive subsystem, which commands and directs, in this process, hundreds (or thousands) of productive units, regardless of their geographical location, nationality or capital control. Thru the utilization of available public intervention tools, the Capitalist state has favored the formation of the world nuclear productive subsystem, thus guiding the accumulation process in the interior of this system. Therefore, the conclusion of the Nuclear Cooperation Agreement between Brazil and Germany and the resultant establishment of the Brazilian Nuclear Program (following the authoritarian model of public administration), is well fitted in the general dynamics of subordination/articulation of the Brazilian economy to the world economy and, particularly, to the world nuclear productive subsystem. (author)

  11. Proposta de método de inspeção de radioproteção aplicada em instalações de medicina nuclear

    Directory of Open Access Journals (Sweden)

    Mendes Leopoldino da Cruz Gouveia

    2004-01-01

    Full Text Available O objetivo principal deste trabalho é implantar um método de inspeção imparcial e eficiente, visando à utilização segura e correta das radiações ionizantes no campo da medicina nuclear. Este método de inspeção aqui proposto foi aplicado em 113 serviços de medicina nuclear do país, obedecendo a uma freqüência de análise bienal (1996, 1998, 2000 e 2002. Foram estabelecidos 82 itens de radioprote��ão com pesos para cada item, baseados nos fatores de risco, de acordo com as normas da Comissão Nacional de Energia Nuclear (CNEN e as recomendações da Agência Internacional de Energia Atômica. Na análise do serviço, cada item de não conformidade com as normas da CNEN gerou uma irregularidade de radioproteção, com seu peso associado. O somatório dos pesos deu a cada serviço uma pontuação final que o classificou dentro de três faixas de valores que determinaram uma tomada de decisão por parte do órgão regulador e fiscalizador: funcionamento sem restrição - menor que 100 pontos; funcionamento com restrição - igual ou maior que 100 e menor que 300 pontos; funcionamento suspenso - igual ou maior que 300 pontos. Para o caso de irregularidades reincidentes, criou-se um fator multiplicativo para a pontuação. A reincidência em qualquer item de radioproteção (irregularidade teve seu peso multiplicado por 2n, onde n era o número de vezes em que o item encontrava-se irregular. O estabelecimento prévio de itens de radioproteção, com atribuição de pesos para cada item, procurou minimizar os valores subjetivos e pessoais presentes no julgamento e na avaliação técnica das instituições inspecionadas.

  12. Environmental management of works in pipelines at natural protected areas; Gestao ambiental em obras de faixas de dutos nas areas naturais protegidas

    Energy Technology Data Exchange (ETDEWEB)

    Raul, Vanderlei Lourenco; Alves, Anibal Jose Constantino; Martini, Andrea Dietrich; Lima, Silvia Ferreira de; Campos, Cleber Lucio dos Santos; Ozorio, Tarcisio Faria; Melo Neto, Joao Evangelista de [PETROBRAS Transporte S. A. (TRANSPETRO), Rio de Janeiro, RJ (Brazil)

    2008-07-01

    The TRANSPETRO pipeway in the State of Sao Paulo crosses different scenarios, including Permanent Preservation Areas and Conservation Units, as the Parque Estadual da Serra do Mar - PESM, which contains the most extensive Mata Atlantica fragment, with more than 315,000 hectares. The rigor of environmental organisms imposes a number of extra conditions to critical points to be considered in activities with interference in the conservation unit. It was studied the case of thirty two kilometer pipeline substitution of OSBAT pipeway, in the Sao Sebastiao city, in the area covered by the PESM, to know the effective of environmental controls adopted. It was able to analyze the results about the application of management instruments at different levels, including independent external audit, audit of the Company that realized the work activities and audit of the own specialized people of TRANSPETRO and PETROBRAS. (author)

  13. Innovation and knowledge generation in cooperation nets: challenges for regulations in the nuclear safety area in Brazil; Inovacao e geracao de conhecimento nas redes de cooperacao: desafios para a regulacao na area de seguranca nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Staude, Fabio

    2014-07-01

    The importance of inter-organisational cooperation within the innovation process has been increasingly recognized. In fact, all organisations, at some point, need to look to external sources for inputs to the process of building up technological competence. In this sense, through a detailed case study, this thesis examine theoretical and empirically how collaborative initiatives have supported the Brazilian nuclear regulatory body in the development and implementation of innovations, in order to verify the positive relationship between the collaboration and the organisational innovation performance. Emphasizing the importance of both internal sources of knowledge and external participation, the study encompasses documentary analysis, a preliminary survey and semi-structured interviews with the regulatory body employers in charge of controlling medical and research facilities and activities involving radiation sources. The thesis demonstrates that innovations developed and implemented in the Brazilian nuclear safety and security area are associated with collaborative initiatives, in order to improve the organizational capability to fulfill safety obligations, providing some important implications for regulatory body managers concerned with the management of innovation. The findings also identified actors with a significant degree of influence in the innovation process. The result reveals that the support provided by these actors has a significant influence on the innovation performance of the Brazilian nuclear regulatory body, suggesting that Brazil should adopt more interactive models of innovation and knowledge transfer. In addition, the findings show that these key actors can play a very distinctive role in the context of sectoral systems of innovation information regime. (author)

  14. Actividades enzimáticas antioxidativas em Cistus Ladanifer L. provenientes de áreas não contaminadas em elementos vestigiais Antioxidant enzymes activity of Cistus Ladanifer L. from areas non contaminated in trace elements

    Directory of Open Access Journals (Sweden)

    Erika Santos

    2011-07-01

    Full Text Available Avaliou-se a actividade das enzimas antioxidativas (catalase, peroxidase e superóxido dismutase e as concentrações em As, Cu, Pb e Zn nas folhas de duas populações de Cistus ladanifer L. colhidas, na Primavera e no Verão, em solos não contaminados em elementos vestigiais (Caldeirão e Pomarão e com condições climáticas diferentes. Nos solos das duas áreas, as concentrações totais e disponíveis (extracção com DTPA em elementos vestigiais foram baixas. A distribuição dos elementos pelas folhas novas e maduras foi semelhante entre áreas e estações do ano. As actividades enzimáticas variaram consoante a população. As folhas colhidas nas duas estações do ano, excepto as folhas novas de Verão do Pomarão, apresentaram actividade enzimática na fracção solúvel e iónica. Comparando as estações do ano e áreas de amostragem, constatou-se que as actividades enzimáticas representam um mecanismo de tolerância a vários factores de stresse (radiação UV, temperatura do ar elevada no verão, défice hídrico no verão, baixa-média fertilidade do solo e conteúdo de elementos vestigiais no solo, o que confere uma elevada plasticidade à espécie.The aim of this study was to evaluate the antioxidant enzymes activity (catalase, peroxidase and superoxide dismutase and the concentrations of As, Cu, Pb and Zn in leaves from two populations of Cistus ladanifer growing on soils non-contaminated with trace elements (Caldeirco and Pomarco, but with different climatic conditions and in two different seasons (spring and summer. In both areas, total and available concentrations (DTPA extraction of trace elements in soils were low. The distribution of elements for young and mature leaves was similar between areas and seasons. The enzyme activities varied with the plant population. Leaves collected in the two seasons, except young leaves from Pomarco collected in summer, showed enzymatic activity in the soluble and ionic fractions

  15. Energia nuclear na mídia: Jornalismo científico em portais de notícias nacionais

    Directory of Open Access Journals (Sweden)

    Ricardo Henrique Almeida Dias

    2017-07-01

    Full Text Available This study seeks to examine how the nuclear energy is conveyed by the news media. We used the newsworthiness criteria in journalistic discourse to analyse some science journalism texts on nuclear energy in Brazilian news websites. We selected some news and classified using news values such as conflict, proximity, novelty and relevance. We concluded that nuclear energy is conveyed by the media in a way that the advantages and disadvantages were discussed, and news values were useful to point how all these arguments worked.

  16. Development of a software for predicting the effects of nuclear and radiological terrorism events in city areas

    International Nuclear Information System (INIS)

    Luo Lijuan; Chen Bo; Zhuo Weihai; Lu Shuyu

    2011-01-01

    Objective: To develop a new software system that can directly display the predicted results on an electronic map, in order to get a directly perceived understanding of the affected areas of nuclear and radiological terrorism events in city areas. Methods: Three scenarios of events including spreading radioactive materials, dirty bomb attack, and explosion or arson attacks on the radiation facilities were assumed. Gaussian diffusion model was employed to predict the spread and deposition of radioactive pollutants, and both the internal and external doses were estimated for the representative person by using the corresponding dose conversion factors. Through integration of the computing system and Mapinfo geographic information system (GIS), the predicted results were visually displayed on the electronic maps of a city. Results: The new software system could visually display the predicted results on the electronic map of a city, and the predicted results were consistent with those calculated by the similar software Hotspot®. The deviation between this system and Hotspot was less than 0.2 km for predicted isoplethic curves of dose rate downwind. Conclusions: The newly developed software system is of the practical value in predicting the effects of nuclear and radiological terrorism events in city areas. (authors)

  17. AIRDOS-II computer code for estimating radiation dose to man from airborne radionuclides in areas surrouding nuclear facilities

    International Nuclear Information System (INIS)

    Moore, R.E.

    1977-04-01

    The AIRDOS-II computer code estimates individual and population doses resulting from the simultaneous atmospheric release of as many as 36 radionuclides from a nuclear facility. This report describes the meteorological and environmental models used is the code, their computer implementation, and the applicability of the code to assessments of radiological impact. Atmospheric dispersion and surface deposition of released radionuclides are estimated as a function of direction and distance from a nuclear power plant or fuel-cycle facility, and doses to man through inhalation, air immersion, exposure to contaminated ground, food ingestion, and water immersion are estimated in the surrounding area. Annual doses are estimated for total body, GI tract, bone, thyroid, lungs, muscle, kidneys, liver, spleen, testes, and ovaries. Either the annual population doses (man-rems/year) or the highest annual individual doses in the assessment area (rems/year), whichever are applicable, are summarized in output tables in several ways--by nuclides, modes of exposure, and organs. The location of the highest individual doses for each reference organ estimated for the area is specified in the output data

  18. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1980

    International Nuclear Information System (INIS)

    Smith, D.D.; Grossman, R.F.; Corkern, W.D.; Thome, D.J.; Patzer, R.G.; Hopper, J.L.

    1981-06-01

    The US Environmental Protection Agency's (EPA) Environmental Monitoring Systems Laboratory in Las Vegas (EMSL-LV) continued its Offsite Radiological Safety Program for the Nevada Test Site (NTS) and other sites of past underground nuclear tests. For each test, the Laboratory provided airborne meteorological measurements, ground and airborne radiation monitoring teams, and special briefings to the Test Controller's Advisory Panel. Test-related radioactivity from the NTS was detected offsite following the Riola Test conducted on September 25, 1980. This consisted of xenon-133 (3.4 x 10 -11 μCi/m1) and xenon-135 (3.6 x 10 -10 μCi/m1) in a compressed air sample collected at Lathrop Wells, Nevada. The estimated dose equivalent to the whole body of a hypothetical receptor at Lathrop Wells from exposure to the radioxenon was 0.011 mrem, which is 0.006 percent of the radiation protection guide for a suitable sample of the general population. Whole-body counts of individuals residing in the environs of the NTS showed no manmade radionuclides attributable to the testing program. The only radioactivity from non-NTS sites of past underground nuclear tests was due to tritium in water samples collected from the Project Dribble Site near Hattiesburg, Mississippi, and the Project Long Shot Site on Amchitka Island, Alaska. The maximum concentrations measured at these locations were 1 and 0.1 percent of the Concentration Guide for drinking water, respectively. A small amount of airborne radioactivity originating from nuclear tests carried out by the People's Republic of China was detected during 1980 at some stations scattered throughout the Air Surveillance Network. The Laboratory's Animal Investigation Program sampled tissues from wildlife and domestic animals on and around the NTS. Data from analysis of these tissues are published separately in an annual report

  19. JAEA's efforts for regional transparency in the area of nuclear nonproliferation

    International Nuclear Information System (INIS)

    Hoffheins, Barbara; Kawakubo, Yoko; Inoue, Naoko

    2014-03-01

    The Japan Atomic Energy Agency (JAEA) has undertaken a joint R and D project with the US Department of Energy's National Nuclear Security Administration (DOE/NNSA) for the purposes of developing an Information Sharing Framework (ISF) for regional nonproliferation cooperation since July 2011. This project builds on nearly twenty years of technical cooperation between JAEA, its predecessor organizations and the DOE including the activities to define, develop and test transparency technologies and other multilateral efforts. The objective of current project is to design a viable information sharing process to support the goals of building confidence in the peaceful nature of regional nuclear programs. At the end of a two-year-effort, project partners, JAEA and Sandia National Laboratories (SNL), have defined the comprehensive requirements for an ISF that will ensure nonproliferation transparency success and sustainability. In October 2011, a parallel project with the similar title and objective was launched under the arrangement between the US DOE/NNSA and the Republic of Korea Ministry of Education, Science and Technology (MEST). Since then, JAEA, SNL, the Korea Institute for Nuclear Nonproliferation and Control (KINAC) and Korea Atomic Energy Institute (KAERI) have jointly carried out the project in a form of informal, multilateral cooperation. The project partners have identified needs and audience for ISF, and initiated the discussion to develop requirements for ISF through workshops, meetings, regular telephone conferences, etc. The activities include conducting a survey to identify stakeholders' needs and requirements for an ISF, launching a website to practice information sharing concepts, and presenting papers. This paper provides the historical context of the current project to establish ISF, and reports the progress to date and speculates on future directions. (author)

  20. Plutonium and Uranium in Human Bones from Areas surrounding the Semipalatinsk Nuclear Test Site

    OpenAIRE

    Masayoshi, YAMAMOTO; Masaharu, HOSHI; Aya, SAKAGUCHI; Kunihiko, SHINOHARA; Osamu, KURIHARA; Kazbek N., APSALIKOV; Boris I., GUSEV; Low Level Radioactivity Laboratory, K-INET, Kanazawa University; Research Institute for Radiation Biology and Medicine, Hiroshima University; Low Level Radioactivity Laboratory, K-INET, Kanazawa University; Japan Nuclear Cycle Development Institute; Japan Nuclear Cycle Development Institute; Kazakh Science Research Institute for Radiation, Medicine and Ecology; Kazakh Science Research Institute for Radiation, Medicine and Ecology

    2006-01-01

    To evaluate the present levels of^Pu and U in residents living near the Semipalatinsk nuclear test site, more than 70 bone samples were obtained at autopsy. The subjects ranged in age from 30 to 86 years (mean 59.3±12.9). Most of the samples consisted of victims who died of various diseases. Plutonium and U were radiochemically separated and determined by α-ray spectrometry. The mean concentrations of ^Pu and ^U observed were 0.050±0.041 mBq/g-ash (vertebrae 71, long-bones 18) and 0.28±0.13 m...

  1. Transportation of nuclear weapons through urban areas in the United Kingdom

    International Nuclear Information System (INIS)

    1990-01-01

    This study concentrates on the road carriage of assembled nuclear warheads to and from the Royal Ordnance factory at Burghfield, Berkshire - a task that is necessary to deliver new warheads to the sites of storage and deployment, and which also entails movement of existing stocks of warheads being returned to Burghfield for maintenance, refurbishing and or replacement. During these movements there is risk of accident and damage to the warhead assemblies in transit and, therefore, consequences that could result in harm to people and property in the locality of the accident. (author)

  2. Public-relation and countermeasure in crisis in the area of nuclear and radiation safety

    International Nuclear Information System (INIS)

    Wang Ruiping

    2009-01-01

    We are living in the world filling crises, with information transparency and economy globalization. The public-relation is one of important measures against those crises, whose achievements have been proved in our past practices. The countermeasure is a complementarity with propaganda and crises preparation for crises. It is a new field, needing new ideas and technology to fit developing situations, and new conceptions and countermeasures to set it up. In the article, the author is trying to explain why to apply the measure to answer crises in the nuclear and radiation safety management. (author)

  3. Weeds occurrence in areas submitted to distinct winter crops Ocorrência de plantas daninhas em áreas submetidas a manejos de inverno

    Directory of Open Access Journals (Sweden)

    G. Concenço

    2012-12-01

    Full Text Available In the Western Region of Brazil, it is usual to have two agricultural harvests in the same cropping season. Usually the first crop is soybean, followed by corn. In areas where corn is not planted due to a delayed harvest of soybean, farmers generally do not use winter crops. For these areas, the planting of winter oilseed crops aiming at the production of bio-fuels is one of the best alternatives; in addition, this would help in reducing the occurrence of weed species at the following summer crop. This study aimed to assessing the weed community in distinct winter crops post soybean crop, in terms of species composition, level of infestation and severity of occurrence. The following treatments were evaluated: agriculture under a no-till system with winter fallow, winter oilseed crops (crambe, radish, rapeseed with no-till agriculture in the summer, and agriculture under a conventional tillage system with winter fallow. Phytosociological evaluations of all treatments were carried out 75 DAE of the oilseed crops, and the diversity indexes of Margalef, Menhinick, Simpson, and Shannon-Weiner were determined. Areas were also grouped by cluster analysis based on UPGMA applied at Jaccard's similarity matrix. Among the treatments with winter coverage, radish was the most efficient crop in suppressing the occurrence of weed species. The area with conventional tillage agriculture and winter fallow allowed for a higher occurrence of troublesome weeds. On the other hand, the area under fallow showed the highest absolute level of infestation. Overall, oilseed crops in the winter contribute to lower levels of infestation by weed species in these areas.Na região Centro-Oeste do Brasil, é usual a obtenção de duas colheitas na mesma safra agrícola. Normalmente o primeiro cultivo é de soja, seguida por milho. Em áreas onde o milho não é cultivado devido à colheita tardia da soja, os produtores normalmente não utilizam culturas ou coberturas no per

  4. Evaluation of the geologic relations and seismotectonic stability of the Yucca Mountain area, Nevada Nuclear Waste Site Investigation (NNWSI)

    International Nuclear Information System (INIS)

    1988-10-01

    This report provides a summary of progress for the project ''Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI)'' for the eighteen month period of January 1, 1987 to June 10, 1988. This final report was preceded by the final report for the initial six month period, July 1, 1986 to December 31, 1986 (submitted on January 25, 1987, and revised in June 1987.) Quaternary Tectonics, Geochemical, Mineral Deposits, Vulcanic Geology, Seismology, Tectonics, Neotectonics, Remote Sensing, Geotechnical Assessments, Geotechnical Rock Mass Assessments, Basinal Studies, and Strong Ground Motion

  5. Evaluation of the geologic relations and seismotectonic stability of the Yucca Mountain Area Nevada Nuclear Waste Site Investigation (NNWSI)

    International Nuclear Information System (INIS)

    1995-01-01

    This report provides a summary of progress for the project open-quotes Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI).close quotes A similar report was previously provided for the period of 1 October 1993 to 30 September 1994. The report initially covers the activities of the General Task and is followed by sections that describe the progress of the other ongoing Tasks which are listed below. Task 1: Quaternary Tectonics Task 3: Mineral Deposits, Volcanic Geology Task 4: Seismology Task 5: Tectonics Task 8: Basinal Studies

  6. Integrated structural design of nuclear power plants for high seismic areas

    International Nuclear Information System (INIS)

    Rieck, P.J.

    1979-01-01

    A design approach which structurally interconnects NPP buildings to be located in high seismic areas is described. The design evolution of a typical 600 MWe steel cylindrical containment PWR is described as the plant is structurally upgraded for higher seismic requirements, while maintaining the original plant layout. The plant design is presented as having separate reactor building and auxiliary structures for a low seismic area (0.20 g) and is structurally combined at the foundation for location in a higher seismic area (0.30 g). The evolution is completed by a fully integrated design which structurally connects the reactor building and auxiliary structures at superstructure elevations as well as foundation levels for location in very severe seismic risk areas (0.50 g). (orig.)

  7. Product kerma in the air-area and radiation dose in dental radiodiagnosis; Produto kerma ar-area e dose efetiva em radiodiagnostico odontologico

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Alessandro Martins da, E-mail: amcosta@usp.br [Universidade de Sao Paulo (USP), Ribeirao Preto, SP (Brazil). Faculdade de Filosofia, Ciencias e Letras. Dept. de Fisica

    2014-07-01

    The main purpose of patient dosimetry in diagnostic radiology is to determine dosimetric quantities for the establishment and use of reference levels and comparative risk assessment. In recent publications the use of the air kerma-area product, PKA, has been suggested in dental radiology, as this quantity is more closely related to risk. The aim of this study was to perform a preliminary survey of PKA and effective dose in different types of dental examinations. The future perspective is a large-scale survey for the establishment and use of diagnostic reference levels in dentistry in Brazil. (author)

  8. Product kerma air area and effective dose in dental radiology; Produto kerma no ar-area e dose efetiva em radiodiagnostico odontologico

    Energy Technology Data Exchange (ETDEWEB)

    Mauro, Rodrigo A.P.; Souza, M. Daiane M.; Costa, Alessandro M. [Universidade de Sao Paulo (USP), Ribeirao Preto (USP), SP (Brazil). Faculdade de Filosofia Ciencias e Letras

    2016-07-01

    The main purpose of patient dosimetry in diagnostic radiology is to determine dosimetric quantities for the establishment and use of reference levels and comparative risk assessment. The use of the air kerma-area product, P{sub KA}, has been suggested in dental radiology, as this quantity is more closely related to risk. The aim of this study was to perform a preliminary survey of P{sub KA} and effective dose in different types of dental examinations. The future perspective is a large-scale survey for the establishment and use of diagnostic reference levels in dentistry in Brazil. (author)

  9. Product kerma air area and effective dose in dental radiology; Produto kerma no ar area e dose efetiva em radiodiagnostico odontologico

    Energy Technology Data Exchange (ETDEWEB)

    Mauro, Rodrigo A.P.; Souza, Daiane M.; Costa, Alessandro M., E-mail: rodrigomauro@usp.br [Universidade de Sao Paulo (USP), Ribeirao Preto, SP (Brazil). Faculdade de Filosofia Ciencias e Letras

    2016-07-01

    The main purpose of patient dosimetry in diagnostic radiology is to determine dosimetric quantities for the establishment and use of reference levels and comparative risk assessment. The use of the air kerma-area product, P{sub KA}, has been suggested in dental radiology, as this quantity is more closely related to risk. The aim of this study was to perform a preliminary survey of P{sub KA} and effective dose in different types of dental examinations. The future perspective is a large-scale survey for the establishment and use of diagnostic reference levels in dentistry in Brazil. (author)

  10. Calibration and intercomparison methods of dose calibrators used in nuclear medicine facilities; Metodos de calibracao e de intercomparacao de calibradores de dose utilizados em servicos de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Alessandro Martins da

    1999-07-01

    Dose calibrators are used in most of the nuclear medicine facilities to determine the amount of radioactivity administered to a patient in a particular investigation or therapeutic procedure. It is therefore of vital importance that the equipment used presents good performance and is regular;y calibrated at a authorized laboratory. This occurs of adequate quality assurance procedures are carried out. Such quality control tests should be performed daily, other biannually or yearly, testing, for example, its accuracy and precision, the reproducibility and response linearity. In this work a commercial dose calibrator was calibrated with solution of radionuclides used in nuclear medicine. Simple instrument tests, such as response linearity and the response variation of the source volume increase at a constant source activity concentration, were performed. This instrument can now be used as a working standard for calibration of other dose calibrators/ An intercomparison procedure was proposed as a method of quality control of dose calibrators used in nuclear medicine facilities. (author)

  11. Exploration of cystalline rocks for nuclear waste repositories: Some strategies for area characterization

    International Nuclear Information System (INIS)

    Trask, N.J.; Roseboom, E.H.; Watts, R.D.; Bedinger, M.S.

    1991-01-01

    A general strategy for the exploration of crystalline rock massed in the eastern United States for the identification of potential sites for high-level radioactive waste repositories has been generated by consideration of the Department of Energy (DOE) Siting Guidelines, available information on these crystalline rocks, and the capabilities and limitations of various exploration methods. The DOE has recently screened over 200 crystalline rock massed in 17 states by means of literature surveys and has recommended 12 rock masses for more intensive investigation including field investigations. The suggested strategy applies to the next stage of screen where the objective is to identify those potential sites that merit detailed site characterization including an exploratory shaft and underground study. This document discusses strategies for reconnaissance and field investigations, including the early phases of drilling, to provide geoscience information on the areas under construction. A complete Area Characterization Plan, to be developed by DOE with involvement of the states within which the areas to be studied are located, will outline all of the investigations to be carried out in the area phase including their cost and scheduling. Here, we provide input for the Area Characterization Plan by discussing what we believe to be the most important issues that need to be addressed in this phase and suggesting methods for their resolution. This report is not intended as a complete outline of area phase geoscience investigations, however. 79 refs., 4 figs

  12. Assessment of factors that affect the effectiveness of regulatory bodies: an application to the nuclear area

    International Nuclear Information System (INIS)

    Almeida, Ivan Pedro Salati de

    2005-09-01

    This work examines the main factors that affect the effectiveness of the non-economic regulatory process and establishes a model to propose actions to improve the regulation and the role of the regulatory body. The Soft Systems Methodology (SSM) is used and some tools for analysis, derived from the expectations of the stake holders, are added to the methodology. The stake holders taken into account are the public, the licensees, the supervisory bodies, other regulatory bodies, international organizations, concerned groups, and the regulatory body staff. The proposed actions aim to gradually change the organization, and the adopted methodology sees the organizational evolution as a continuum. Some elements of the Theory of Complexity are compared to the SSM concepts in order to validate the evolutionary approach. The model is applied to the specific case of,the nuclear regulation and the Brazilian regulatory body. Situations perceived as 'problem situations' are listed and some actions are proposed for improvement, including the establishment of performance indicators for effectiveness in nuclear regulation. (author)

  13. Hybrid environmental robot: a tool for monitoring gas on flooded area; Robo ambiental hibrido: utilizacao como ferramenta para monitoramento de gases em areas alagadas

    Energy Technology Data Exchange (ETDEWEB)

    Goes, Emerson de; Cerqueira, Romulo Curty; Reis, Ney Robinson S. [PETROBRAS, Rio de Janeiro, RJ (Brazil)

    2008-07-01

    The impoundment of rivers for power generation leads to flooding of vast areas of land vegetation. Most submerged plants, die and enter into decomposition, releasing CO2 (carbon dioxide), CH4 (methane gas) into the air for many years. Scientists from around the world seek to clarify the processes to which these gases are submitted and their contributions to the process of global warming. Estimates suggest that the re-use of methane that passes through the turbines of these power plants could increase their energy potential by 75% and reduce their emissions of these gases by 65%, reducing their impact on global warming and resulting in carbon credits. To check the feasibility of using new processes and technologies to generate energy that recycles this biogas, operations for monitoring these biogases become routine tasks. The frequency is such that the exposure of humans to the risks of gas combustion, inherent to scenarios where these operations take place, becomes unacceptable. This motivates the use of robots in this activity. This paper presents the multi-mission platform Hybrid Environmental Robot, named 'Chico Mendes', as a tool for tracking gas emission and specially designed for flooded forest areas.

  14. Comparative QRA (Quantitative Risk Analysis) of natural gas distribution pipelines in urban areas; Analise comparativa dos riscos da operacao de linhas de gas natural em areas urbanas

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Luiz Fernando S. de [Energy Solutions South America (Brazil); Cardoso, Cassia de O.; Storch, Rafael [Det Norske Veritas (DNV) (Brazil)

    2008-07-01

    The natural gas pipeline network grows around the world, but its operation inherently imposes a risk to the people living next to pipelines. Due to this, it is necessary to conduct a risk analysis during the environmental licensing in Brazil. Despite the risk analysis methodology is well established, some points of its application for the distribution pipelines are still under discussion. This paper presents a methodology that examines the influences of major projects and operating parameters on the risk calculation of a distribution pipeline accident in urban areas as well as the possible accident scenarios assessment complexity. The impact of some scenarios has been evaluated using a Computational Fluid Dynamics tool. The results indicate that, under certain conditions, the risks from the pipeline operation under operating pressures of 20 bar may be acceptable in location class 3 or even in class 4. These results play a very important role if management decisions on the growth of the distribution of natural gas network in densely populated areas as well as in the improvement of laws to control the activity of distribution of natural gas. (author)

  15. Hematology, micronuclei and nuclear abnormalities in fishes from São Francisco river, Minas Gerais state, Brazil = Hematologia, micronúcleos e anomalias nucleares em peixes do rio São Francisco, Estado de Minas Gerais, Brasil

    Directory of Open Access Journals (Sweden)

    Robson Seriani

    2011-01-01

    Full Text Available This study aimed to determine the variables leukocytary, erythrocytary, frequency of micronuclei and nuclear abnormalities in peripheral erythrocytes of Prochilodus argenteus, Pimelodus maculatus and Myleus micans from São Francisco river basin, Minas Gerais State, during the summer and winter. Thrombocytes, hematocrit and leukocyte of P.argenteus series, was influenced by climatic conditions. In P. maculatus, not were significant differences for all leukocytes and thrombocytes. In M. micans, values are unprecedented in the literature, with MCV and absolute number of leukocytes found superior to other species of the family Characidae. The frequency of micronuclei and nuclear abnormalities in erythrocytes, the three species not showed seasonal differences between the sites. However, the highest values were found in summer. Furthermore, we observed a positive correlation between the increase in the percentage of micronuclei with nuclear abnormalities.O presente estudo teve como objetivo, determinar as variáveis leucocitárias, eritrocíticas, freqüência de micronúcleos e anomaliasnucleares nos eritrócitos do sangue periférico de Prochilodus argenteus, Pimelodus maculatus e Myleus micans de um trecho da bacia do rio São Francisco, Minas Gerais, no verão e inverno. Trombóctios, hematócrito e a serie leucocítária de P.argenteus, foi influenciado pela sazonalidade. Em P. maculatus, não ocorreram diferenças significativas para todos os leucócitos e trombócitos. Em M. micans, os valores são inéditos na literatura, apresentando VCM e número absoluto de leucócitos superior ao encontrados para outras espécies dafamília Characidae. A freqüência de micronúcleos e de anomalias nucleares nos eritrócitos, nas três espécies não apresentou diferenças sazonais e entre os pontos amostrais. No entanto, os valores mais altos foram encontrados no verão. Além disso, foi possível observar correlação positiva entre o aumento da

  16. At convenience and systematic random sampling: effects on the prognostic value of nuclear area assessments in breast cancer patients.

    Science.gov (United States)

    Jannink, I; Bennen, J N; Blaauw, J; van Diest, P J; Baak, J P

    1995-01-01

    This study compares the influence of two different nuclear sampling methods on the prognostic value of assessments of mean and standard deviation of nuclear area (MNA, SDNA) in 191 consecutive invasive breast cancer patients with long term follow up. The first sampling method used was 'at convenience' sampling (ACS); the second, systematic random sampling (SRS). Both sampling methods were tested with a sample size of 50 nuclei (ACS-50 and SRS-50). To determine whether, besides the sampling methods, sample size had impact on prognostic value as well, the SRS method was also tested using a sample size of 100 nuclei (SRS-100). SDNA values were systematically lower for ACS, obviously due to (unconsciously) not including small and large nuclei. Testing prognostic value of a series of cut off points, MNA and SDNA values assessed by the SRS method were prognostically significantly stronger than the values obtained by the ACS method. This was confirmed in Cox regression analysis. For the MNA, the Mantel-Cox p-values from SRS-50 and SRS-100 measurements were not significantly different. However, for the SDNA, SRS-100 yielded significantly lower p-values than SRS-50. In conclusion, compared with the 'at convenience' nuclear sampling method, systematic random sampling of nuclei is not only superior with respect to reproducibility of results, but also provides a better prognostic value in patients with invasive breast cancer.

  17. JSPS-CAS Core University Program seminar on summary of 10-year collaborations in plasma and nuclear fusion research area

    International Nuclear Information System (INIS)

    Toi, Kazuo; Wang Kongjia

    2011-07-01

    The JSPS-CAS Core University Program (CUP) seminar on “Summary of 10-year Collaborations in Plasma and Nuclear Fusion Research Area” was held from March 9 to March 11, 2011 in the Okinawa Prefectural Art Museum, Naha city, Okinawa, Japan. The collaboration program on plasma and nuclear fusion started from 2001 under the auspices of Japanese Society of Promotion of Science (JSPS) and Chinese Academy of Sciences (CAS). This year is the last year of the CUP. This seminar was organized in the framework of the CUP. In the seminar, 29 oral talks were presented, having 14 Chinese and 30 Japanese participants. These presentations covered key topics related to the collaboration categories: (1) improvement of core plasma properties, (2) basic research on fusion reactor technologies, and (3) theory and numerical simulation. This seminar aims at summarizing the results obtained through the collaborations for 10 years, and discussing future prospects of China-Japan collaboration in plasma and nuclear fusion research areas. (author)

  18. Innovation and knowledge generation in cooperation nets: challenges for regulations in the nuclear safety area in Brazil

    International Nuclear Information System (INIS)

    Staude, Fabio

    2014-01-01

    The importance of inter-organisational cooperation within the innovation process has been increasingly recognized. In fact, all organisations, at some point, need to look to external sources for inputs to the process of building up technological competence. In this sense, through a detailed case study, this thesis examine theoretical and empirically how collaborative initiatives have supported the Brazilian nuclear regulatory body in the development and implementation of innovations, in order to verify the positive relationship between the collaboration and the organisational innovation performance. Emphasizing the importance of both internal sources of knowledge and external participation, the study encompasses documentary analysis, a preliminary survey and semi-structured interviews with the regulatory body employers in charge of controlling medical and research facilities and activities involving radiation sources. The thesis demonstrates that innovations developed and implemented in the Brazilian nuclear safety and security area are associated with collaborative initiatives, in order to improve the organizational capability to fulfill safety obligations, providing some important implications for regulatory body managers concerned with the management of innovation. The findings also identified actors with a significant degree of influence in the innovation process. The result reveals that the support provided by these actors has a significant influence on the innovation performance of the Brazilian nuclear regulatory body, suggesting that Brazil should adopt more interactive models of innovation and knowledge transfer. In addition, the findings show that these key actors can play a very distinctive role in the context of sectoral systems of innovation information regime. (author)

  19. Pesticidas no perfil de solos em áreas de plantação de cebolas em Ituporanga, SC Pesticides in the soil profile in planting areas of onions in Ituporanga, SC

    Directory of Open Access Journals (Sweden)

    Adilson Pinheiro

    2011-05-01

    Full Text Available Objetivou-se com este trabalho avaliar as concentrações de resíduos de pesticidas no perfil do solo sob cultura de cebola, no município de Ituporanga, em Santa Catarina. Coletas de amostras foram realizadas nas profundidades de 0 a 20, 40 a 60 e 80 a 100 cm, em três áreas com plantação de cebola. Nestas áreas são realizadas rotações de cultura, abrangendo o milho, cebola, batata, feijão e beterraba. Três séries de amostragens foram realizadas nos períodos de 2006 e 2007, sendo coletadas, em um ano, amostras simples e, no outro, uma amostra composta. Para cada amostra foram determinadas as concentrações dos herbicidas: 2,4-D, alacloro, atrazina, diurom, dos fungicidas: azoxistrobina, metalaxil, metconazol, tebuconazol e do inseticida: lambda-cialotrina. Os resultados mostram que os ingredientes ativos considerados foram detectados nas três profundidades. Os fungicidas foram detectados com maior frequência na camada superficial. As concentrações variaram entre as áreas e entre as profundidades, de forma descontínua. O comportamento de distribuição das concentrações foi similar para todos os pesticidas. Supõe-se que a existência de caminhos preferenciais no perfil do solo seja o fator responsável pela ocorrência de concentrações elevadas em profundidade, de forma irregular.This study aims to evaluate the pesticide concentrations in the soil profile under cultivation of onion in the municipality of Ituporanga in Santa Catarina. Samples of soil were collected, at depths of 0-20, 40-60 and 80-100 cm in three areas. In these the maize, onion, potatoes, beans, and beets are used in crop rotation. Three sets of samples were collected in the period 2006 and 2007. In the first year single samples were collected and in the other year, a composite sample. For each sample, the concentrations of herbicide 2,4-D, alachlor, atrazine, diuron, of fungicides: azoxystrobin, metalaxyl, metconazole, tebuconazole and of insecticides

  20. Trap-nesting bees (Hymenoptera, Apoidea in areas of dry semideciduous forest and caatinga, Bahia, Brazil Abelhas (Hymenoptera, Apoidea que nidificam em ninhos-armadilha em áreas de floresta semi-decídua e caatinga, Bahia, Brasil

    Directory of Open Access Journals (Sweden)

    Cândida M. L. Aguiar

    2005-12-01

    Full Text Available In this study were examined the species richness and seasonal abundance of cavity-nesting bees in areas of dry semi-deciduous forest and caatinga in the State of Bahia, Brazil. Sampling was done employing two types of trap-nests: bamboo canes and tubes made of black cardboard with dimensions of either 58 x 6 mm or 105 x 8 mm. The traps were inspected once a month. One hundred and forty-six nests of 11 bee species were collected in the forest, and 121 nests of seven species were collected in the caatinga. Five species of cleptoparasitic bees were also reared from these nests. The highest nesting frequencies occurred in the wet season in both areas. Nests parasitism was important only for Centris tarsata Smith, 1874, and was higher at the caatinga site than in the forest. The mortality of pre-emergent adults was high, especially in C. tarsata,Tetrapedia diversipes Klug, 1810 and Euglossa cordata (Linnaeus, 1758. Information on the number of cells per nest, the size, shape, and arrangement of brood cells in the nests, as well as the number of adults produced and the number of generations per year are also presented. Species richness, temporal patterns of nesting, and percentage of parasitism were compared with other habitats.Neste estudo foram investigadas a riqueza de espécies e a abundância sazonal de abelhas que nidificam em cavidades em áreas de Floresta estacional semi-decídua e Caatinga na Bahia. A amostragem foi realizada com dois tipos de ninhos-armadilha (= N.A.: gomos de bambu e tubos de cartolina preta (58 x 6 mm e 105 x 8 mm. Os N.A. foram inspecionados uma vez por mês. Foram coletados 146 ninhos de 11 espécies de abelhas na floresta e 121 ninhos de sete espécies na caatinga. Além disso, cinco espécies de abelhas cleptoparasitas foram criadas a partir destes ninhos. As freqüências de nidificação mais altas ocorreram na estação úmida em ambas as áreas. Parasitismo de ninhos foi importante apenas para Centris tarsata

  1. <em>Angiostrongylus vasorumem> in red foxes (<em>Vulpes vulpesem> and badgers (<em>Meles melesem> from Central and Northern Italy

    Directory of Open Access Journals (Sweden)

    Marta Magi

    2010-06-01

    Full Text Available Abstract During 2004-2005 and 2007-2008, 189 foxes (<em>Vulpes vulpesem> and 6 badgers (<em>Meles melesem> were collected in different areas of Central Northern Italy (Piedmont, Liguria and Tuscany and examined for <em>Angiostrongylus vasorumem> infection. The prevalence of the infection was significantly different in the areas considered, with the highest values in the district of Imperia (80%, Liguria and in Montezemolo (70%, southern Piedmont; the prevalence in Tuscany was 7%. One badger collected in the area of Imperia turned out to be infected, representing the first report of the parasite in this species in Italy. Further studies are needed to evaluate the role played by fox populations as reservoirs of infection and the probability of its spreading to domestic dogs.
    Riassunto <em>Angiostrongylus vasorumem> nella volpe (<em>Vulpes vulpesem> e nel tasso (<em>Meles melesem> in Italia centro-settentrionale. Nel 2004-2005 e 2007-2008, 189 volpi (<em>Vulpes vulpesem> e 6 tassi (<em>Meles melesem> provenienti da differenti aree dell'Italia settentrionale e centrale (Piemonte, Liguria Toscana, sono stati esaminati per la ricerca di <em>Angiostrongylus vasorumem>. La prevalenza del nematode è risultata significativamente diversa nelle varie zone, con valori elevati nelle zone di Imperia (80% e di Montezemolo (70%, provincia di Cuneo; la prevalenza in Toscana è risultata del 7%. Un tasso proveniente dall'area di Imperia è risultato positivo per A. vasorum; questa è la prima segnalazione del parassita in tale specie in Italia. Ulteriori studi sono necessari per valutare il potenziale della volpe come serbatoio e la possibilità di diffusione della parassitosi ai cani domestici.

    doi:10.4404/hystrix-20.2-4442

  2. Views of West Valley area residents concerning the Nuclear Fuel Services facility at West Valley, New York

    International Nuclear Information System (INIS)

    Kamieniecki, S.; Milbrath, L.W.

    1978-06-01

    A number of major findings have emerged from this analysis. Although most people have heard or read about the Nuclear Fuel Services plant at West Valley, few exhibit a high level of knowledge about the issue area. A clear majority of residents living in the region are concerned about the presence of the facility. Many are particularly concerned about the health dangers that can result from radioactive contamination of the environment. People want to see something done about the facility, but do not know exactly what. When forced to choose one out of three possible alternatives, twice as many people preferred to ''completely remove the plant and restore the area'' than either of the two remaining alternatives. People who are concerned about the facility tend to favor removal of the plant and restoration of the area. Nearly three-fourths of West Valley area residents who believe that the plant did not employ enough people to significantly help the economy of the region favor removal of the facility and restoration of the area. The results of this study may help policymakers choose the most acceptable course of action

  3. Assessment of fast and thermal neutron ambient dose equivalents around the KFUPM neutron source storage area using nuclear track detectors

    Energy Technology Data Exchange (ETDEWEB)

    Fazal-ur-Rehman [Physics Department, King Fahd University of Petroleum and Minerals, Dhahran 31261 (Saudi Arabia)]. E-mail: fazalr@kfupm.edu.sa; Al-Jarallah, M.I. [Physics Department, King Fahd University of Petroleum and Minerals, Dhahran 31261 (Saudi Arabia); Abu-Jarad, F. [Radiation Protection Unit, Environmental Protection Department, Saudi Aramco, P. O. Box 13027, Dhahran 31311 (Saudi Arabia); Qureshi, M.A. [Center for Applied Physical Sciences, King Fahd University of Petroleum and Minerals, Dhahran 31261 (Saudi Arabia)

    2005-11-15

    A set of five {sup 241}Am-Be neutron sources are utilized in research and teaching at King Fahd University of Petroleum and Minerals (KFUPM). Three of these sources have an activity of 16Ci each and the other two are of 5Ci each. A well-shielded storage area was designed for these sources. The aim of the study is to check the effectiveness of shielding of the KFUPM neutron source storage area. Poly allyl diglycol carbonate (PADC) Nuclear track detectors (NTDs) based fast and thermal neutron area passive dosimeters have been utilized side by side for 33 days to assess accumulated low ambient dose equivalents of fast and thermal neutrons at 30 different locations around the source storage area and adjacent rooms. Fast neutron measurements have been carried out using bare NTDs, which register fast neutrons through recoils of protons, in the detector material. NTDs were mounted with lithium tetra borate (Li{sub 2}B{sub 4}O{sub 7}) converters on their surfaces for thermal neutron detection via B10(n,{alpha})Li6 and Li6(n,{alpha})H3 nuclear reactions. The calibration factors of NTD both for fast and thermal neutron area passive dosimeters were determined using thermoluminescent dosimeters (TLD) with and without a polyethylene moderator. The calibration factors for fast and thermal neutron area passive dosimeters were found to be 1.33 proton tracks cm{sup -2}{mu}Sv{sup -1} and 31.5 alpha tracks cm{sup -2}{mu}Sv{sup -1}, respectively. The results show variations of accumulated dose with the locations around the storage area. The fast neutron dose equivalents rates varied from as low as 182nSvh{sup -1} up to 10.4{mu}Svh{sup -1} whereas those for thermal neutron ranged from as low as 7nSvh{sup -1} up to 9.3{mu}Svh{sup -1}. The study indicates that the area passive neutron dosimeter was able to detect dose rates as low as 7 and 182nSvh{sup -1} from accumulated dose for thermal and fast neutrons, respectively, which were not possible to detect with the available active neutron

  4. Basofilia e anisotropia nucleares em células de camundongo após tratamento com oxamniquine Nuclear basophilia and anisotropy in cells of mice treated with oxamniquine

    Directory of Open Access Journals (Sweden)

    Ivanira José Bechara

    1984-02-01

    Full Text Available Com o objetivo de se estudar a ação da oxamniquine, uma droga utilizada no tratamento da esquistossomose, sobre a cromatina de núcleos de células animais, foram estudados os padrões de basofilia e anisotropia nucleares em hepatócitos, em células do músculo cardíaco e em linfócitos de camundongos adultos jovens. A oxamniquine foi administrada por via oral (436 mg/kg e preparados foram obtidos após diversos tempos de fornecimento da droga aos animais. Nos núcleos corados com azul de toluidina a pH 4,0, após digestão com RNAse, não se encontrou diferença quanto aos padrões de basofilia e anisotropia comparando-se animais tratados com controles. Demonstrou se assim que as moléculas de oxamniquine não se alojam no interior da dupla hélice do DNA, não alteram a sua conformação helicoidal nem se ligam aos grupos fosfatos livres desta macromolécula, diferindo, portanto, da atuação de outro esquistossomicida, o hycanthone.With the aim of evaluating the effect of oxamniquine, a drug used in the clinical trials of schistosomiasis mansoni, on chromatin of animal cell nuclei, the patterns of nuclear basophilia and anisotropy were determined for hepatocytes, cardiac miocytes, and lymphocytes of young adult mice. The animals received the oxamniquine orally in a single dose of 436 mg/kg. Cell preparations were obtained at various times after the administration of the drug. The nuclei were subjected to RNAse digestion and stained with a toluidine blue solution at pH 4.0. No difference was found when comparing the patterns of nuclear basophilia and anisotropy of treated animals with those of untreated controls. It was demonstrated that the oxamniquine molecules do not penetrate the interior of the DNA double helix, neither do they alter the helical conformation of this nucleic acid. Furthermore, the oxamniquine molecules do not attach themselves to the free phosphate groups of the DNA. Therefore, this drug does not affect the DNA of the

  5. Measurement of local dose rates in controlled areas of nuclear power plants. Version 6/85

    International Nuclear Information System (INIS)

    1985-01-01

    Local dose rate measurements according to this regulation, serve the following purposes: Development of preventive measures for radiation protection with respect to maintenance and modifications in controlled areas, e.g. determination of individual measures for personnel protection, development of flow charts and dose rate estimates; monitoring of the personnel's location of activity within the controlled area, including determination of time-dependence of local dose rates and determination of immediate radiation protection measures required; limitation and identification of controlled areas. Such measurements are performed to ensure that the principles of radiation protection as stated in Art. 28 (1) of the Radiation Protection Ordinance with respect to external radiation exposure of the personnel, and the requirements of Art. 61 (1) of the Radiation Protection Ordinance relating to controlled areas are met and the limitation and identification of controlled areas as prescribed in Art 57 (1) of the Radiation Protection Ordinance can be performed. They are not used to determine body doses as per Art. 63 of the Radiation Protection Ordinance. (orig./HP) [de

  6. Estimative of dose area product in interventional cardiology procedures: a literature review; Estimativa do produto dose-area em procedimentos de cardiologia intervencionista: uma revisao de literatura

    Energy Technology Data Exchange (ETDEWEB)

    Real, Jessica V.; Santos, Romulo R.; Luz, Renata M. da [Pontificia Universidade Catolica do Rio Grande do Sul (PUCRS), Porto Alegre, RS (Brazil). Hospital Sao Lucas. Servico de Fisica Medica; Friedrich, Barbara Q.; Silva, Ana Maria Marques da, E-mail: jessica.real@pucrs.br [Pontificia Universidade Catolica do Rio Grande do Sul (PUCRS), Porto Alegre, RS (Brazil). Faculdade de Fisica

    2014-08-15

    The aim of this work is to present a literature review of the values of dose area product (DAP) in coronary angiography (CA) and percutaneous transluminal coronary angioplasty (PTCA), achieved by papers pubMaria E. D.lished in the last ten years. The results shows that the average values of DAP decreased by 22.6% and 5.78% for CA and PTCA procedures, respectively, in comparison with the studies published in the last 5 and 10 years. It was found that these values are in accordance to the recommendations published by IAEA and NCRP Although there was a reduction along the years for the average values of DAP, the data highlight the need for further studies on reference levels, as large variability are observed. (author)

  7. Environmental impact of the nuclear incident occurring in the middle Asia of the former Soviet Union on Beijing area

    International Nuclear Information System (INIS)

    Su Qiong

    1995-10-01

    The results of a nuclear incident occurred in the Middle Asia of the former Soviet Union was monitored and reported. Its impact on Beijing area was estimated under some assumptions. The concentration of 7 Be in the rain water was increased by two times or more compared with the annual average of the normal conditions and the one in the atmospheric dust was about two times during the monitoring period. The concentration of the 7 Be in the same samples is much higher than the one in the rainy season of the same period of the year. This will cause about 0.41 μSv/a additional dose load to the residents in Beijing area, which is about 1/10,000 to 1/1,000 of the dose level limitation set in the national standard 'GB4792-84'. (3 figs., 1 tab.)

  8. Identification and characterization of potential discharge areas for radionuclide transport by groundwater from a nuclear waste repository in Sweden.

    Science.gov (United States)

    Berglund, Sten; Bosson, Emma; Selroos, Jan-Olof; Sassner, Mona

    2013-05-01

    This paper describes solute transport modeling carried out as a part of an assessment of the long-term radiological safety of a planned deep rock repository for spent nuclear fuel in Forsmark, Sweden. Specifically, it presents transport modeling performed to locate and describe discharge areas for groundwater potentially carrying radionuclides from the repository to the surface where man and the environment could be affected by the contamination. The modeling results show that topography to large extent determines the discharge locations. Present and future lake and wetland objects are central for the radionuclide transport and dose calculations in the safety assessment. Results of detailed transport modeling focusing on the regolith and the upper part of the rock indicate that the identification of discharge areas and objects considered in the safety assessment is robust in the sense that it does not change when a more detailed model representation is used.

  9. A digital method for period measurements in a nuclear reactor; Um metodo digital para medidas de periodo em um reator nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Mundim, Sergio Gorretta

    1971-02-15

    The present paper begins by giving a theoretical treatment for the nuclear reactor period. The conventional method of measuring the period is analysed and some previously developed digital methods are described. The paper criticises the latter, pointing out some deficiencies which the proposed process is able to eliminate. All errors connected with this process are also analysed. The paper presents suitable solutions to reduce them to a minimum. The total error is found to he less than the error presented by the other methods described. A digital period meter is designed with memory resources and an automatic scaler changer. Integrated circuits specifications are used in it. Real time experiments with nuclear reactors were made in order to check te validity of the method. The data acquired were applied to a simulated digital period meter implemented in a general purpose computer. The nuclear part of the work was developed at the 'Comissao Nacional de Energia Nuclear' and the simulation work was dane at the 'Departamento de Calculo Cientifico' of COPPE, which also advised the author in the completion of this thesis. (author)

  10. A digital method for period measurements in a nuclear reactor; Um metodo digital para medidas de periodo em um reator nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Mundim, Sergio Gorretta

    1971-02-15

    The present paper begins by giving a theoretical treatment for the nuclear reactor period. The conventional method of measuring the period is analysed and some previously developed digital methods are described. The paper criticises the latter, pointing out some deficiencies which the proposed process is able to eliminate. All errors connected with this process are also analysed. The paper presents suitable solutions to reduce them to a minimum. The total error is found to he less than the error presented by the other methods described. A digital period meter is designed with memory resources and an automatic scaler changer. Integrated circuits specifications are used in it. Real time experiments with nuclear reactors were made in order to check te validity of the method. The data acquired were applied to a simulated digital period meter implemented in a general purpose computer. The nuclear part of the work was developed at the 'Comissao Nacional de Energia Nuclear' and the simulation work was dane at the 'Departamento de Calculo Cientifico' of COPPE, which also advised the author in the completion of this thesis. (author)

  11. Building the European Research Area in nuclear fission pioneering steps in actinide science

    International Nuclear Information System (INIS)

    Forsstroem, Hans

    2004-01-01

    The concept of the European Research Area (ERA) aims at closer development of research policies in Europe and closer networking of research capacities, to reduce fragmentation of research in Europe. The goal is to make European research more effective and competitive. Several approaches are made to create ERA. The European Research Framework Programme is one tool in this context, with the introduction of the new instruments, Integrated Projects, Networks of Excellence and Integrated Infrastructure Initiatives. Actinide science is one area that could benefit from better coordination and more effective use of the research capacities, both human and physical. The European Commission is thus funding a Network of Excellence (ACTINET-6) and an Integrated Project (EUROPART) in this area within the sixth EURATOM Framework Programme. (author)

  12. Allelic diversity in populations of Solanum lycocarpum A. St.-Hil (Solanaceae in a protected area and a disturbed environment Diversidade alélica em populações de Solanum lycocarpum A. St.-Hil (Solanaceae em Unidade de Conservação e em ambiente sob influência antrópica

    Directory of Open Access Journals (Sweden)

    Tânia Maria de Moura

    2011-12-01

    Full Text Available This study aimed to compare the genetic diversity of populations of Solanum lycocarpum A.St.-Hil between natural and human disturbed environments, with the assumption that protected areas have greater genetic diversity than disturbed areas. For this study, two populations were sampled in Goiás State, Brazil. One was located in a conservation unit, Serra de Caldas Novas State Park, in the Caldas Novas municipality. The other was located in a pasture area in the municipality of Morrinhos. The two populations are 41 km apart. We sampled 60 individuals from each population, which were genotyped with five microsatellite loci (SSR. The highest number of alleles was recorded in the population of the conservation unit, where we found 11 exclusive and five rare alleles. In the disturbed area, we recorded only three exclusive alleles and one rare allele. Although we did not observe significant inbreeding in these populations, genetic divergence between them was high (G ST (Hedrick=0.147 =0.147 for a species with long distance seed dispersal. The results corroborate the hypothesis that the population in the less disturbed area harbors greater allelic diversity. They also confirm the effectiveness of using protected areas to preserve the genetic diversity of the species.O presente trabalho teve por objetivo comparar a diversidade genética em populações de Solanum lycocarpum A.St.-Hil, em ambientes naturais e antropizados, sob a hipótese de que Unidades de Conservação abrigam maior diversidade genética que áreas antropizadas. Para isso foram estudadas duas populações da espécie, uma situada em uma Unidade de Conservação, o Parque Estadual da Serra de Caldas Novas (PESCAN em Caldas Novas/GO e outra situada em uma área de pastagem no município de Morrinhos-GO. As populações distanciam-se em 41 km. Foram amostrados 60 indivíduos de cada população e os mesmos foram genotipados com cinco locos microssatélites (SSR. Pode-se registrar a maior

  13. Study of cleft lip and palate deformities among the residents of the Semipalatinsk nuclear test site area in Kazakhstan

    International Nuclear Information System (INIS)

    Zhumadilova, A.; Sultanova, A.; Shabanbaeva, Zh.; Ergalieva, U.; Utulenova, G.; Abralina, Sh.; Okamoto, Tetsuji

    2010-01-01

    The aim was to investigate the association between long-term radiation exposure and the high prevalence of cleft lip and palate anomalies among the residents from exposed areas and to compare to non-exposed areas. A retrospective study of 716 case reports was carried out on cleft lip and palate deformities patients (1978-1998). The case reports were screened and studied for frequency of cleft lip and palate by gender and number of patients, including epidemiological studies of cleft lip and palate anomalies cases in 1000 newborns in the three zones of radiation risk where the hospitalized patients resided. The statistical analyses of the retrospective study of cleft lip and palate patients were estimated by X 2 -test and performed with the Stat View 5.0 statistical analysis program. 5,10 cases of cleft lip and palate patients per 1000 live births were calculated in the zone of maximum radiation risk, which is extremely high, and 2,30 cases of the anomalies per 1000 among the newborns in the zone of heightened radiation risk and both were significantly higher than those in the zone of minimum risk. The incidence varied in different years, from 5,66 per 1000 live births in 1978-1988 (at the time of nuclear testing) to 4,14 per 1000 live births in 1990-1998 (after the nuclear testing was stopped) in the area of maximum radiation risk and showed that the number of cleft lip and palate anomalies cases was significantly higher in both periods of time compare to the zones of heightened and minimum radiation risk. This study suggests that the high prevalence cleft lip and palate anomalies among the newborns from the exposed areas was due to the long-term radiation exposure.

  14. The decision-making process during accidents or incidents in the operational nuclear area

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Maria da Penha Sanches; Vanni, Silvia Regina Vanni [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil); Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)], email: penhamartins@yahoo.com.br, e-mail: sjcvanni@yahoo.com.br; Andrade, Delvonei Alves de [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)], e-mail: delvonei@ipen.br

    2009-07-01

    This study reflects on one of the human behavior mediating factors that face nuclear facility operators during their decision-making process. It includes some mental processes used to determine the best course of action, based on intuitive and creative decisions, within a specific set of rational conditions which depend much more on perception about threats than on theoretical knowledge. A fast and efficient decision, in an unstable and ongoing changing scenario/environment, is extremely complex. The decision-making process goes beyond the purely rational level and many times is influenced by intuition. The importance of the decision-making process leads the study to also review human factors. The methodology used in this paper is based on cognitive aspects which are focused essentially on studies such as: decision process models, decision types and human rationality limits (time) versus individual decisions. Lastly, it makes assessments on how reason, emotion and being under stress relate to the decision-making process (author)

  15. Economic comparison of nuclear, coal, and oil-fired electric generation in the Chicago area

    International Nuclear Information System (INIS)

    Corey, G.R.

    1981-01-01

    The current and historical performances of 17 large nuclear and coal- and oil-fired steam-electric generating units now operated by Commonwealth Edison Company are examined, and the actual busbar costs of electricity generated by these units in recent years are summarized. Cost estimates for future steam-electric units are provided, and attempts are made to deal realistically with the effect of inflation. Social and regulatory constraints are seen to affect the economics of future units and the willingness of the industry to finance them. It is concluded that, given the uncertainties, utility managers have an incentive to diversify their sources of power generation when society seems to discourage such a course of action. 6 refs

  16. Method for screening the Nevada Test Site and contiguous areas for nuclear waste repository locations

    International Nuclear Information System (INIS)

    Sinnock, S.; Fernandez, J.A.; Neal, J.T.; Stephens, H.P.; Hartway, B.L.; Los Alamos Technical Associates, Inc., NM)

    1982-01-01

    This paper outlines the general concepts of a technical method for systematic screening of the Nevada Test Site (NTS), Nye County, Nevada, for potentially suitable nuclear waste repository locations. After a general discussion of the organization and the purpose of the current screening activity, the paper addresses the steps of the screening method. These steps include: hierarchically organizing technical objectives for repository performance (an objectives tree); identifying and mapping pertinent physical characteristics of a site and its setting (physical attributes); relating the physical conditions to the objectives (favorability curves); identifying alternative locations and numerically evaluating their relative merits; investigating the effects of subjective judgments on the evaluations (sensitivity analyses); documenting the assumptions, logic, and results of the method. 19 references, 10 figures

  17. The decision-making process during accidents or incidents in the operational nuclear area

    International Nuclear Information System (INIS)

    Martins, Maria da Penha Sanches; Vanni, Silvia Regina Vanni; Andrade, Delvonei Alves de

    2009-01-01

    This study reflects on one of the human behavior mediating factors that face nuclear facility operators during their decision-making process. It includes some mental processes used to determine the best course of action, based on intuitive and creative decisions, within a specific set of rational conditions which depend much more on perception about threats than on theoretical knowledge. A fast and efficient decision, in an unstable and ongoing changing scenario/environment, is extremely complex. The decision-making process goes beyond the purely rational level and many times is influenced by intuition. The importance of the decision-making process leads the study to also review human factors. The methodology used in this paper is based on cognitive aspects which are focused essentially on studies such as: decision process models, decision types and human rationality limits (time) versus individual decisions. Lastly, it makes assessments on how reason, emotion and being under stress relate to the decision-making process (author)

  18. Prevalência de transtornos mentais em área urbana no norte de Minas Gerais, Brasil Prevalence of mental disorders in an urban area in Brazil

    Directory of Open Access Journals (Sweden)

    Luciana Colares Maia

    2004-10-01

    Full Text Available OBJETIVO: Detectar a prevalência de transtornos mentais em idosos residentes em área urbana. MÉTODOS: Uma amostra de 327 idosos (60 anos de idade ou mais residentes na cidade de Montes Claros, no norte de Minas Gerais, foi selecionada por amostragem probabilística, em estratos múltiplos, dentro de estrato homogêneo, sendo a unidade amostral o domicílio. Os transtornos mentais foram aferidos por meio de um questionário de rastreamento psicogeriátrico (QRP. Utilizou-se análise univariada usando o qui-quadrado e análise multivariada de regressão logística. RESULTADOS: A prevalência estimada de transtornos mentais foi 29,3%, associada com sexo feminino, número de doença, capacidade funcional e local de residência (favela/não favela. CONCLUSÕES: Comparando com outros estudos comunitários, a prevalência de distúrbios mentais entre os idosos na área urbana foi alta e está associada com múltiplas doenças, incapacidade e pobreza. É uma realidade preocupante pelo de seu impacto sobre a qualidade de vida relativa à saúde da população e sobre os serviços de saúde nas próximas décadas.OBJECTIVE: To detect the prevalence of mental disorders among the elderly residents of an urban area. METHODS: A sample of 327 elderly residents (60 years and older of the city of Montes Claros, in northern Minas Gerais, was selected by means of probabilistic sampling, in multiple strata, within a homogeneous stratum. The sample unit was the home. Mental disorders were determined by means of the Short Psychiatric Evaluation Schedule (SPES. Univariate analysis was done via the chi-squared test and multivariate analysis via logistical regression. RESULTS: The estimated prevalence of mental disorders was 29.3%. Their presence was associated with female sex, number of illnesses, functional capacity and place of residence (shantytown/non-shantytown. CONCLUSIONS: Comparing the results with other community studies, the prevalence of mental disorders

  19. An area of protection around nuclear facilities - questions at issue in atomic law and law concerning the protection against nuisances. Pt. 2

    International Nuclear Information System (INIS)

    Blickle, D.

    1973-01-01

    The necessity for an area of protection around nuclear facilities could originate from the need to protect these facilities against outside effects. Danger to nuclear facilities can only threaten from a few industries which are of a dangerous nature. In order to keep away these industries there is no need for an area of protection around the nuclear facilities. It would be sufficient to consider in the licensing procedures, according to the trade regulations, that the close proximity of nuclear facilities can present a danger of a special kind, whereby the standards of the nuclear licensing procedures are to be applied. In this context it would be permissible, too, to make bigger demands on the safety requirements than requested by the trade regulations solely. Furthermore, the need to keep away human settlements from the area with nuclear facilities without creating an area of protection can be complied with area planning by interpreting the laws of area planning in such a way that subsequent planning which would increase the risks can be rejected. In any case, poltical clarification of this point seems to be necessary. (orig./LN) [de

  20. An area of protection around nuclear facilities - questions at issue in atomic law and law concerning the protection against nuisances. Pt. 3

    International Nuclear Information System (INIS)

    Hasenfuss, W.

    1973-01-01

    The author takes the view that areas of protection do not only not promote but can impede more than hitherto the development of nuclear energy, a field in which it is vital to keep pace with other countries in the world, also after the decision of the Federal Court of Justice regarding the location of the KWO. The best guarantee for safe operation of a nuclear facility and for the protection of citizens, which would be the guarantee for the development of nuclear energy as well, are the safety precautions in the nuclear facility itself which are generally accepted and finely balanced with regard to their necessity and consequence. (orig./LN) [de

  1. An aerial radiological survey of the Fort Calhoun Nuclear Power Plant and surrounding area, Fort Calhoun, Nebraska

    International Nuclear Information System (INIS)

    1994-05-01

    An aerial radiological survey was conducted over the Fort Calhoun Nuclear Power Plant in Fort Calhoun, Nebraska, during the period June 19 through June 28, 1993. The survey was conducted at an altitude of 150 feet (46 meters) over a 25-square-mile (65-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Fort Calhoun Nuclear Power Plant and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 12 microroentgens per hour and were attributed to naturally-occurring uranium, thorium, and potassium. The aerial data were compared to ground-based benchmark exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system. A previous survey was conducted on August 9 and 10, 1972, before the plant began operation. Exposure rates measured in both surveys were consistent with normal terrestrial background

  2. IAEA Says Finland's Loviisa Nuclear Power Plant Committed to Safety, Sees Areas for Enhancement

    International Nuclear Information System (INIS)

    2018-01-01

    An International Atomic Energy Agency (IAEA) team of experts said the operator of Finland’s Loviisa Nuclear Power Plant (NPP) demonstrated a commitment to safety. The team also identified areas for further enhancement. The Operational Safety Review Team (OSART) concluded an 18-day mission on 22 March to Loviisa NPP, whose two 531-MWe pressurized-water reactors started commercial operation in 1977 and 1980, respectively. Fortum Power and Heat OY operate the plant, located about 100 km east of Helsinki, the capital. Nuclear power generates one-third of electricity in Finland, which has four operating power reactors and is constructing a fifth reactor. OSART missions aim to improve operational safety by objectively assessing safety performance using the IAEA’s safety standards and proposing improvement where appropriate. The 16-member team comprised experts from Brazil, Canada, China, France, Germany, Hungary, Romania, Russia Federation, Slovak Republic, South Africa, Spain, Ukraine, United Kingdom, United States of America as well as IAEA officials. The review covered the areas of leadership and management for safety; training and qualification; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency preparedness and response; accident management; human, technology and organizational interactions; and long-term operation. The team identified a number of good practices that will be shared with the nuclear industry globally, including: • The plant has developed the capability to automatically calculate leak rate tests of containment. • The plant established a process to test and improve modifications and updates early. • The plant has adopted a key system to effectively control access to various rooms in the plant. The mission made several proposals to improve operational safety, including: • The plant management should improve communications of their expectations and consistently reinforce their

  3. An overview of equivalent doses in eye lens of occupational radiation workers in medical, industrial and nuclear areas

    International Nuclear Information System (INIS)

    Lima, A.R.; Silva, F.C.A. da; Hunt, J.G.

    2013-01-01

    Some epidemiological evidences were recently reviewed by the ICRP and it was suggested that, for the eye lens, the absorbed dose threshold for induction of late detriments is about 0.5 Gy. On this basis, on 2011, the ICRP has recommended changes to the occupational dose limit in planned exposure situations, reducing the eye lens dose equivalent limit of 150 mSv to 20 mSv per year, on average, during the period of 5 years, with exposure not exceeding 50 mSv in a single year. Following the ICRP recommendation, the Brazilian Commission of Nuclear Energy (CNEN) adopted immediately the new limit to the eyes lens. This study aimed to show an overview about the doses in eye lens of occupational radiation workers in situations of planned exposures in the medical, industrial and nuclear areas, emphasizing the greatest radiological risks applications. It was observed that there are some limitations, such as example, to use individual monitor calibrated on Hp(3), to assess the equivalent dose in the eye lens. This limitation obstructs some experimental studies and monitoring of the levels of radiation received in the eye lens of radiation workers. Recent studies have showed that the lenses of eyes monitoring of workers, mainly in the planned exposure, must be follow-up. However, such researches were obtained only in medical exposures, mainly in interventional medicine procedures. Studies with planned exposure on nuclear and industrial areas are really needed and will be very important due to the new recommended by ICRP dose limits. (author)

  4. Palm oil as a sustainable energy alternative in degraded areas of the Amazon region; O dende como alternativa energetica sustentavel em areas degradadas na Amazonia

    Energy Technology Data Exchange (ETDEWEB)

    Villela, Alberto Arruda

    2009-02-15

    Bio fuels are important tools in reducing emissions of greenhouse gases (GHG); however, to minimize the conflict with food crops, energy crops with high efficiency and capacity to absorb Co2, such as the oil palm, should be prioritized. The European Union intends to replace 10% of liquid fossil fuel demand with bio fuels by 2020. According to studies conducted by the European Commission, this will entail the annual import of more than 3 million tonnes of palm oil, the most produced and least expensive vegetable oil in the world. 87% of global production comes from Indonesia and Malaysia, where the relentless expansion of oil palm cultivation has caused extensive forest devastation, threatening biodiversity and increasing GHG emissions. The Netherlands, a large importer of oil palm products, developed a methodology (Cramer) for the certification of sustainable bio energy production, assessing economic, social, environmental aspects, as well as GHG emissions, throughout the supply chain. It sets a mandatory minimum 30% reduction of GHG emissions in the bio-energy chain for use in transport and 70% for use in heat and power generation, as compared to the chain of the fossil counterpart. This dissertation shows that oil and bio diesel (ethyl ester) from palm grown in the Amazon meets this GHG mitigation criterion when degraded areas are utilized for cultivation, but not when forests are razed for that purpose. (author)

  5. Cold stress effects on cardiomyocytes nuclear size in: light microscopic evaluation Efeitos do estresse pelo frio sobre o tamanho nuclear do cardiomiócito em ratos: avaliação por microscopia de luz

    Directory of Open Access Journals (Sweden)

    Adriano Meneghini

    2008-12-01

    Full Text Available INTRODUCTION: Total body induced hypothermia and myocardial cooling are effective methods regarding myocardial protection during heart surgery and ischemia. It is described in previous studies that extreme low temperature exposure causes mitochondrial cristae and myofilament disarrangement in cardiomyocytes, however, no investigation has analyzed the effects of cold stress on nuclear size of cardiomyocytes. OBJECTIVES: To evaluate the effects of acute cold stress exposure on the nuclear size of cardiomyocytes in rats. METHODS: The experimental study procedures were performed on 300-310g adult male Wistar rats. Rats (n=20 were divided into two groups: 1 Control (CON and; 2 Induced hypothermic (IH group. Animals of IH group were exposed during 4 hours once at a controlled temperature of - 8ºC. It was performed histological analysis of liver and adrenal gland to examine the stress condition of animals. Cardiomyocytes nucleus size were examined by three independent investigators with the same and standardized criteria and analyzed by Bartko's intra-class correlation coefficient (R>0.75 = positive concordance. Student's t test was applied. The significance level was set at PINTRODUÇÃO: Hipotermia corporal induzida e resfriamento do miocárdio são métodos efetivos em relação à proteção domiocárdio durante cirurgias cardíacas e isquemia. É descrito na literatura que a exposição a temperaturas extremamente baixas causa comprometimentos de miofilamentos e de cristas mitocondriais em cardiomiócitos, entretanto, nenhum estudo analisou os efeitos do estresse pelo frio no tamanho do núcleo dos cardiomiócios. OBJETIVOS: Analisar os efeitos do estresse agudo pelo frio sobre o tamanho do núcleo dos cardiomiócitos. MÉTODOS: O estudo foi realizado em ratos Wistar adultos, pesando 300-310g (n=20. Os ratos foram divididos em dois grupos: 1 Controle (CON e; 2 Hipotermia induzido (IH. Os animais do grupo IH foram expostos a uma temperatura

  6. Implications for reconstruction of the relationship between nuclear industry and siting areas in Japan. Lessons learnt from the cases of Site Stakeholder Groups in United Kingdom

    International Nuclear Information System (INIS)

    Sugawara, Shin-etsu

    2014-01-01

    After the Fukushima nuclear accident, the Japanese nuclear community began to recognize the need for establishing local stakeholder meetings in nuclear siting areas for information sharing and communication in reference to the experiences in European countries. This report shows the patterns of institutional design and the management style of stakeholder meetings in UK based on the interview survey, including SSGs (Site Stakeholder Groups) around the NDA (Nuclear Decommissioning Authority) sites and LCLCs (Local Community Liaison Councils) around the nuclear power stations in operation. SSGs have developed a local-oriented management style under the leadership of independent chairs elected from local stakeholders, in contrast to LCLCs where the operator of nuclear energy facilities has the initiative of management. SSGs play critical roles in improving quality of decision-making and enhancing its legitimacy through providing forums for local stakeholder engagement in the process of NDA's consultations and BPEO (Best Practicable Environmental Option) implementation. Based on these insights from UK's cases, the author suggests the following remedies for the relationship between the nuclear industry and siting areas in Japan: (1) introducing evaluation systems of stakeholder engagement linked to the insurance rates of nuclear energy liability, and (2) modifying the nuclear safety agreements into risk management principles. (author)

  7. Fishing activity characterization in areas under influence of seismic activity; Caracterizacao da atividade pesqueira em areas sob influencia da atividade sismica

    Energy Technology Data Exchange (ETDEWEB)

    Fuse, Izabel Yukimi; Zanella, Joao Francisco Illa Font; Eliseire Junior, Dirceu; Pereira, Edisio [Hidrosfera Oceanografia e Meio Ambiente, Rio de Janeiro, RJ (Brazil); Souza, Sergio Augusto Coelho de; Ferraz, Alexandre; Costa, Leandro Soares da; Vidal, Leonardo; Duppre, Mauricio [Okeanos Consultoria e Meio Ambiente Ltda. (Brazil); Uller, George [CGG do Brasil, Rio de Janeiro, RJ (Brazil)

    2004-07-01

    Seismic surveys are an important method in prospecting for oil and gas reservoirs in the marine environment. The ELPN/IBAMA has required that companies develop an adequate social programme in parallel with the seismic surveys to establish a better interaction with the communities influenced by these operations and reduce possible negative effects. Between January and October 2003, CGG Brazil studied coastal communities in the following areas. BM-CE-1 e BM -CE-2, Ceara; Fragata, BM-ES-5 e BM-ES-6, Espirito Santo; BM BAR-1 e BM BAR-3, Maranhao and BM-C-25 and BM-C-16 off Campos basin. Communities and groups that could potentially be influenced by the surveys were visited to mitigate direct and indirect impacts. Preliminary results show that fisheries were the main group to be monitored. A standard questionnaire was used to characterize the local fisheries and interviews were held with fishermen, boat owners and members of the fishery industries (n=422). In Ceara the fishery is typically handmade and occurs in water depths up to 200 meters. The main boat propulsion is sail and the 'Cacoeira' is the most popular gear used. Off Espirito Santo, small and medium motored boats are usually used and line is the main gear among the fishermen. At Barreirinhas (Maranhao), boats are usually up to 14 meters long, and operate in water depths of up to 120 metres. Again the 'cacoeira' is the proffered gear. We concluded that Programs carried out by CGG reached their purpose. This is confirmed by low incident rate between seismic ships and the fisheries fleet. (author)

  8. Assessment of radiation doses to the public in areas contaminated by the Fukushima Daiichi Nuclear Power Station accident

    International Nuclear Information System (INIS)

    Takahara, Shogo; Iijima, Masashi; Shimada, Kazumasa; Kimura, Masanori; Homma, Toshimitsu

    2013-01-01

    In the areas contaminated by radioactive materials due to the Fukushima Daiichi Nuclear Power Station accident, many residents are exposed to radiation through various exposure pathways. Dose assessment is important for providing appropriate protection to the people and clarifying the impact of the accident. The aim of this study is to provide preliminary results of the assessment of radiation doses received by the inhabitants of Fukushima Prefecture. To assess the doses realistically and comprehensively, a probabilistic approach was adopted using data that reflected realistic environmental trends and lifestyle habits in Fukushima Prefecture. In the first year after the contamination, the 95th percentile of the annual effective dose received by the inhabitants evacuated from the evacuation areas and the deliberate evacuation areas was mainly in the 1-10 mSv dose band. However, the 95th percentile of the dose received by some outdoor workers and inhabitants evacuated from highly contaminated areas was in the 10-50 mSv dose band. The doses due to external exposure to deposited radionuclides were the dominant exposure pathway, and their contributions were about 90% under prevailing contamination conditions in Fukushima Prefecture. In addition, 20%-30% of the lifetime effective dose was delivered during the first year after the contamination. (author)

  9. Use of nuclear technique in samples for agricultural purposes Uso de técnica nuclear em amostras de interesse na agricultura

    Directory of Open Access Journals (Sweden)

    Kerley A. P. de Oliveira

    2013-02-01

    Full Text Available The concern related to environment is growing. Due to this, it is needed to determine chemical elements in a large range of concentration. The neutron activation technique (NAA determines the elemental composition by the measurement of artificial radioactivity in a sample that was submitted to a neutron flux. NAA is a sensitive and accurate technique with low detection limits. An example of application of NAA was the measurement of concentrations of rare earth elements (REE in waste samples of phosphogypsum (PG and cerrado soil samples (clayey and sandy soils. Additionally, a soil reference material of the International Atomic Energy Agency (IAEA was also analyzed. The REE concentration in PG samples was two times higher than those found in national fertilizers, (total of 4,000 mg kg-1 , 154 times greater than the values found in the sandy soil (26 mg kg-1 and 14 times greater than the in clayey soil (280 mg kg-1 . The experimental results for the reference material were inside the uncertainty of the certified values pointing out the accuracy of the method (95%. The determination of La, Ce, Pr, Nd, Pm, Sm, Eu, Tb, Dy, Ho, Er, Tm, Yb and Lu in the samples and reference material confirmed the versatility of the technique on REE determination in soil and phosphogypsum samples that are matrices for agricultural interest.A preocupação crescente com o meio ambiente leva à necessidade de serem determinados elementos químicos em faixas de concentração cada vez mais largas. Entre as técnicas existentes, está a ativação neutrônica (AAN, que determina a composição química elementar por meio da medida da radioatividade artificial induzida ao se submeter uma amostra a um fluxo de nêutrons. A AAN possui alta sensibilidade, exatidão, precisão e natureza não destrutiva (dispensa tratamento químico prévio. Como exemplo de aplicação da técnica, elementos terras raras (ETR foram determinados em amostras do resíduo fosfogesso (PG e de solo

  10. Repository for spent nuclear fuel. Preliminary construction description - layout D Oskarshamn the Simpevarp area

    International Nuclear Information System (INIS)

    2006-02-01

    This report presents the preliminary design of a repository located in the Simpevarp area. The description has been disposed so as to deal primarily with the site dependent layouts for the above- and underground constructions. The report is disposed as follows: c1 gives the background and some basic information. Chapter 2 presents the demands and necessary conditions that take precedence when adapting the plant to the local conditions, construction, operation and closure. Chapter 3 is a general description of the area, its infrastructure and the specific sites that have been studied. Chapter 4-5 describe the design of the plant for the two chosen sites. Chapter 6 gives a review of data for the plant, and Chapter 7 'References' is the last part of the main document. The appendices A-I give brief information on the general, non-site specific, parts of the plant, e.g. buildings, life cycle, system, operation and organization

  11. Repository for spent nuclear fuel. Preliminary construction description - layout D Oskarshamn the Laxemar area

    International Nuclear Information System (INIS)

    2006-05-01

    This report presents the preliminary design of a repository located in the Laxemar area. The description has been disposed so as to deal primarily with the site dependent layouts for the above- and underground constructions. The report is disposed as follows: Chapter 1 gives the background and some basic information. Chapter 2 presents the demands and necessary conditions that take precedence when adapting the plant to the local conditions, construction, operation and closure. Chapter 3 is a general description of the area, its infrastructure and the specific sites that have been studied. Chapters 4-5 describe the design of the plant for the two chosen sites. Chapter 6 gives a review of data for the plant, and Chapter 7 'References' is the last part of the main document. The appendices A-I give brief information on the general, non-site specific, parts of the plant, e.g. buildings, life cycle, system, operation and organization

  12. Estrutura populacional de Pinus elliottii em áreas de regeneração florestal em Juiz de Fora, MG Population structure of Pinus elliottii in areas of forest regeneration in Juiz de Fora, MG, Brazil

    Directory of Open Access Journals (Sweden)

    Talita Aperibense Menon

    2012-12-01

    Full Text Available Plantas do gênero Pinus são conhecidas pelo potencial de invasão biológica. O Campus da Universidade Federal de Juiz de Fora (UFJF foi arborizado na década de 1960 com o plantio massivo de Pinus elliottii, e hoje a espécie está alastrada. Neste estudo, realizado no Campus da UFJF, Juiz de Fora, MG foi analisada a estrutura populacional da espécie em dois ambientes de regeneração florestal: aberto (pastagem abandonada e fechado (floresta secundária. Partiu-se da premissa que o ambiente aberto apresentaria uma população mais estruturada, pela preferência da espécie por áreas abertas. A amostragem foi por parcelas aleatórias (15 parcelas de 5 m x 5 m em cada ambiente, onde foram medidos todos os indivíduos da espécie (árvores: DAP ≥ 5 cm; arvoretas: DAP 0,05 com as variáveis ambientais indicou que a competição por recursos com a vegetação nativa não é um problema aparente para a permanência da espécie. Plants of the genus Pinus are known worldwide by biological invasion potential. In the 1960s there were massive plantations of Pinus elliottii in the Campus of Juiz de Fora University, and nowadays the species is widespread. This study analyzed the species population structure in two distinct forest regeneration environments: open area (abandoned pasture and closed-canopy (secondary forest on the campus of UFJF, Juiz de Fora, MG, Brazil. The hypothesis were that the open environment would present a better structured population, due to the preference of species for open areas. Random plots were allocated (15 plots of 5 m x 5 m in each environment, and all individuals of the species (trees: dbh . 5 cm, saplings, dbh 0.05 with environmental variables showed that competition for resources within the local vegetation is not an apparent problem for the permanence of species.

  13. Developing a Vital Area Identification in Nuclear Power Plants Using PSA Results

    International Nuclear Information System (INIS)

    Kim, Kilyoo; Jung, Woosik; Yang, Juneon

    2008-01-01

    After 9/11, a physical protection and vital area identification (VAI) became important. In the well known VAI methodology, fault trees (FTs) to mitigate the initiating events caused by sabotage or terror should be prepared for the VAI. The KAERI VAI method is to develop FTs by using Probabilistic Safety Assessment (PSA) and Risk Informed In-service Inspection (RI-ISI) results. In this paper, how to develop a VAI model by using PSA and RI-ISI results is described

  14. Biological studies in the sea area surrounding the Loviisa nuclear power plant in the year 1977

    International Nuclear Information System (INIS)

    Ilus, Erkki

    1980-03-01

    Observations of rise in water temperature caused by the plant's cooling water were made in a large area of Haestholmsfjaerden. The mean temperatures during the growth period and summer months were on average of the same magnitude as those in the 1970s, except very close to the outlet, where the mean temperatures were clearly increased by the cooling water. The salinity of the water increased to exceptionally high values in September in the whole study area. Salinities even exceeding 0.6% were measured in the surface water of Haestholmsfjaerden. The concentrations of total phosphorus and total nitrogen were clearly above the level found earlier in the area, but the increase in the nutrient level was similar at all stations (including the reference station at Pernajanlahti). The amount of oxygen in the bottom water of the deep part of Haestholmsfjaerden in late summer was lower than in previous years (1.2 ml/l, 14% of the saturation level). The phytoplankton biomass spring maximum was greater at all stations than in 1974-76. Differences in species composition were small compared with earlier years. The amounts of chlorophyll a during the spring maximum were higher in 1977 than in 1975-76. The level of phytoplankton primary production in the whole study area was lower in 1977 than in the 1970s on average. The annual production at station nearest the outlet, was about 10% greater than at station situated in the middle of Haestholmsfjaerden, owing to higher production in the middle of summer. No important differences in 'in vitro' primary production were observed between sampling places near the water intake and the outlet and the values were of the same magnitude as in 1976. (T.V.)

  15. Wide area tracking method for augmented reality supporting nuclear power plant maintenance work

    International Nuclear Information System (INIS)

    Ishii, Hirotake; Yan, Weida; Yang, Shou-feng; Shimoda, Hiroshi; Izumi, Masanori

    2010-01-01

    A new fiducial marker for augmented reality was designed along with a method that recognizes the markers captured by a camera and calculates the relative position and orientation between the markers and the camera. These markers can be used at both long and short distances without increasing their number in the environment. Results of the experimental evaluation show that the new marker can be used in a larger area than legacy markers such as square markers and circular markers. (author)

  16. Dependence of the specific surface area of the nuclear fuel with the matrix oxidation

    International Nuclear Information System (INIS)

    Gomez, F.; Quinones, J.; Iglesias, E.; Rodriguez, N.

    2008-01-01

    This paper is focused on the study of the changes in the specific surface area measured using BET techniques. The objective is to obtain a relation between this parameter and the change in the matrix stoichiometry (i.e., oxidation increase). None of the actual models used for extrapolating the behaviour of the spent fuel matrix under repository conditions have included this dependence yet. In this work the specific surface area of different uranium oxide were measured using N 2 (g) and Kr(g). The starting material was UO 2+x (s) with a size powder distribution lower than 20 μm. The results included in this paper shown a strong dependence on specific surface area with the matrix stoichiometry, i.e., and increase of more than one order of magnitude (SUO 2 = 6 m 2 *g -1 and SU 3 O 8 = 16.07 m 2 *g -1 ). Furthermore, the particle size distribution measured as a function of the thermal treatment done shows changes on the powder size related to the changes observed in the uranium oxide stoichiometry. (authors)

  17. Local area distribution of fallout radionuclides from Fukushima Daiichi Nuclear Power Plant determined by autoradiography analysis

    International Nuclear Information System (INIS)

    Sakamoto, Fuminori; Ohnuki, Toshihiko; Kozai, Naofumi; Igarashi, Shosuke; Yamasaki, Shinya; Yoshida, Zenko; Tanaka, Shunichi

    2012-01-01

    The environmental behavior of radioactive Cs in the fallout from the accident of the Fukushima Daiichi Nuclear Power Plant has been studied by measuring its spatial distribution on/in trees, plants, and surface soil beneath the plants using autoradiography analysis. The results of autoradiography analysis showed that radioactive Cs was distributed on the branches and leaves of trees that were present during the accident and that only a small fraction of radioactive Cs was transported to new branches and leaves grown after the accident. Radioactive Cs was present on the grass and rice stubble on the soils, but not in the soils beneath the grass and rice stubble, indicating that the radioactive Cs was deposited on the grass and the rice plant. In addition, the ratio of the radioactive Cs that penetrated into the soil layer by weathering was very small two months after the accident. These results indicate that trees and other plants are the reservoir of the fallout Cs and function to retard the fallout Cs migration with rain water. (author)

  18. Death analysis of residents in an area of twenty kilometers around Qinshan nuclear power station

    International Nuclear Information System (INIS)

    Ma Mingqiang; Lu Zhunrong; Zheng Wen; Sun Peizhi

    2001-01-01

    Objective: To set up a data bank for residents health condition 20 kilometers within around Qinshan nuclear power station. Methods: Combining with retrospective investigation, the relevant data were acquired from medical certification for resident's death reported by all local disease surveillance. Results: The mortality rate of these residents from 1988 to 1999 was 6.92%. The first course of mortality was diseases of respiratory system, the second of circulatory system, and the third was malignant tumor. The first 5 death causes among all male and female persons were diseases of respiratory system and circulatory system, malignant tumor, injuries and poisoning, diseases of digestive system. The mortality rate for malignant tumor was 121.33/100000 (the standard death rate is : 100.13/100000), and liver cancer was the first death cause, while lung and stomach cancers, the second and the third, respectively. The main death causes in juvenile and youth was leukemia, but liver cancer and lung cancer were the main courses of death in the middle-aged, and in old people, lung and liver cancers. Conclusion: The chronic non-infectious diseases in respiratory system, circulatory system etc, are the major death causes in the residents, the mortality rate for malignant tumor in them is lower than that reported by provincial disease surveillance station

  19. An analysis of the death of main malignant tumor of inhabitants in nuclear power station area

    International Nuclear Information System (INIS)

    Ma Mingqiang; Lu Zunrong; Zheng Wen; Chen Guopei

    1997-01-01

    The authors reported the analysis on the death millimeter situation of inhabitants living around one nuclear power station during pre-operation period of 1988∼1991 and 1992∼1993 operating period. Total surrey population in six years is 2585521 person year, gross malignant tumour death rate is 116.38 x 10 -5 , calibrated death rate is 97.04 x 10 -5 , of which male is 129.20 x 10 -5 , female 65.39 x 10 -5 . An extremely significant difference is noted statistically. Individual annual death rate is 112.00 x 10 -5 , 120.15 x 10 -5 , 125.17 x 10 -5 , 116.45 x 10 -5 , 105.42 x 10 -5 and 119.16 x 10 -5 respectively. The statistical difference was no marked. The highest mortality rate is from the liver cancer, then from the cancer of the lung, of the stomach and of the esophagus. 94 cases died from leukemia with a mortality rate of 3.64 x 10 -5 , and 5 died from thyroid carcinoma, accounting for 0.17% of the total death cases

  20. Stakeholder involvement in the management of rural areas following a nuclear accident: the farming network

    International Nuclear Information System (INIS)

    Mercer, J.; Nisbet, A.F.

    2002-01-01

    The importance of the participation of stakeholders in the formulation of strategies for maintaining agricultural production and food safety following a nuclear accident, has been successfully demonstrated by the Agriculture and Food Countermeasures Working Group (AFCWG). This group was set up in the UK by the National Radiological Protection Board (NRPB) and the then Ministry of Agriculture, Fisheries and Food in 1997 (Nisbet and Mondon, 2001). Before this time stakeholder organisations had not collectively considered the implications of contamination of the foodchain in the event of an accidental release of radioactivity. With funding from the European Commission (EC) the UK approach to stakeholder engagement is being taken forward on a European basis during the period 2000-2004 through a project given the acronym FARMING (Food and Agriculture Restoration Management Involving Networked Groups). The overall objective of this project is to create a network of stakeholder working groups in 5 member states (UK, Belgium, Finland, France and Greece) to assist in the development of robust and practicable strategies for restoring and managing contaminated agricultural land and food products in a sustainable way. The initial intention was to involve at least 50 individual stakeholders

  1. Prolonged Living as a Refugee from the Area Around a Stricken Nuclear Power Plant Increases the Risk of Death.

    Science.gov (United States)

    Tanaka, Reiichiro

    2015-08-01

    Although it is well known that the Great East Japan Earthquake (March 11, 2011) resulted in a large number of disaster-related deaths, it is not common knowledge that the number of disaster-related deaths continues to increase, even four years after the earthquake, in Fukushima Prefecture, where the nuclear power plant accident occurred. There has been a lack of a minute and critical analysis for the causes for this continuous increase. In this report, the causes for the increase in disaster-related deaths in Fukushima Prefecture were analyzed by aggregating and comparing multiple data released by public organizations (the Reconstruction Agency, the National Police Agency, and Fukushima Prefecture), which may also have implications for developing response strategies to other disasters. The disaster-related death rate, the dead or missing rate, and the refugee rate (the number of disaster-related deaths, dead or missing persons, and refugees per 1,000 people) in each prefecture in stricken areas, and also each city, county, town, and village in Fukushima Prefecture, were calculated and compared with each other. The populations which were used for the calculation of each death rate in the area were based on the number of dead victims who had lived in the area when the earthquake occurred, regardless of where they were at the time of their death. The disaster-related death rate was higher than the dead or missing rate in the area around a stricken nuclear power plant in Fukushima Prefecture. These areas coincide exactly with the Areas under Evacuation Orders because of unsafe radiation levels. The external and internal radiation doses of most of the victims of the Great East Japan Earthquake have appeared not to be so high to harm their health, until now. The psychological stress associated with being displaced from one's home for a long time with an uncertain future may be the cause for these disaster-related deaths. There is an urgent need to recognize refugees

  2. Nuclear methods used to compare air pollution in a city and a pollution-free area

    International Nuclear Information System (INIS)

    Shani, G.; Haccoun, A.

    1976-01-01

    A comparison study was made between city pollution and open-area pollution in order to be able to distinguish between air pollution whose source is urban activity (i.e. industry, transportation, etc.) and that in an area free of man's activities. The comparison was made between Beersheba, a city in the south of Isreal, and a spot in the desert, 40 km south of the city. The meteorological conditions at the two places are the same, and it is reasonable to assume that the background pollution (the dust that covers the area), is the same in both places. Neutron activation analysis was used for pollution detection; it is clear that certain elements cannot be detected by this means, though they may be known to exist in the air; hence, certain trace elements of the dust could be detected, but not, for example, the major components such as Ca and Si. The results are classified as typical urban pollutants and non-urban pollutants. Weather condition dependence was also investigated. The major source of urban pollution in Beersheba is bromine, which exists in the air in large quantities. The other urban pollutants are Zn, Cr, and Sb; these elements are found mainly in the city, in smaller quantities than bromine. The concentration of these elements is greatly reduced at night due to cessation of work in industry and reduced vehicular movement. The effect of weather and a seasonal dependence are clearly indicated (e.g. when the wind velocity increases and its direction is from the east, pollution in Beersheba rises). At the end of the winter the air is clearer than at the end of the summer. (author)

  3. Social living environment of population in the surveillance area of Rivne nuclear power plant

    International Nuclear Information System (INIS)

    Prilipko, V.A.; Ozerova, Yu.Yu.; Morozova, M.M.; Shevchenko, K.K.

    2014-01-01

    The list of benefits and compensations associated with living near the functioning NPP needs improvement and coordination with opinion of local communities. Their implementation at that needs a permanent information support. Some links are established between areas that are important in shaping of social feelings and assessment of environmental situation, perception of radiation situation, possibility of socio-political, man-made and natural emergencies. The more confident respondents in welfare of ecological state of residence, the higher level is in their social comfort

  4. Plutonium and uranium in human bones from areas surrounding the Semipalatinsk nuclear test site.

    Science.gov (United States)

    Yamamoto, Masayoshi; Hoshi, Masaharu; Sakaguchi, Aya; Shinohara, Kunihiko; Kurihara, Osamu; Apsalikov, Kazbek N; Gusev, Boris I

    2006-02-01

    To evaluate the present levels of 239,240Pu and U in residents living near the Semipalatinsk nuclear test site, more than 70 bone samples were obtained at autopsy. The subjects ranged in age from 30 to 86 years (mean 59.3+/-12.9). Most of the samples consisted of victims who died of various diseases. Plutonium and U were radiochemically separated and determined by alpha-ray spectrometry. The mean concentrations of 239,240Pu and 238U observed were 0.050+/-0.041 mBq/g-ash (vertebrae 71, long-bones 18) and 0.28+/-0.13 mBq/g-ash (22.8+/-10.6 microg U/kg-ash) (vertebrae 58, long bones 16), respectively. The present 239,240Pu levels were within the range found for human bone samples from other countries due solely to global fallout in the early 1980s. The average U concentration was close to the estimate (mean 22.5 microg U/kg-ash) for the UK, and about 10 times higher than those estimated for residents in New York City and Japan. By assuming that the average concentration of 239,240Pu in bone samples is the value at 45 years after instantaneous inhalation in 1955, the initial total intake and the effective dose for 45 years were estimated as 10 Bq and 0.2 mSv, respectively. The annual intake of total U (234,235,238U) and its effective dose for 60 years were estimated as 30 Bq for adult and 0.1 mSv, respectively, for chronic ingestion.

  5. Methodological proposal for identification and evaluation of environmental aspects and impacts of nuclear facilities of IPEN, Sao Paulo, SP, Brazil: a case study applied to the Nuclear Fuel Center; Proposta metodologica para a identificacao e avaliacao de aspectos e impactos ambientais em instalacoes nucleares do IPEN: estudo de caso aplicado ao Centro do Combustivel Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Mattos, Luis Antonio Terribile de

    2013-07-01

    This work presents an application of Failure Mode Effect Analysis (FMEA) to the process of identification of environmental aspects and impacts as a part of implementation and maintenance of an Environmental Management System (EMS) in accordance with the NBR ISO 14001 standard. Also, it can contribute, as a complement, to the evaluation and improvement of safety of the installation focused. The study was applied to the Nuclear Fuel Center (CCN) of Nuclear and Energy Research Institute (IPEN), situated at the Campus of University of Sao Paulo, Brazil. The CCN facility has the objective of promoting scientific research and of producing nuclear fuel elements for the IEA-R1 Research Reactor. To identify the environmental aspects of the facility activities, products, and services, a systematic data collection was carried out by means of personal interviews, documents, reports and operation data records consulting. Furthermore, the processes and their interactions, failure modes, besides their causes and effects to the environment, were identified. As a result of a careful evaluation of these causes it was possible to identify and to classify the major potential environmental impacts, in order to set up and put in practice an Environmental Management System for the installation under study. The results have demonstrated the validity of the FMEA application to nuclear facility processes, identifying environmental aspects and impacts, whose controls are critical to achieve compliance with the environmental requirements of the Integrated Management System of IPEN. It was demonstrated that the methodology used in this work is a powerful management tool for resolving issues related to the conformity with applicable regulatory and legal requirements of the Brazilian Nuclear Energy Commission (CNEN) and the Brazilian Institute of Environment (IBAMA). (author)

  6. Anew applied approach for dynamic air quality simulation in industrial and nuclear polluted areas

    International Nuclear Information System (INIS)

    Abdel Aal, M.M.; Tawfik, F.S.; Ramadan, A.

    2002-01-01

    Air pollution transport and diffusion and diffusion models are the only tools for inferring a quantitative deterministic relation between pollutant emissions and ambient air quality. This study deals with the simulation of pollutants transport and diffusion at shobra El-Khemia, where this site is considered the most public and polluted area in greater cairo city. The results of such a model matches to a great extent with the measured ones because it takes into consideration dry and wet deposition and first-order reaction chemistry. Specified time period was chosen to simulate the pollutant of sulphur dioxide over the studied area. The meteorological parameters were measured to calculate the hourly stability classes and height of mixing layer. Also, the concentration of sulphur dioxide was continuously measured at the faculty of agriculture to compare between its values and the estimated results. Yen's factory was taken to be the source of pollutant, thus, the emission rate and concentration of sulphur dioxide were measured at the top of their stacks. The analysis of estimated results provided that, at neutral condition, there was only one maximum concentration while at unstable conditions, there were more than one maximum concentration. The maximum estimated average hourly concentration and the average daily measuring concentration at shoubra Elkheima were within the air quality limit of egyptian law no. 4 (1994). The measured values are greater than the estimated ones by 15 to 30 % . This could be attributed to the effect of transportation, which was neglected during the application of model

  7. Metrological aspects in estimating of radiation dose in patients of nuclear medicine; Aspectos metrologicos na estimativa da dose efetiva de pacientes em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ruzzarin, Anelise

    2015-06-01

    In order to investigate the performance of routine measurements in nuclear medicine services, LNMRI/IRD has been conducting, since 1998, a comparison program of activity measurements of radiopharmaceuticals administered to patients in nuclear medicine. Correction factors are determined from the result of performance analysis in order to determine with better accuracy the activity to be administered to the patients. The present study shows how the correction factor is determined by the ratio between the measurement of the activity at the nuclear medicine center and the activity determined by the LNMRI, which is adopted as reference. It is essential that the dose calibrator be calibrated with standards traceable to national metrology laboratories, so that the activity administered to the patient is neither greater nor smaller than the appropriate value. The corrected values of the activities can be used to calculate with greater accuracy the effective doses received by the patients as well as the risk of cancer. Information related to radiopharmaceuticals and administered activities, type of exams and patient data of three Brazilian hospitals were collected for 1496 adults and 134 children submitted to diagnostic exams employing {sup 99m}Tc and {sup 131}I. Results showed up to a considerable difference between the administered activity and the corrected activity until 30% and 13% above the reference value, respectively, for the {sup 131}I and {sup 99m}Tc was detected. The consequences of these differences were not very critical in this study since the activity measured in dose calibrator before administration was lower than the corrected activity, thus causing a lower effective dose in patients. However, this reduction in activity may result in problems in obtaining the image and consequently, failure diagnosis, delaying correct diagnosis. On the other hand, the overestimation would be worse, mainly in therapeutic applications, because an unnecessarily high absorbed

  8. Quality assessment of radiopharmaceuticals in nuclear medicine services at Northeast states, Brazil; Avaliacao da qualidade de radiofarmacos em servicos de medicina nuclear de estados da regiao nordeste

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, Wellington Gomes de

    2012-07-01

    The radiopharmaceuticals are used in the field nuclear medicine services (NMS) as tracer in the diagnoses and treatment of many diseases. Radiopharmaceuticals used in nuclear medicine and usually have a minimum of pharmacological effect. The procedures for labelling Radiopharmaceuticals should be observed in order to minimize risks to patients, employees and individuals from the public, and to be administered in humans, must be sterile and free of pyrogens and possess elements all measures of quality controls required a conventional drug. The 'Agencia Nacional de Vigilancia Sanitaria (ANVISA)' in its 'Resolucao de Diretoria Colegiada' (RDC) No. 38 of June 4{sup th} 2008, decided that the NMS must perform quality control in the generators eluate and radiopharmaceuticals according to recommendations of manufacturers and scientific evidence accepted by ANVISA. Thus, this study proposes to evaluate the quality of the generator {sup 99M}o-{sup 99m}Tc eluate and radiopharmaceuticals labeled with {sup 99m}Tc used in most NMS of some states in the Northeast, in relation to radionuclide, chemical, radiochemical purity and pH and promote the inclusion of procedure for quality control of radiopharmaceuticals in routine NMS. The results show that 90% radionuclidic purity, 98.2% purity chemical and radiochemical purity of 46% and 100% of the eluates are in agreement with international pharmacopoeias; already radiopharmaceuticals showed 82.6% purity and all radiochemical pH values are also in accordance with international pharmacopoeias. Even with so many positive results, staff the majority of MNS was not able to perform the quality control of the eluates and radiopharmaceuticals. Showing the importance of implementing of quality control programs of the eluates and radiopharmaceuticals in nuclear medicine. (author)

  9. Quality assessment of radiopharmaceuticals in nuclear medicine services at Northeast states, Brazil; Avaliacao da qualidade de radiofarmacos em servicos de medicina nuclear de estados da regiao nordeste

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, Wellington Gomes de

    2012-07-01

    The radiopharmaceuticals are used in the field nuclear medicine services (NMS) as tracer in the diagnoses and treatment of many diseases. Radiopharmaceuticals used in nuclear medicine and usually have a minimum of pharmacological effect. The procedures for labelling Radiopharmaceuticals should be observed in order to minimize risks to patients, employees and individuals from the public, and to be administered in humans, must be sterile and free of pyrogens and possess elements all measures of quality controls required a conventional drug. The 'Agencia Nacional de Vigilancia Sanitaria (ANVISA)' in its 'Resolucao de Diretoria Colegiada' (RDC) No. 38 of June 4{sup th} 2008, decided that the NMS must perform quality control in the generators eluate and radiopharmaceuticals according to recommendations of manufacturers and scientific evidence accepted by ANVISA. Thus, this study proposes to evaluate the quality of the generator {sup 99M}o-{sup 99m}Tc eluate and radiopharmaceuticals labeled with {sup 99m}Tc used in most NMS of some states in the Northeast, in relation to radionuclide, chemical, radiochemical purity and pH and promote the inclusion of procedure for quality control of radiopharmaceuticals in routine NMS. The results show that 90% radionuclidic purity, 98.2% purity chemical and radiochemical purity of 46% and 100% of the eluates are in agreement with international pharmacopoeias; already radiopharmaceuticals showed 82.6% purity and all radiochemical pH values are also in accordance with international pharmacopoeias. Even with so many positive results, staff the majority of MNS was not able to perform the quality control of the eluates and radiopharmaceuticals. Showing the importance of implementing of quality control programs of the eluates and radiopharmaceuticals in nuclear medicine. (author)

  10. A diagnostic of the strategy employed for communicating nuclear related information to Brazilian communities around uranium mining areas

    International Nuclear Information System (INIS)

    Ferrari Dias, Fabiana; Tirollo Taddei, Maria H.

    2008-01-01

    This paper presents a diagnostic of the strategy used by the Brazilian uranium mining industry to communicate nuclear related information to communities around a mining area. The uranium mining industry in Brazil, which is run by the government, has been concerned with communication issues for quite some time. The need to communicate became more apparent after new mining operations started in the Northern region of Brazil. The fact that the government does not have a clear communication guideline made the operators of the uranium mining industry aware of the increasing demand for establishment of a good relationship with several types of Stake holders as well as employment of personnel with experience in dealing with them. A diagnostic of the current communication situation in Brazil and an analysis of the approaches over the past years was done through interviews with employees of the mining industry and review of institutional communication materials. The results were discussed during a Consultant's Meeting organized by the IAEA 's Seibersdorf Laboratory in October 2007. The output of the meeting included an overview of modern communication strategies used by different countries and a suggestion for new uranium mining operations in developing or under developed countries. The strategy for communicating nuclear related information to Brazilian communities varied according to the influence of different Stake holder groups. One initiative worth mentioning was the creation of a Mobile Nuclear Information Thematic Room, which was installed in several locations. This project was seen as one of the main tools to relate to community. Many Stake holders were identified during the diagnostic phase in preparation for the IAEA 's meeting on communication strategy: children, NGOs (Non Government Organizations), local churches, media and internal Stake holders, among others. An initial evaluation showed that the perception of a neighbouring community regarding an uranium

  11. Adaptation of the dynamic model for radiological assessment of nuclear accident in rural area under conditions of tropical climate

    International Nuclear Information System (INIS)

    Vinhas, Denise Martins

    2004-01-01

    Following an accidental release of radionuclides to the atmosphere that leads to the contamination of large areas, a detailed and fast methodology to assess the prognosis of public exposure is needed, in order to estimate radiological consequences and propose and optimize decisions related to the protection of the public. The model ECOSYS has been chosen to integrate the SIEM, the Integrated Emergency System developed by IRD/CNEN, to assess the doses at the short, medium and long term to the public after an accidental contamination of rural areas. The objective of this work is to perform the adaptation of the model ECOSYS to be used in Brazil to assess public exposure and support decision processes regarding the implementation of protective measures but also to guide the need for studies and research aiming to improve the adequacy of estimates to the actual Brazilian situation. The area select for reference to this work consists on the 50 km radius area surrounding the Brazilian nuclear power plants, located at Angra dos Reis County, in the state of Rio de Janeiro. The methodology included the definition of criteria to select agricultural cultures and animals to be simulated, taking into account both the availability of the production at the selected area and the relevance of the food to the population regional diet. Radionuclides included in this study were 137 Cs, 90 Sr and 131 I. A large survey has been performed to gather data related to both agricultural practices and behavior of radionuclides in the selected agricultural-systems. The results of simulation indicated the relevance of the knowledge of local aspects on the estimated doses. Important factors included the kind of products produced, seasonality, agricultural practices, animals feed practices, kind of soil, and ingestion habits of the population. (author)

  12. Siting of Nuclear Power Plants in Metropolitan Areas. Estimation of Population Doses due to Accidental Release of Fission Products

    Energy Technology Data Exchange (ETDEWEB)

    Bresser, H. [Technischer Ueberwachungs-Verein Rheinland E.V., Cologne (Germany); Schwarzer, W. [Institut fuer Reaktorsicherheit der Technischen Ueberwachungs-Vereine E.V., Cologne (Germany)

    1967-09-15

    The safety of large nuclear power plants in heavily populated areas depends entirely on engineered safeguards. An assessment of their reliability and effectiveness will have to play a major role in any safety analysis of such a plant, and this assessment will have to be made on the basis of the radiological burden to the environment - in terms of individual dose and a population dose - which can be accepted as tolerable in case of a severe accident. The calculation of the dispersion of fission products in the atmosphere, which links the radiological burden to the release of radioactivity, should be modified. The fact that distance factors, aside from a comparably small exclusion area, can no longer be taken into account suggests the introduction of the parameter ''population density'' and an extensive use of the man-rem concept. In this connection the time history of the release and the influence of variations of wind directions lose their importance. The authors have carried out calculations of the population dose, which could be received in a metropolitan area as a consequence of a severe reactor accident, using population densities, height of release above ground and generalized meteorological data as the main parameters. The results of these calculations are used as a basis for an assessment of the performance requirements of the engineered safeguards system, and the relative importance of different components of this system is discussed. (author)

  13. Aerial radiological survey of the Grand Gulf Nuclear Station and surrounding area, Port Gibson, Mississippi. Date of survey: March 1982

    International Nuclear Information System (INIS)

    Ballatore, L.A.; Hilton, L.K.

    1982-09-01

    An aerial radiological survey was performed from 11 to 20 March 1982 over a 260-square-kilometer area centered on the Grand Gulf Nuclear Station at Port Gibson, Mississippi (the station was not yet in operation at the time of the survey). All gamma ray data were collected by flying east-west lines spaced 152 meters apart at an altitude 91 meters above ground level. Processed data showed that all gamma rays detected within the survey area were those expected from naturally occurring terrestrial background emitters. Count rates obtained from the aerial platform were converted to exposure rates at 1 meter above the ground and are presented in the form of an isoradiation contour map. The observed exposure rates were between 5 and 13 microroentgens per hour (μR/h), with most of the area ranging from 9 to 10 μR/h. These values include an estimated cosmic ray contribution of 3.6 μR/h. The exposure rate obtained from soil samples and ionization chamber measurements taken from within the survey site displayed positive agreement with the aerial data

  14. Aerial radiological survey of the Palo Verde Nuclear Generating Station and surrounding area, Wintersburg, Arizona. Date of survey: November 1982

    International Nuclear Information System (INIS)

    Semmler, R.A.

    1984-01-01

    An aerial survey of terrestrial gamma radiation was performed during the period 4 November through 15 November 1982 over a 16-kilometer by 16-kilometer (10-mile by 10-mile) area approximately centered on the Palo Verde Nuclear Generating Station near Wintersburg, Arizona. Gamma radiation spectral data were collected while flying a helicopter over a regular pattern of parallel lines spaced 150 meters (500 feet) apart at an altitude of 90 meters (300 feet). All radiation measurements taken at the nominal flight altitude were corrected for altitude variations, cosmic radiation, and helicopter background to generate exposure rates from terrestrial sources extrapolated to 1 meter above ground level. The data are presented as isoradiation contour maps. The average terrestrial radiation levels fall between 8 and 14 microrentgens per hour (μR/h). All gamma radiation detected within the survey area was associated with naturally occurring radionuclides. Direct ground-based measurements at 1 meter height were also taken at four scattered sites within the survey area. These values agree with the contour intervals determined from the aerial measurements and differ from the mean value of adjacent contours by no more than 10%. 6 references, 5 figures, 2 tables

  15. Disposal of waste from the cleanup of large areas contaminated as a result of a nuclear accident

    International Nuclear Information System (INIS)

    1992-01-01

    The report provides an overview of the methodology and technology available to load, transport and dispose of large volumes of contaminated material arising from the cleanup of areas after a nuclear accident and includes data on the planning, implementation, management and costing of such activities. To demonstrate the use of this information, three cleanup and disposal scenarios are examined, ranging from disposal in many small mounds or trenches within the contaminated area to disposal in a large facility away from the plant. As in the two companion reports, it is assumed that the population has been evacuated from the affected area. The report reviews the generic types of low level radioactive waste which are likely to arise from such a cleanup. The report does not deal with the recovery and disposal of intermediate and high level radioactive material on or near the plant site. This material will have to be recovered, packaged, transported and stored on-site or disposed of at an appropriate facility. These operations should be done by specialist teams using shielded or remotely operated equipment. Also not included are methods of in situ stabilization of contamination, for example ploughing to bury the top contaminated layer at a suitable depth. These techniques, which are likely to be widely used in part of the evacuated are, are discussed in IAEA Technical Reports Series No. 300, Vienna, 1989. 50 refs, 18 figs, 4 tabs

  16. Nuclear spectroscopy - maximum attainable accuracy in the calculation of peak area

    International Nuclear Information System (INIS)

    Supian Samat; Evans, C.J.

    1989-01-01

    The general principles are discussed for the analysis of a peak of arbitrary shape (including the case of multiple peaks) superimposed on a background of arbitrary shape. Application of these principles to the case of a small Gaussian peak on a flat background gives a rule for determining how many channels should be included in the analysis so that accuracy should not be lost, and how many channels in the background should be included in estimating the standard error in the peak area. It is shown that the use of an approximate method of analysis may lead to a significant loss of accuracy, and to a significant over-estimation of the standard error. (author)

  17. Fire safety assessment for the fire areas of the nuclear power plant using fire model CFAST

    International Nuclear Information System (INIS)

    Lee, Yoon Hwan; Yang, Joon Eon; Kim, Jong Hoon

    2005-03-01

    Now the deterministic analysis results for the cable integrity is not given in case of performing the fire PSA. So it is necessary to develop the assessment methodology for the fire growth and propagation. This document is intended to analyze the peak temperature of the upper gas layer using the fire modeling code, CFAST, to evaluate the integrity of the cable located on the dominant pump rooms, and to assess the CCDP(Conditional Core Damage Probability) using the results of the cable integrity. According to the analysis results, the cable integrity of the pump rooms is maintained and CCDP is reduced about two times than the old one. Accordingly, the fire safety assessment for the dominant fire areas using the fire modeling code will capable to reduce the uncertainty and to develop a more realistic model

  18. Radiation monitoring around United States nuclear test areas, calendar year 1989

    Energy Technology Data Exchange (ETDEWEB)

    1990-05-01

    This report describes the Offsite Radiation Safety Program conducted during 1989 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory-Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels, and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether the testing is in compliance with existing radiation protection standards, and to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of both animals and humans. To implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any release of radioactivity, personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each test. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to NTS activities. Trends were evaluated in the Noble Gas and Tritium, Milk Surveillance, TLD, and PIC networks, and the Long-Term Hydrological Monitoring Program. 35 refs., 68 figs., 32 tabs.

  19. Radiation monitoring around United States nuclear test areas, calendar year 1989

    International Nuclear Information System (INIS)

    1990-05-01

    This report describes the Offsite Radiation Safety Program conducted during 1989 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory-Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels, and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether the testing is in compliance with existing radiation protection standards, and to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of both animals and humans. To implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any release of radioactivity, personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each test. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to NTS activities. Trends were evaluated in the Noble Gas and Tritium, Milk Surveillance, TLD, and PIC networks, and the Long-Term Hydrological Monitoring Program. 35 refs., 68 figs., 32 tabs

  20. Seismic stability of the survey areas of potential sites for the deep geological repository of the spent nuclear fuel

    Directory of Open Access Journals (Sweden)

    Kaláb Zdeněk

    2017-07-01

    Full Text Available This paper deals with the seismic stability of the survey areas of potential sites for the deep geological repository of the spent nuclear fuel in the Czech Republic. The basic source of data for historical earthquakes up to 1990 was the seismic website [10]. The most intense earthquake described occurred on September 15, 1590 in the Niederroesterreich region (Austria in the historical period; its reported intensity is Io = 8-9. The source of the contemporary seismic data for the period since 1991 to the end of 2014 was the website [11]. It may be stated based on the databases and literature review that in the period from 1900, no earthquake exceeding magnitude 5.1 originated in the territory of the Czech Republic.

  1. Hydrogeological modelling of the eastern region of Areco river locally detailed on Atucha I and II nuclear power plants area

    International Nuclear Information System (INIS)

    Grattone, Natalia I.; Fuentes, Nestor O.

    2009-01-01

    Water flow behaviour of Pampeano aquifer was modeled using Visual Mod-flow software Package 2.8.1 with the assumption of a free aquifer, within the region of the Areco river and extending to the rivers of 'Canada Honda' and 'de la Cruz'. Steady state regime was simulated and grid refinement allows obtaining locally detailed calculation in the area of Atucha I and II Nuclear power plants, in order to compute unsteady situations as the consequence of water flow variations from and to the aquifer, enabling the model to study the movement of possible contaminant particles in the hydrogeologic system. In this work the effects of rivers action, the recharge conditions and the flow lines are analyzed, taking always into account the range of reliability of obtained results, considering the incidence of uncertainties introduced by data input system, the estimates and interpolation of parameters used. (author)

  2. Variation of radiocesium concentrations in cedar pollen in the Okutama area since the Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Tsuruoka, H.; Inoue, K.; Sakano, Y.; Hamada, M.; Shimizu, H.; Fukushi, M.

    2015-01-01

    Due to releases of radionuclides in the Fukushima Daiichi Nuclear Power Plant accident, radiocesium ( 134 Cs and 137 Cs) has been incorporated into large varieties of plant species and soil types. There is a possibility that radiocesium taken into plants is being diffused by pollen. Radiocesium concentrations in cedar pollen have been measured in Ome City, located in the Okutama area of metropolitan Tokyo, for the past 3 y. In this research, the variation of radiocesium concentrations was analysed by comparing data from 2011 to 2014. Air dose rates at 1 m above the ground surface in Ome City from 2011 to 2014 showed no significant difference. Concentration of 137 Cs contained in the cedar pollen in 2012 was about half that in 2011. Between 2012 and 2014, the concentration decreased by approximately one-fifth, which was similar to the result of a press release distributed by the Japanese Ministry of Agriculture, Forestry and Fisheries. (authors)

  3. Study of virtual reality application in training programs on nuclear technology; Estudo da aplicacao de realidade virtual em programas de treinamento sobre tecnologia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Pastura, Valeria da Fonseca e Silva

    2016-07-01

    The activities developed in the units which organize the National Nuclear Energy Commission (CNEN) are present in various sectors of the Brazilian society, being them in medicine, industry, electricity generation, mining, and among the others. Based on the assumption that the employees are CNEN's mayor differential and the training programs play an important role in the process of organizational development, because they align the professionals with the strategies of the institution properly. Focusing on these matters, this master's thesis aimed to evaluate the training programs which are applied by CNEN, in order to propose and evaluate the use of the Virtual Reality (VR) expertise as a new method to be applied in the training programs. To accomplish this purpose, we performed two methodological approaches through questionnaires. And from the analysis of the results obtained, we could realize that there was no efficient training program which is systematically applied by CNEN, and the use of the RV technique improves the training programs in the understanding of themes whose assimilation is challengeable, such as those related to nuclear power. In this sense, for a better functional performance, the training programs adopted by CNEN must be structured so as to enable the development of each server's skills as well as abilities and, it is actually hoped that the virtual reality tools could be inserted in these programs to pursue only this purpose. (author)

  4. Implementation of a metrology national network for radionuclides used in nuclear medicine; Implementacao de uma rede nacional de metrologia de radionuclideos utilizados em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Santos, J.A. dos; Lopes, R.T. [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-Graduacao de Engenharia (COPPE)], e-mail: joyra@ird.gov.br, e-mail: ricardo@lin.ufrj.br; Iwahara, A.; Tauhata, L. [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Lab. Nacional de Metrologia das Radiacoes Ionizantes (LNMRI)], e-mail: iwahara@ird.gov.br, e-mail: tauhata@ird.gov.br; Nicoli, I.G.; Dias, C.M. [Comissao Nacional de Energia Nuclear (DIPLAN/CNEN-DF), Brasilia, DF (Brazil). Distrito do Planalto], e-mail: ieda@cnen.gov.br, e-mail: cintia@cnen.gov.br

    2003-07-01

    The Brazilian Laboratory for Metrology of Ionizing Radiation (LNMRI), of the Radioprotection and Dosimetry Institute, owned by the National Commission of Nuclear Energy (IRD/CNEN-RJ) has conducting since 1998, a comparison program for measurements of radiopharmaceuticals activities applied to patients at Nuclear Medicine sector aiming to the assessment the quality of those measurements. In the Rio de Janeiro state this program is successfully performed existing however the necessity to implement such program all over the country. This problem is being solved through the implementation of a reference laboratories network at several points in the brazilian territory. For the establishment and good working of the network the following factors must be observed: the radionuclide calibrators at the reference laboratories must be connected to the LNMRI; the operators must be trained by the staff or the LNMRI, and the quality guarantee must be assured through a comparison program. Presently, the network point placed in Brasilia is running and covering all the center-west region. The results obtained at this region show that the implementation of the metrology network is viable, important and achievable.

  5. Increase in the amount of evaporator concentrate from nuclear power plants in cemented products; Aumento da quantidade de concentrado de evaporador proveniente de usinas nucleares em produtos cimentados

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Bruna S., E-mail: brusilveirac@gmail.com [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil); Tello, Clédola C.O., E-mail: tellocc@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    Nuclear power plants, research centers and other nuclear facilities are sources of radioactive liquid waste generation. These wastes can come from cooling of the primary reactor system, cleaning spent pool of fuel, washing contaminated clothing, among others. One of the most used methods for the treatment of these aqueous flows is the evaporation, which generates the concentrate of the evaporator, waste classified as low and medium level of radiation. Norms determine that radioactive waste must be minimized, and that to be accepted in repositories, they must be solidified. The work sought to reduce the volume of the evaporated concentrate waste and its subsequent solidification in cement. In order to carry out the tests, the evaporator concentrate (CE) simulation solution was prepared and then dried in an oven. Subsequently, cementation of the dry material was made using cement, fluidizer, NaOH and water. After a curing time of 28 days, the compressive strength tests were made for all specimens obtained, and for the samples that obtained resistance above that required by the norm, which is 10MPa, the percentages of reject incorporated and volume reduction. The results showed that, by drying the evaporator concentrate, it was possible to reduce the volume of the waste generated by up to 27% in relation to the waste without drying, which shows that drying is an effective way to increase the incorporation of the evaporator concentrate in packaged waste.

  6. Practical approach in training (on-the-job) for workers in nuclear industries; Abordagem pratica no treinamento (on-the-job) para trabalhadores em industrias nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Vianna, Vilson Bedim; Rocha, Janine Gandolpho da [Industrias Nucleares do Brasil SA, Rio de Janeiro, RJ (Brazil)

    2005-07-01

    This work approaches the 'on-the-job training' - a method of practical training - used in nuclear industries for workers who handle radioactive nuclides. The required training must, in accordance with the ISO 9000 standard, be geared to meet the needs of the organization, including the minimization of errors in operation with radionuclides, which involves various aspects (standard, social, environmental, personal and process safety etc.). Therefore, the training process must have the commitment of everybody and have a logical and documented sequence, where both the individual and the needs of the company are raised and analyzed. The clear identification of the radiological risks associated to the hands-on training is critical to the safety of who is being trained and should be part of the training content. However, the greatest challenge is a mechanism allowing to transform the hands-on training in practical learning. The role of training in the modern nuclear industry should not be restricted to provide conditions for better training or development of the employee, but also motivate the continuous improvement of the company and of the productive process.

  7. Fault diagnosis of generation IV nuclear HTGR components – Part II: The area error enthalpy–entropy graph approach

    International Nuclear Information System (INIS)

    Rand, C.P. du; Schoor, G. van

    2012-01-01

    Highlights: ► Different uncorrelated fault signatures are derived for HTGR component faults. ► A multiple classifier ensemble increases confidence in classification accuracy. ► Detailed simulation model of system is not required for fault diagnosis. - Abstract: The second paper in a two part series presents the area error method for generation of representative enthalpy–entropy (h–s) fault signatures to classify malfunctions in generation IV nuclear high temperature gas-cooled reactor (HTGR) components. The second classifier is devised to ultimately address the fault diagnosis (FD) problem via the proposed methods in a multiple classifier (MC) ensemble. FD is realized by way of different input feature sets to the classification algorithm based on the area and trajectory of the residual shift between the fault-free and the actual operating h–s graph models. The application of the proposed technique is specifically demonstrated for 24 single fault transients considered in the main power system (MPS) of the Pebble Bed Modular Reactor (PBMR). The results show that the area error technique produces different fault signatures with low correlation for all the examined component faults. A brief evaluation of the two fault signature generation techniques is presented and the performance of the area error method is documented using the fault classification index (FCI) presented in Part I of the series. The final part of this work reports the application of the proposed approach for classification of an emulated fault transient in data from the prototype Pebble Bed Micro Model (PBMM) plant. Reference data values are calculated for the plant via a thermo-hydraulic simulation model of the MPS. The results show that the correspondence between the fault signatures, generated via experimental plant data and simulated reference values, are generally good. The work presented in the two part series, related to the classification of component faults in the MPS of different

  8. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1997

    Energy Technology Data Exchange (ETDEWEB)

    Davis, M.G.; Flotard, R.D.; Fontana, C.A.; Hennessey, P.A.; Maunu, H.K.; Mouck, T.L.; Mullen, A.A.; Sells, M.D.

    1999-01-01

    This report describes the Offsite Radiological Environmental Monitoring Program (OREMP) conducted during 1997 by the US Environmental Protection Agency`s (EPAs), Radiation and Indoor Environments National Laboratory, Las Vegas, Nevada. This laboratory operated an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling and analyzing milk, water, and air; by deploying and reading thermoluminescent dosimeters (TLDs); and using pressurized ionization chambers (PICs) to measure ambient gamma exposure rates with a sensitivity capable of detecting low level exposures not detected by other monitoring methods.

  9. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1993

    Energy Technology Data Exchange (ETDEWEB)

    Chaloud, D.J; Daigler, D.M.; Davis, M.G. [and others

    1996-06-01

    This report describes the Offsite Radiation Safety Program conducted during 1993 by the Environmental Protection Agency`s (EPA`s) Environmental Monitoring Systems Laboratory - Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ionization chambers (PICs); by biological monitoring of foodstuffs including animal tissues and food crops; and by measurement of radioactive material deposited in humans.

  10. Improved method for calculation of population doses from nuclear complexes over large geographical areas

    International Nuclear Information System (INIS)

    Corley, J.P.; Baker, D.A.; Hill, E.R.; Wendell, L.L.

    1977-09-01

    To simplify the calculation of potential long-distance environmental impacts, an overall average population exposure coefficient (P.E.C.) for the entire contiguous United States was calculated for releases to the atmosphere from Hanford facilities. The method, requiring machine computation, combines Bureau of Census population data by census enumeration district and an annual average atmospheric dilution factor (anti chi/Q') derived from 12-hourly gridded wind analyses provided by the NOAA's National Meteorological Center. A variable-trajectory puff-advection model was used to calculate an hourly anti chi/Q' for each grid square, assuming uniform hourly releases; seasonal and annual averages were then calculated. For Hanford, using 1970 census data, a P.E.C. of 2 x 10 -3 man-seconds per cubic meter was calculated. The P.E.C. is useful for both radioactive and nonradioactive releases. To calculate population doses for the entire contiguous United States, the P.E.C. is multiplied by the annual average release rate and then by the dose factor (rem/yr per Ci/m 3 ) for each radionuclide, and the dose contribution in man-rem is summed for all radionuclides. For multiple pathways, the P.E.C. is still useful, provided that doses from a unit release can be obtained from a set of atmospheric dose factors. The methodology is applicable to any point source, any set of population data by map grid coordinates, and any geographical area covered by equivalent meteorological data

  11. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1993

    International Nuclear Information System (INIS)

    Chaloud, D.J; Daigler, D.M.; Davis, M.G.

    1996-06-01

    This report describes the Offsite Radiation Safety Program conducted during 1993 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory - Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ionization chambers (PICs); by biological monitoring of foodstuffs including animal tissues and food crops; and by measurement of radioactive material deposited in humans

  12. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1997

    International Nuclear Information System (INIS)

    Davis, M.G.; Flotard, R.D.; Fontana, C.A.; Hennessey, P.A.; Maunu, H.K.; Mouck, T.L.; Mullen, A.A.; Sells, M.D.

    1999-01-01

    This report describes the Offsite Radiological Environmental Monitoring Program (OREMP) conducted during 1997 by the US Environmental Protection Agency's (EPAs), Radiation and Indoor Environments National Laboratory, Las Vegas, Nevada. This laboratory operated an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling and analyzing milk, water, and air; by deploying and reading thermoluminescent dosimeters (TLDs); and using pressurized ionization chambers (PICs) to measure ambient gamma exposure rates with a sensitivity capable of detecting low level exposures not detected by other monitoring methods

  13. Participação comunitária em um programa de intervenção em área de proteção ambiental Community participation in an intervention program developed in a protected area

    Directory of Open Access Journals (Sweden)

    Andréia Faraoni Freitas Setti

    2010-12-01

    Full Text Available Este artigo discute os conceitos de participação e empowerment em Promoção da Saúde e Desenvolvimento Sustentável, considerando as agendas de implementação local, Municípios/Cidades Saudáveis e Agenda 21, e a importância dos processos de avaliação nesse contexto, por meio da análise de uma intervenção em área de mananciais - o Programa Bairro Ecológico (PBE, desenvolvido em 51 bairros do município de São Bernardo do Campo, Estado de São Paulo, Brasil. O estudo teve por objetivo avaliar os processos de participação e empowerment da comunidade, a partir das ações desencadeadas pelo PBE. Foram aplicados questionários e realizados grupos focais com moradores de bairros que sofreram a intervenção. Também foram realizadas entrevistas individuais com gestores do programa e do poder judiciário. Os resultados indicaram que a participação na implementação do PBE favoreceu o empowerment individual e grupal, presente nas duas comunidades estudadas. As comunidades tornaram-se mais organizadas. Há indícios de que os processos de tomada de decisões são centralizados. Apesar disso, as comunidades entendem que sua participação no programa lhes traz muitas coisas boas. Houve um processo participativo no desenvolvimento do programa, ainda que alguns relatos apontem para o caráter obrigatório da participação. Deve-se destacar o impacto do envolvimento e fortalecimento das lideranças na implementação e sustentabilidade do programa. No que diz respeito a esta última, verificou-se que a sensibilização ambiental tem sido fator determinante para a execução e manutenção das ações ao longo do tempo.This article discusses the concepts of participation and empowerment in Health Promotion and Sustainable Development, considering the local implementation agendas:/ Healthy Cities and Agenda 21, and taking into account the importance of evaluation in this context. This was achieved through the analysis of an intervention

  14. Primeiro registro de Aedes albopictus em área da Mata Atlântica, Recife, PE, Brasil First report of Aedes albopictus in areas of rain forest in Brazil

    Directory of Open Access Journals (Sweden)

    Cleide MR de Albuquerque

    2000-06-01

    Full Text Available Pela primeira vez é registrada a presença do Aedes albopictus em remanescentes de Mata Atlântica, localizada em área urbana em Recife (Pernambuco, Brasil. As coletas foram realizadas em isca humana e em criadouros de formas jovens (ocos de árvores, bambus, bromélias e pneu. A presença de Ae. albopictus na região metropolitana do Recife representa um risco potencial do inter-relacionamento dessa espécie de mosquito com a população.This is the first report of the presence of Aedes albopictus in the native rain forest, near the urban area of Recife (State of Pernambuco, Brazil. Adult female mosquitoes were collected using human bait. Mosquitoes in aquatic stages were looked for in treeholes, bamboos, bromeliads and old tires. The existence of Ae. albopictus in the metropolitan area of Recife poses a potential risk for the interaction of this mosquito species with the urban human population.

  15. Evaluation of quality control of radiopharmaceuticals in Nuclear Medicine service; Avaliacao do controle de qualidade de radiofarmacos em servico de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Tavares, Jamille A. Lopes; Lira, Renata F. de, E-mail: jam_alt@hotmail.com, E-mail: renatafariasdelira@hotmail.com [Universidade Federal de Pernambuco (UFPE), Recife (Brazil); Santos, Marcus Aurelio P. dos, E-mail: masantos@cnen.gov.br [Centro Regional de Ciencias Nucleares do Nordeste (CRCN-NE/CNEN-PE), Recife, PE (Brazil)

    2014-07-01

    Radiopharmaceuticals are a type of pharmaceutical preparation associated with radionuclides with purpose of diagnosis and therapy. Nuclear Medicine Services (NMS) should perform quality control of radiopharmaceuticals according to the recommendations of the manufacturer and scientific evidences accepted by the National Agency Sanitary Surveillance ( Brazilian ANVISA). This study evaluated the quality of the main radiopharmaceuticals in a NMS of the state of Pernambuco in relation to pH and radiochemical purity. The results showed that 96.8% of the radiopharmaceuticals showed radiochemical purity and all pH values were within the range recommended by the American pharmacopoeia. The study found that the quality control when inserted into the NMS, provides important data that allows exclusion of radiopharmaceuticals with low radiochemistry purity, favoring a reliable diagnosis and ensuring good radiation protection practices and biosecurity for patient and occupationally exposed individuals.

  16. The particle swarm optimization algorithm applied to nuclear systems surveillance test planning; Otimizacao aplicada ao planejamento de politicas de testes em sistemas nucleares por enxame de particulas

    Energy Technology Data Exchange (ETDEWEB)

    Siqueira, Newton Norat

    2006-12-15

    This work shows a new approach to solve availability maximization problems in electromechanical systems, under periodic preventive scheduled tests. This approach uses a new Optimization tool called PSO developed by Kennedy and Eberhart (2001), Particle Swarm Optimization, integrated with probabilistic safety analysis model. Two maintenance optimization problems are solved by the proposed technique, the first one is a hypothetical electromechanical configuration and the second one is a real case from a nuclear power plant (Emergency Diesel Generators). For both problem PSO is compared to a genetic algorithm (GA). In the experiments made, PSO was able to obtain results comparable or even slightly better than those obtained b GA. Therefore, the PSO algorithm is simpler and its convergence is faster, indicating that PSO is a good alternative for solving such kind of problems. (author)

  17. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    The first text deals with a new circular concerning the collect of the medicine radioactive wastes, containing radium. This campaign wants to incite people to let go their radioactive wastes (needles, tubes) in order to suppress any danger. The second text presents a decree of the 31 december 1999, relative to the limitations of noise and external risks resulting from the nuclear facilities exploitation: noise, atmospheric pollution, water pollution, wastes management and fire prevention. (A.L.B.)

  18. Characterization of ceramics of titanium oxide to treatment of effluents from nuclear area

    International Nuclear Information System (INIS)

    Silva, Milena Hudson da; Oliveira, Elizabeth E. de Mello

    2017-01-01

    Membrane separation processes (PSM) have become increasingly important technology, with application in several areas to separate, concentrate or purify solutions. PSM has been justified because it is an easy-to-operate separation technique and, in general, does not involve phase change. Ceramic membranes exhibit superior properties as polymeric, mainly about chemical resistance to solvents and extremes of temperature and pH. Ceramic membranes are composed of a porous support, responsible for the mechanical resistance and covered by a thin layer, responsible for selectivity. In this work were prepared supports based on titanium oxide (TiO 2 ), which features high stability, thermal, chemical resistance to organic solvents and application in a wide pH range (0-14). Three aqueous solutions were prepared containing TiO 2 and corn starch at concentrations of 0, 15 and 30%, acting as a pores former. The solutions were dried in Spray-Dryer, to obtain a homogeneous mixture and grainy. The support has been compressed to a pressure of 1.5 Kgfcm -2 in the form of cylindrical disks of 2.5 cm diameter sintered at temperatures of 1100 and and 1150° C. The discs were weighed and their dimensions measured for the determination of geometric density and porosity. Hydraulic permeability tests were performed at pressures of 1 to 4 bar. The conditions of 1100 ° C without addition of starch and 1150 ° C with 15% of starch had porosities of 42% and 44%, respectively, values close to that suggested in the literature, between 35-40%

  19. Patterns identification in supervisory systems of nuclear reactors installations and gas pipelines systems using self-organizing maps; Identificacao de padroes em sistemas supervisorios de instalacoes de reatores nucleares e em sistemas de gasodutos utilizando mapas auto-organizaveis

    Energy Technology Data Exchange (ETDEWEB)

    Doraskevicius Junior, Waldemar

    2005-07-01

    Self-Organizing Maps, SOM, of Kohonen were studied, implemented and tested with the aim of developing, for the energy branch, an effective tool especially for transient identification in nuclear reactors and for gas pipelines networks logistic supervision, by classifying operations and identifying transients or abnormalities. The digital system for the test was developed in Java platform, for the portability and scalability, and for belonging to free development platforms. The system, executed in personal computers, showed satisfactory results to aid in decision taking, by classifying IRIS (International Reactor Innovative and Secure) reactor operation conditions (data from simulator) and by classifying Southeast (owner: TRANSPETRO - Brazil) gas pipeline network. Various adaptations were needed for such business, as new topologies for the output layer of artificial neural network and particular preparation for the input data. (author)

  20. Mortality in Zarinsk area of Altai Krai as a territory exposed to radiation as a result of nuclear tests at the Semipalatinsk test site

    OpenAIRE

    Kolyado I.; Plugin S.

    2017-01-01

    In Altai krai, there exists a regional segment of the National Radiation Epidemiological Register. The most numerous contingent are victims of nuclear tests at the Semipalatinsk testing site. The new method of calculation of cumulative total effective whole-body radiation dose in patients exposed to radiation as a result of nuclear testing at the Semipalatinsk test site allowed expanding this contingent, to a large extent - due to the inhabitants of Zarinsk area of Altai Krai. The given artic...

  1. A pesquisa na área de Gerenciamento em Enfermagem no Brasil La investigación en la area de Gerencia en Enfermería en Brasil Research in Nursing Administration area in Brazil

    Directory of Open Access Journals (Sweden)

    Paulina Kurcgant

    2005-04-01

    Full Text Available O presente estudo teve como objetivo identificar e analisar a produção do conhecimento na área do gerenciamento em enfermagem, no país, resultante das pesquisas produzidas nos cursos de Mestrado, Doutorado e Teses de Livre-Docência no período 1979-2000. A população do estudo constituiu-se de 138 Dissertações, 50 Teses de Doutorado e 10 de Livre-Docência, totalizando 198 produções. Estas foram analisadas de acordo coma s linhas de pesquisa da área campo Organizacional. Os resultados permitiram visualizar a distribuição da produção por temática, linha de pesquisa, década; método; corrente de pensamento adotada e região geográfica. Permitiram, também, traçar considerações a respeito da trajetória, necessidades e perspectivas das pesquisas em Gerenciamento em Enfermagem.El presente estudio tuvo como objetivos identificar y analizar la producción del conocimiento en el área de gerencia en enfermería, en el país, resultante de las investigaciones producidas en los cursos de Maestría, Doctorado y Tesis de Libre Docencia al período 1979-2000 . La población del estudio fue constituida por 138 tesis de maestría, 50 tesis de Doctorado y 10 de Libre Docencia, totalizando 198 producciones científicas. Estas fueron analizadas de acuerdo con las líneas de investigación del área campo Organizacional. Los resultados permitieron visualizar la distribución de la producción por temática, línea de investigación, década; método; corriente de pensamiento adoptada en esos estudios y región geográfica. Permitieron, también, trazar consideraciones sobre la trayectoria, necesidades y perspectivas de las investigaciones en Gerencia en Enfermería.The present study had as objective the identification and analysis of knowledge production in the field of nursing management in the country, resulting from research conducted in the Master and Doctorate Programs as well as Ph.D, during the period of 1979-2000. The study sample was

  2. Estudo de dois anos com animais reservatórios em área de ocorrência de leishmaniose tegumentar americana humana em bairro de urbanização antiga na cidade de Manaus-AM, Brasil Two year study of reservoir animals in an old urban area with cutaneous Leishmaniasis occurrence in the city of Manaus-AM, Brazil

    Directory of Open Access Journals (Sweden)

    Jorge Augusto de Oliveira Guerra

    2007-01-01

    Full Text Available Os autores descrevem o resultado de dois anos de investigação de um foco de Leishmaniose Tegumentar Americana (LTA, ocorrida em área urbanizada em um conjunto habitacional na cidade da Manaus-AM. Chama atenção o fato de que este não é o padrão de ocorrência de surtos da doença na região, e sim interrupção da transmissão após urbanização. Foram investigados os animais considerados reservatórios em potencial para a leishmaniose em domicílios humanos e em áreas de floresta adjacentes. Foram testados anticorpos contra Leishmania spp em amostras de sangue de cães e detectada reatividade pela reação de imunofluorescencia indireta em oito (20,51 % dos examinados. Entre os animais silvestres examinados a espécie Didelphis marsupialis foi predominante, com 20 exemplares capturados, sendo encontrados homoflagelados em três destes e lesões suspeitas de leishmaniose cutanea em dois. Acredita-se que um assentamento populacional desordenado ocorrido nas adjacências tenha causado o deslocamento das populações de vetores e reservatórios naturais em direção às casas do conjunto Hiléia propiciando o surto.This is the result of a two year follow-up of a Cutaneous Leishmaniasis (CL foci in the Hileia urban neighborhood in Manaus. It is important to point out that this is not the usual pattern of Leishmaniasis occurrence in this area. The authors investigated the animal potential reservoir in households and in the surrounding forest area. Samples were tested for leishmaniasis antibodies by RIFI. Eight (20.51% of the examined domestic dogs showed reactivity. In captured wild animals, the Didelphis marsupialis was predominant in twenty specimens, three with homoflagelated in the blood and two with suspicious cutaneous lesions. We believe that the disordered population growth in the nearby area pushed the population of vectors and natural reservoir toward the homes in the Heleia neighborhood creating conditions for this outbreak.

  3. One safety critical indicators model for regulatory actions on nuclear power plants based on a level 1 PSA; Um modelo de indicadores criticos de seguranca para acoes regulatorias em usinas nucleares baseado em uma APS nivel 1

    Energy Technology Data Exchange (ETDEWEB)

    Araujo, Jefferson Borges

    2006-03-15

    This study presents a general methodology to the establishment, selection and use of safety indicators for a two loop PWR plant, as Angra 1. The study performed identifies areas considered critical for the plant operational safety. For each of these areas, strategic sub-areas are defined. For each strategic sub-area, specific safety indicators are defined. These proposed Safety Indicators are based on the contribution to risk considering a quantitative risk analysis. For each safety indicator, a goal, a bounded interval and proper bases are developed, to allow for a clear and comprehensive individual behavior evaluation. Additionally, an integrated evaluation of the indicators, using expert systems, was done to obtain an overview of the plant general safety. This methodology can be used for identifying situations where the plant safety is challenged, by giving a general overview of the plant operational condition. Additionally, this study can also identify eventual room for improvements by generating suggestions and recommendations, as a complement for regulatory actions and inspections, focusing resources on eventual existing weaknesses, in order to increase or maintain a high pattern of operational safety. (author)

  4. Modelos de determinação não-destrutiva da área foliar em girassol Models for estimating leaf area in sunflower

    Directory of Open Access Journals (Sweden)

    Ivan Carlos Maldaner

    2009-08-01

    Full Text Available Os objetivos deste trabalho foram obter e testar modelos matemáticos de estimativa da área do limbo foliar em função das suas dimensões lineares para o girassol. Foram conduzidos dois experimentos na área experimental do departamento de Fitotecnia da Universidade Federal de Santa Maria. As plantas de girassol foram coletadas a partir dos 27 dias após emergência (DAE. A área foliar (AF foi determinada pelo método dos discos. Ajustaram-se modelos lineares, quadráticos, cúbicos e potenciais entre área foliar e comprimento ou largura e seus produtos (comprimento*largura, sendo eliminados os que apresentaram coeficiente de determinação menor do que 0,90. A estatística utilizada para avaliar o desempenho dos modelos foi a raiz do quadrado médio do erro (RQME. Os modelos que melhor se ajustaram aos dados foram: potência, quadrático e cúbico, considerando a largura como variável independente. A área foliar de girassol pode ser estimada com o modelo potência, por ser o mais preciso, e a largura da folha.The objective of this study was to obtain and to numerical models to estimate the leaf area in function leaves linear dimension in sunflower. Two experiments were conducted at the experimental area of the Plant Science Department of the Federal University of Santa Maria, Santa Maria, RS, Brazil. Plants of sunflower were collected starting 27 days after emergency (DAE. The disks method was used to determine the leaf area (LA. Leaves were dried in oven at 65°C until constant weight. Linear, quadratic, cubic and power models between leaf area and length or width, and the product (length * width, were fitted. Models that apresented coefficient of determination lower than 0.90 were not selected. The statistic used to evaluate the performance of the models was the root mean square error (RQME. Models that had the best fit were power, quadratic and cubic using blade width as the independent variable. Leaf area in sunflower can be

  5. Simulation of Groundwater Movement for Nuclear Research Center at AlTuwaitha Area in Baghdad City, Iraq

    Directory of Open Access Journals (Sweden)

    Ayad Sleibi Mustafa

    2017-07-01

    Full Text Available The simulation of groundwater movement has been carried out by using MODFLOW model in order to show the impact of change of water surface elevation of the Tigris river on layers of the aquifer system for Nuclear Research Center at Al-Tuwaitha area, in addition to evaluate the ability of the proposed pumping well to collect groundwater and change the direction of flow at steady-state. The results of the study indicated that there is a good match between the values of groundwater levels that calculated in the model and measured in the field, where mean error is 0.09 m.The study also showed that the increasing of water surface elevation of the Tigris river led to increase in the hydraulic head of observed wells, while the use proposed pumping well reduced the hydraulic head and intercepted the movement of groundwater flow. The flow direction is toward the Tigris river, and the velocity of flow is clear in the third layer identified medium sand which is 0.0015 m/day. The using of the proposed pumping well has changed the direction of groundwater, especially in the area around the well.

  6. Pu distribution in seawater in the near coastal area off Fukushima after the Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Bu, W.T.; Zheng, J.; Aono, T.; Wu, J.W.; Tagami, K.; Uchida, S.; Guo, Q.J.; Yamada, M.

    2015-01-01

    The Fukushima Daiichi Nuclear Power Plant (FDNPP) accident released large amount of radionuclides into the marine environment. Compared with the fission products, data on the distributions of Pu in the marine environment of the western North Pacific after the accident is limited. To better understand the Pu contamination in the marine environment after the accident, for the first time, we determined Pu isotope ratio ( 240 Pu/ 239 Pu) in addition to 239+240 Pu activity in seawater collected in the near coastal area (mostly within the 30 km zone) off the FDNPP site. The 239+240P u activities were 4.16-5.52 mBq/m 3 and the 240 Pu/ 239 Pu atom ratios varied from 0.221 to 0.295. These values were compared with the baseline data for Pu distribution in the near coast seawaters before the FDNPP accident (2008-2010). The results suggested that there is no significant Pu contamination in seawater in the near coastal area off the FDNPP site from the accident two years after the accident. (author)

  7. Radionuclide content and hydrodynamic characterization of the area in the vicinity of the Centro Regional de Ciencias Nucleares

    International Nuclear Information System (INIS)

    Brandao, Yana B.; Borges, Edvane

    2008-01-01

    In order to comply with the Brazilian environmental laws, a survey of the radiation levels in the site of construction of the Centro Regional de Ciencias Nucleares (CRCN), in the urban area of Recife, state of Pernanbuco, Brazil, was conducted, for further assessment of the impact caused by the center activities. Concentration level of 238 U and 210 Po were determined in soil and water samples were in the vicinity of the CRCN. The 238 U content in soil samples varied from 7 to 44.4 Bq.kg -1 . For water samples, the measured values for 210 Po ranged from 12 to 19.6 mBq.L -1 . Soil samples were collected to determine the hydrodynamic characteristic of the area. In order to determine the soil-water retention curves, samples were collected from the surface and at depths of 20-25 cm, 40-45 cm, 60-65 cm, 80-85 cm and 100-105 cm. The results of soil-water retention curves showed that the soil of the center, compounded by various embankments, presented several textural classifications, which ranged from loam sandy, loamy sand, loam and sand clay earth within the same profile 0-100 cm. (author)

  8. An estimate of the maximal doses incurred by persons accompanying patients in the waiting area of a nuclear medicine department

    International Nuclear Information System (INIS)

    Dzik-Jurasz, A.S.K.; Farwell, J.

    1997-01-01

    The aim of the study was to make an estimate of the maximal doses that might be incurred by persons accompanying active patients in a nuclear medicine department waiting area. This was in order to determine whether the dose to such individuals approached current legislative or recently recommended limits. Thermoluminescent dosemeters were taped to the walls of the waiting area at waist level to the sitting individual, such that their record would reflect as closely as possible the dose incurred by an individual sitting next to an active patient. Dividing the recorded dose with the total occupancy time of that seat derived an average dose rate. Maximal doses were estimated by the product of the latter and maximal occupancy times. It was assumed that an accompanying individual would have been sitting next to the active patient for their whole duration of stay. The maximum estimates were 278 μSv and 103.2 μSv. These values are likely to be overestimates by the virtue of the TLD integrating the whole dose of its surrounds, especially adjacent active individuals. By current legislation and recent recommendations the values are reassuringly low, but idiosyncrasies in local practice might need to be considered in individual departments. (author)

  9. Surface motion near underground nuclear explosions in desert alluvium Operation Nougat I, Area 3, Nevada Test Site

    International Nuclear Information System (INIS)

    Perret, W.R.

    1978-05-01

    During Operation Nougat I, which was conducted in late 1961 and the first half of 1962, Sandia Laboratories measured surface motion in the vicinity of all contained underground nuclear explosions conducted by the Los Alamos Scientific Laboratory in Area 3 of the Nevada Test Site. This report presents and analyses most of the data derived from that study. Propagation velocities in the desert alluvium, 4440 ft/sec, and underlying tuff, 6020 ft/sec, are typical of those derived from later measurements. Motion attenuation data exhibit considerable scatter, in part because of early measurement and data reduction techniques but primarily because of differences in the characteristics of the geologic media which had not then been recognized. However, regression fits to the scaled data show attenuation of scaled acceleration at a rate 35% greater than that observed for Merlin event data (Merlin was conducted later in Area 3). The attenuation rate for particle velocity data from Nougat I events was 47% less than that for Merlin data, and the Nougat I scaled displacement data attenuation rate was 87% less than that for Merlin data. Analysis of data from a vertical string of gages extending to the surface above the Mink explosion has established a significant difference between normal spallation above contained explosions in competent rock and the reaction of uncemented alluvium to similar explosive loading

  10. Seismic stability of the survey areas of potential sites for the deep geological repository of the spent nuclear fuel

    Science.gov (United States)

    Kaláb, Zdeněk; Šílený, Jan; Lednická, Markéta

    2017-07-01

    This paper deals with the seismic stability of the survey areas of potential sites for the deep geological repository of the spent nuclear fuel in the Czech Republic. The basic source of data for historical earthquakes up to 1990 was the seismic website [1-]. The most intense earthquake described occurred on September 15, 1590 in the Niederroesterreich region (Austria) in the historical period; its reported intensity is Io = 8-9. The source of the contemporary seismic data for the period since 1991 to the end of 2014 was the website [11]. It may be stated based on the databases and literature review that in the period from 1900, no earthquake exceeding magnitude 5.1 originated in the territory of the Czech Republic. In order to evaluate seismicity and to assess the impact of seismic effects at depths of hypothetical deep geological repository for the next time period, the neo-deterministic method was selected as an extension of the probabilistic method. Each one out of the seven survey areas were assessed by the neo-deterministic evaluation of the seismic wave-field excited by selected individual events and determining the maximum loading. Results of seismological databases studies and neo-deterministic analysis of Čihadlo locality are presented.

  11. In-Containment Signal Conditioning and Transmission via Power Lines within High Dose Rate Areas of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, Steffen; Weigel, Robert; Koelpin, Alexander [Institute for Electronics Engineering, University of Erlangen-Nuremberg, Cauerstr. 9, 91058 Erlangen (Germany); Dennerlein, Juergen; Janke, Iryna; Weber, Johannes [AREVA GmbH, Paul-Gossen-Str. 100, 91052 Erlangen (Germany)

    2015-07-01

    Signal conditioning and transmission for sensor systems and networks within the containment of nuclear power plants (NPPs) still poses a challenge to engineers, particularly in the case of equipment upgrades for existing plants, temporary measurements, decommissioning of plants, but also for new builds. This paper presents an innovative method for efficient and cost-effective instrumentation within high dose rate areas inside the containment. A transmitter-receiver topology is proposed that allows simultaneous, unidirectional point-to-point transmission of multiple sensor signals by superimposing them on existing AC or DC power supply cables using power line communication (PLC) technology. Thereby the need for costly installation of additional cables and containment penetrations is eliminated. Based on commercial off-the-shelf (COTS) electronic parts, a radiation hard transmitter is designed to operate in harsh environment within the containment during full plant operation. Hardware modularity of the transmitter allows application specific tradeoffs between redundancy and channel bandwidth. At receiver side in non-radiated areas, signals are extracted from the power line, demodulated, and provided either in analog or digital output format. Laboratory qualification tests and field test results within a boiling water reactor (BWR) are validating the proof of concept of the proposed system. (authors)

  12. The US DOE EM international program

    Energy Technology Data Exchange (ETDEWEB)

    Elmetti, Rosa R.; Han, Ana M. [U.S. Department of Energy, Washington, D.C. (United States); Roach, Jay A. [Nexergy Technical, LLC., Falls Church, Virginia (United States)

    2013-07-01

    The U.S. Department of Energy (DOE) Office of Environmental Management (EM) conducts international collaboration activities in support of U.S. policies and objectives regarding the accelerated risk reduction and remediation of environmental legacy of the nations' nuclear weapons program and government sponsored nuclear energy research. The EM International Program supported out of the EM Office of the Associate Principal Deputy Assistant Secretary pursues collaborations with foreign government organizations, educational institutions and private industry to assist in identifying technologies and promote international collaborations that leverage resources and link international experience and expertise. In fiscal year (FY) 2012, the International Program awarded eight international collaborative projects for work scope spanning waste processing, groundwater and soil remediation, deactivation and decommissioning (D and D) and nuclear materials disposition initiatives to seven foreign organizations. Additionally, the International Program's scope and collaboration opportunities were expanded to include technical as well as non-technical areas. This paper will present an overview of the on-going tasks awarded in FY 2012 and an update of upcoming international activities and opportunities for expansion into the remainder of FY 2013 and beyond. (authors)

  13. Sensitivity analysis for heat diffusion in a fin on a nuclear fuel element; Analise de sensitividade na difusao de calor em uma aleta de um elemento combustivel nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Tito, Max Werner de Carvalho

    2001-11-15

    The modern thermal systems generally present a growing complexity, as is in the case of nuclear power plants. It seems that is necessary the use of complex computation and mathematical tools in order to increase the efficiency of the operations, reduce costs and maximize profits while maintaining the integrity of its components. The use of sensitivity calculations plays an important role in this process providing relevant information regarding the resultant influence of variation or perturbation of its parameters as the system works. This technique is better known as sensitivity analysis and through its use makes possible the understanding of the effects of the parameters, which are fundamental for the project preparation, and for the development of preventive and corrective handling measurements of many pieces of equipment of modern engineering. The sensitivity calculation methodology is based generally on the response surface technique (graphic description of the functions of interest based in the results obtained from the system parameter variation). This method presents a lot of disadvantages and sometimes is even impracticable since many parameters can cause alterations or perturbations to the system and the model to analyse it can be very complex as well. The utilization of perturbative methods result appropriate as a practical solution to this problem especially in the presence of complex equations. Also it reduces the resultant computational calculus time considerably. The use of these methods becomes an essential tool to simplify the sensitivity analysis. In this dissertation, the differential perturbative method is applied in a heat conduction problem within a thermal system, made up of a one-dimensional circumferential fin on a nuclear fuel element. The fins are used to extend the thermal surfaces where convection occurs; thus increasing the heat transfer to many thermal pieces of equipment in order to obtain better results. The finned claddings are

  14. Tanks Focus Area annual report FY2000

    International Nuclear Information System (INIS)

    2000-01-01

    The U.S. Department of Energy (DOE) continues to face a major radioactive waste tank remediation effort with tanks containing hazardous and radioactive waste resulting from the production of nuclear materials. With some 90 million gallons of waste in the form of solid, sludge, liquid, and gas stored in 287 tanks across the DOE complex, containing approximately 650 million curies, radioactive waste storage tank remediation is the nation's highest cleanup priority. Differing waste types and unique technical issues require specialized science and technology to achieve tank cleanup in an environmentally acceptable manner. Some of the waste has been stored for over 50 years in tanks that have exceeded their design lives. The challenge is to characterize and maintain these contents in a safe condition and continue to remediate and close each tank to minimize the risks of waste migration and exposure to workers, the public, and the environment. In 1994, the DOE's Office of Environmental Management (EM) created a group of integrated, multiorganizational teams focusing on specific areas of the EM cleanup mission. These teams have evolved into five focus areas managed within EM's Office of Science and Technology (OST): Tanks Focus Area (TFA); Deactivation and Decommissioning Focus Area; Nuclear Materials Focus Area; Subsurface Contaminants Focus Area; and Transuranic and Mixed Waste Focus Area

  15. Tanks Focus Area annual report FY2000

    Energy Technology Data Exchange (ETDEWEB)

    None

    2000-12-01

    The U.S. Department of Energy (DOE) continues to face a major radioactive waste tank remediation effort with tanks containing hazardous and radioactive waste resulting from the production of nuclear materials. With some 90 million gallons of waste in the form of solid, sludge, liquid, and gas stored in 287 tanks across the DOE complex, containing approximately 650 million curies, radioactive waste storage tank remediation is the nation's highest cleanup priority. Differing waste types and unique technical issues require specialized science and technology to achieve tank cleanup in an environmentally acceptable manner. Some of the waste has been stored for over 50 years in tanks that have exceeded their design lives. The challenge is to characterize and maintain these contents in a safe condition and continue to remediate and close each tank to minimize the risks of waste migration and exposure to workers, the public, and the environment. In 1994, the DOE's Office of Environmental Management (EM) created a group of integrated, multiorganizational teams focusing on specific areas of the EM cleanup mission. These teams have evolved into five focus areas managed within EM's Office of Science and Technology (OST): Tanks Focus Area (TFA); Deactivation and Decommissioning Focus Area; Nuclear Materials Focus Area; Subsurface Contaminants Focus Area; and Transuranic and Mixed Waste Focus Area.

  16. New recommendations from the IAEA for medical exposures: impact on nuclear medicine in Brazil; Novas recomendacoes da IAEA para exposicoes medicas: impacto em medicina nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Sa, Lidia Vasconcellos de; Kodlulovich, Simone, E-mail: lidia@ird.gov.br, E-mail: simone@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2013-10-01

    An assessment of the current national standards was performed in order to verify compliance with the new recommendations, taking into account the number of available facilities and medical physicists to meet the requirements. It was found that compliance with the requirements of protocol optimization and individualization of doses, as well as the assignment of responsibility shared by all professionals involved were not disclosed. In Brazil, there is no reference levels established as also there is not a government program to obtain them. The functions and responsibilities of the medical physicist in conducting dosimetry individual patient, quality control and acceptance tests of equipment and also the calibration is not defined in the standard. Currently in Brazil there are 31 certified Medical Physicists in Medicine Nuclear power to meet approximately 390 facilities, representing only 8% required. As a member state of the IAEA, the Brazilian rules governed by CNEN is based on BSS-115, must come to terms with the GSR. The concern is now meeting the requirements, especially those relating to patients, since we have established benchmarks and individualized dosimetry. Beyond addition, the number of medical physicists are not enough to show the country's demand. (author)

  17. Hybrid instrument applied to human reliability study in event of loss of external electric power in a nuclear power plant; Instrumento hibrido aplicado ao estudo da confiabilidade humana em evento de perda de energia eletrica externa em usina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Eduardo Ferraz

    2015-04-01

    The study projects in highly complex installations involves robust modeling, supported by conceptual and mathematical tools, to carry out systematic research and structured the different risk scenarios that can lead to unwanted events from occurring equipment failures or human errors. In the context of classical modeling, the Probabilistic Safety Analysis (PSA) seeks to provide qualitative and quantitative information about the project particularity and their operational facilities, including the identification of factors or scenarios that contribute to the risk and consequent comparison options for increasing safety. In this context, the aim of the thesis is to develop a hybrid instrument (CPP-HI) innovative, from the integrated modeling techniques of Failure Mode and Effect Analysis (FMEA), concepts of Human Reliability Analysis and Probabilistic Composition of Preferences (PCP). In support of modeling and validation of the CPP-HI, a simulation was performed on a triggering event 'Loss of External Electric Power' - PEEE, in a Nuclear Power plant. The results were simulated in a virtual environment (sensitivity analysis) and are robust to the study of Human Reliability Analysis (HRA) in the context of the PSA. (author)

  18. Aid system in the attention direction for accidents diagnosis at nuclear power plants based on artificial intelligence; Sistema de auxilio para o direcionamento da atencao no diagnostico de acidentes em usinas nucleares baseado em inteligencia artificial

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Rafael Gomes da

    2009-07-01

    Transient identification in Nuclear Power Plant (NPP) is often a very hard task and may involve a great amount of human cognition. The early identification of unexpected departures from steady state behavior is an essential step for the operation, control and accident management in NPPs. The bases for the transient identification relay on the evidence that different system faults and anomalies lead to different pattern evolution in the involved process variables. During an abnormal event, the operator must monitor a great amount of information from the instruments that represents a specific type of event Several systems based on specialist systems, neural-networks, and fuzzy logic have been developed for transient identification. In the work, we investigate the possibility of using a Neuro Fuzzy modeling tool for efficient transient identification, aiming to helping the operator crew to take decisions relative to the procedure to be followed in situations of accidents/transients at NPPs. The proposed system uses artificial neural networks (ANN) as first level transient diagnostic After the ANN has done the preliminary transient type identification, a fuzzy-logic system analyzes the results emitting reliability degree of it. A preliminary evaluation of the developed system was made at the Human-System Interface Laboratory (LABIHS). The obtained results show that the system can help the operators to take decisions during transients/accidents in the plant (author)

  19. Evaluation of occupational radiation dose in nuclear medicine: radiopharmaceutical administration to scintiscanning exams of myocardial perfusion; Avaliacao da dose de radiacao ocupacional em medicina nuclear: administracao de radiofarmacos em exames de cintilografria de perfusao miocardica

    Energy Technology Data Exchange (ETDEWEB)

    Komatsu, Cassio V., E-mail: cassiok@yahoo.com [Medicina Nuclear do Triangulo (MNT), Uberlandia, MG (Brazil); Michelin, Charlie A.; Jakubiak, Rosangela R., E-mail: charlie@utfpr.edu.br, E-mail: requi@utfpr.edu.br [Universidade Tecnologica Federal do Parana (UTFPR), Curitiba, PR (Brazil); Lemes, Alyne O.; Silva, Juliana L.M., E-mail: alyne275@gmail.com, E-mail: jujumontesdocinho@gmail.com [Faculdade do Trabalho (FATRA), Uberlandia, MG (Brazil)

    2013-11-01

    In nuclear medicine, workers directly involved in exams are constantly exposed to ionizing radiation. The procedure for administration of the radiopharmaceutical to the patient is one of the most critical times of exposure. In tests of myocardial perfusion scintigraphy (MPS) administration of radiopharmaceutical repeats the steps of rest and cardiac stress. In this study, we used a Geiger -Mueller detector for measuring occupational radiation doses for during the administration of technetium- {sup 99m}- sestamibi in MPS tests. In the evaluation, discriminated the stages of examination and related professional experience time to doses measures at home. It were followed 110 procedures at home (55 conducted by professionals with over 5 years experience and 55 conducted by professionals with less than 1 year of experience) and 55 effort procedures. The results showed that the rest of the procedure time and dose are related to the experience of the worker. More experienced workers were faster (mean: 43 {+-} 16 vs 67 {+-} 25 seconds / procedure), and therefore received lower doses (mean 0.57 {+-} 0.16 versus 0.80 {+-} 0.24 {mu}Sv / procedure), both with statistical significance (p <0.001). In step effort, there were procedures lasting longer (mean: 19 {+-} 2 minutes / procedure), which resulted in higher doses (mean 3.0 {+-} 0.6 {mu}Sv / procedure)

  20. Chernobyl: exclusive investigation. How the French nuclear lobby buries the truth in contaminated areas. The After-Chernobyl or 'Living happy' in contaminated area

    International Nuclear Information System (INIS)

    2006-01-01

    According to the results of this inquiry, the CEPN (study centre on assessment of protection in the nuclear sector) has been created by the main actors of the nuclear industrial sector (EFG, Cogema, CEA and IRSN) and is at the origin of the ETHOS and CORE projects. Moreover, these projects have been financed by public funds. It also shows that the FNSEA (farmer trade union) has been allied to the French nuclear lobby for the distribution probably contaminated and radioactive foodstuff. It evokes the case of Belarus researcher who denounced such contamination and the misappropriation of international funds, and who was sent to jail. It comments the collaboration between the French nuclear sector and the Belarus regime, denounces how the truth about Chernobyl has been hidden, the cynical results of the ETOS program which would imply the consumption of contaminated foodstuff in France in case of nuclear accident. Some proposals are made: to dismantle the CEPN, to stop the participation of French organisations to the CORE and FARMING programs, creation of an independent commission on the consequences of the Chernobyl accident, and so on. For the authors, phasing out nuclear is the only solution o avoid a new Chernobyl

  1. Reference values in blood elements in crioula breed horses by nuclear methodology; Valores de referencia de elementos em sangue de cavalos da raca crioula via metodologia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Baptista, Tatyana Spinosa

    2010-07-01

    In this study the reference value for Br (0,0008 - 0,0056 gL{sup -1}), Ca (0,089 - 0,369 gL{sup -1}), Cl (2,10 - 3,26 gL{sup -1}), Fe (0,381 - 0,689 gL{sup -1}), I (0,00018 - 0,00266 gL{sup -1}), K (1,14 - 2,74 gL{sup -1}), Mg (0,030 - 0,074 gL{sup -1}), Na (1,36 - 2,80 gL{sup -1}), P (<1,99 gL{sup -1}), S (0,99 - 2,79 gL{sup -1}) and Zn (0,0012 - 0,0048 gL{sup -1}) as well as the correlation matrix in blood of Crioulo breed horses were determined using nuclear methodology (Neutron Activation Analysis Technique). These data allowed to identifying physiological alterations related to the sex and regime of exercise (hyperimmune sera production at Butantan Institute, Sao Paulo, Brasil). To perform these analyses was used 20 adult horses (8 males and 12 females), with average mass 350 kg, without clinical signs of disease, 1-3 years old, kept on pasture in Sao Joaquim Farm at Butantan Institute (Sao Paulo city). Other group just immunized, composed by 6 equines males (same age and weight), were also analyzed. These data are an important support to understand the physiological functions of these elements in blood during the process of sera production. (author)

  2. Study of the distribution of ions and metals in blood using nuclear methodology; Estudo da distribuicao de ions e metais em sangue via metodologia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Laura Cristina de

    2008-07-01

    The present study consists of using nuclear tools aiming to establish an alternative procedure to perform biochemistry analyses in whole blood to help the diagnosis of diverse pathologies. The aim is to determine the ions and metals concentrations in whole blood of human beings (specifically: Br, Cl, K e Na), using neutron activation analysis, providing the limits of normality, as well as, the matrix of the correlation for these elements. To perform this study, 283 samples of whole blood had been analyzed (of healthy volunteers selected from blood banks), resulting in the limits of normality for Br (0.0067 - 0.0263 gl{sup -1}), Cl (2.54 - 3.50 gl{sup -1}), K (1.33 - 1.89 gl{sup -1}) and Na (1.48 - 2.06 gl{sup -1}). These data are the first estimates for reference values in whole blood of the Brazilian population. These limits were evaluated in function of the sex and age for checking the biological differences. The behavior of these limits was also evaluated for different populations, i.e., in two distinct regions: Southeast (blood collection carried out in Sao Paulo city) and Northeast (blood collection carried out in Recife city). These places were chosen in function of the similarities (cities with high concentration people and industrialized). Furthermore, a systematic study of these limits was also evaluated, in the period of 4 (four) years, in Sao Paulo city. This analysis was elaborated in function of time due the necessity to update these data, therefore they act as environment monitors. The estimation for Ca and Fe were also proposal for a set of 22 samples of whole blood.(author)

  3. Evaluation of '9{sup 9}Mo presence in eluates of {sup 99}mTc used in nuclear medicine; Avaliacao da presenca de {sup 99}Mo em eluatos de {sup 99m}Tc utilizados em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ribeiro, Bianca da Silva

    2010-07-01

    Tc-99m is used for diagnostic imaging in nuclear medicine through SPECT technique. It is obtained by the elution of {sup 99}Mo/{sup 99m}Tc generators. During the elution process {sup 99}Mo can be extracted becoming a radionuclidic impurity. One of the quality parameters of the eluate is the radionuclidic purity, MBT (molybdenum break through), defined as the ratio between {sup 99}Mo and {sup 99m}Tc activities in the eluate. The North-American and European pharmacopoeias restrict the {sup 99}Mo content, respectively, in 0.015 e 0.1% and, according to the International Atomic Energy Agency (IAEA), the activity ratio at the moment of administration of the radiopharmaceutical to the patient, should not exceed 0.015%. In Brazil, the control of such parameter is not obliged in official regulations. Thus, the objective of this work is to evaluate the occurrence of {sup 99}Mo in {sup 99m}Tc eluates. It was initially optimized a methodology to determine the activity of {sup 99}Mo in eluate samples. Efficiency curves were obtained for a NaI (Tl) 8'' x 4'' scintillation detector installed at the In Vivo Monitoring Laboratory (LABMIV-IRD). The methodology has been validated through the measurement of a {sup 99}Mo standard liquid source calibrated at the National Metrology Laboratory for Ionizing Radiation (LNMRI-IRD). The samples analyzed in this work were gently supplied by 5 Nuclear Medicine Clinics located in the city of Rio de Janeiro. The activities of {sup 99}mTc and {sup 99}Mo in those samples have been measured respectively at the clinics and at the LABMIV. By applying a standardized methodology, the ration between the activities were calculated. The results show that 147 out of 174 samples presented {sup 99}Mo activities above the minimum detectable activity of the technique. On the other hand, only 2 out of 147 samples surpassed the MBT limit suggested by the IAEA and have been detected in samples eluted from generators of 750 mCi. In one of the

  4. Biologia e manejo de plantas daninhas em áreas de plantio direto Weed biology and management in no-tillage areas

    Directory of Open Access Journals (Sweden)

    F.G. Gomes JR.

    2008-01-01

    Full Text Available Procurou-se relacionar alguns aspectos importantes da biologia e do manejo das plantas daninhas infestantes em áreas cultivadas sob sistema de plantio direto, com o objetivo de mostrar que a viabilidade deste plantio depende do controle eficiente das plantas daninhas. Nesse sistema de cultivo ocorrem algumas espécies de plantas daninhas comumente não observadas no sistema convencional, sendo essas constatações relacionadas ao não-revolvimento do solo, favorecendo o desenvolvimento de espécies de plantas daninhas perenes, e às alterações nas condições de temperatura e incidência de luz no interior do solo, influenciando os mecanismos de dormência das sementes de algumas espécies. A estratégia adequada para o controle das plantas daninhas em plantio direto exige conhecimento da dinâmica populacional do banco de sementes do solo e deve reunir métodos integrados de controle para reduzir o uso de herbicidas. A liberação de substâncias alelopáticas de algumas culturas de cobertura e o efeito supressor da camada de palha são medidas importantes para integrar ao controle químico das plantas daninhas. Entretanto, deve-se atentar para os efeitos negativos sobre algumas espécies de plantas cultivadas. As pesquisas na área de biologia das plantas daninhas e alelopatia das culturas de cobertura, associadas com a tecnologia de aplicação de herbicidas e a agricultura de precisão, poderão contribuir para a otimização do controle das plantas daninhas em áreas de plantio direto.Some important aspects of weed biology and control under no tillage are described to show that the viability of this system depends on weed control efficiently performed. Some of the weeds infesting this cropping system are present in much greater density under the conventional system, this being probably due to the little soil disturbance under no tillage systems, where the occurrence of perennial weeds is more feasible, and changes in the temperature and

  5. Evaluation of Radiological Impacts on the Operating Kartini Reactor and Natural Radioactivity of the Site Plan of Nuclear Power Plant Area

    International Nuclear Information System (INIS)

    Yazid, M; Sutresna, G; Sulistyono, A; Ngasifudin

    1996-01-01

    This radiological impacts evaluation covered of radioactivity in water, soil, grass, air samples and ambient gamma radiation that have been carried out in the Kartini reactor area and in the site plan of nuclear power plan are at Ujung Lemah Abang, Jepara, Central Java. The aim of this research was to determine that radiological impacts in the environment around the Kartini reactor compared to natural radioactivity for site plan of nuclear power plan area. The radioactivity in the water, soil and grass samples ware measured by low background beta counting system and were identified by low background gamma spectrometer. The radioactivity in the air samples was measured by beta portable counting system and the ambient gamma radiation was measured by portable high pressurized ionization chamber model RSS-112 Reuther-Stokes. The reactor data measurement was compared to the site plan of nuclear power plant area data for evaluation of radiological impacts on the operating reactor. From the evaluation and comparison can be concluded there are no indication of the radionuclide release from the reactor operation. The average radiactivity in the water, soil grass and air sample from the reactor area were between 0.17 - 0.61 Bq/1; 0,47 - 0,74 Bq/g; 4.43 - 4.60 Bq/g.ash and 49.53 - 70.90 x 10 Bq/cc. The average radioactivity of those sample from the nuclear power plant area were between 0.06-0.90 Bq/I; 0.02-0.86 Bq/g; 1.68-8.07 Bq/g.ash and 65.0-152.3 x 10 Bq/cc. The ambient gamma radiation were between 6.9-36.7 urad/h for the reactor area and 6.8-19.2 urad/h for the nuclear power plant area

  6. Morfologia de nectários em Leguminosae senso lato em áreas de caatinga no Brasil Nectary morphology of Leguminosae senso lato in areas of dry seasonal forest in Brazil

    Directory of Open Access Journals (Sweden)

    Yanna Melo

    2010-12-01

    Full Text Available Nectários extraflorais (Nefs são glândulas secretoras de néctar encontradas em diversas espécies de Angiospermas, inclusive Leguminosae. Essas estruturas podem se apresentar sob diferentes formas (elevados, embebidos; com ou sem estipe; cores distintas e posições nas plantas (na raque, no pecíolo, sendo essas características relevantes aos estudos de taxonomia e sistemática. Este trabalho analisou a diversidade morfológica dos Nefs em Leguminosae de uma área prioritária para a conservação da caatinga no Estado de Pernambuco. As 35 espécies de Legumionsae estudadas foram coletadas no Município de Mirandiba, no semi-árido Pernambucano, e submetidas às técnicas usuais para análise e descrição morfológica. Entre essas espécies, foram caracterizados Nefs com origem primária (não substitutivos e secundária (substitutivos. Dois diferentes tipos com onze formatos distintos foram encontrados entre elas. Uma grande variedade de localização, coloração, projeção, e dimensão foram registradas aqui. Uma chave de identificação e ilustrações foram elaboradas também. Os dados apresentados aqui ampliam o número de espécies estudadas com Nefs para a família, e também confirmam a importância taxonômica e ecológica dessas estruturas para os legumes da região do semi-árido do Brasil.Extrafloral nectaries (Efns are nectar secreting glands found in many species of Angiosperms, including Leguminosae. These structures have various forms (elevated, embedded; stalk present or not; different colors and positions on the plants (on the rachis, on the petiole, and these characteristics are relevant to taxonomy and morphology studies. This work analyses the morphological diversity of Efns in Leguminosae from a priority conservation area of caatinga in Pernambuco state. The 35 Leguminosae species studied were collected in Mirandiba municipality, a semi-arid region of Pernambuco and submitted to the usual techniques of anatomy and

  7. The European nuclear safety and radiation protection area: steps and prospects; L'Europe de la surete nucleaire et de la radioprotection: grandes etapes et perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Gillet, G. [Autorite de Surete Nucleaire, Dir. des relations internationales 75 - Paris (France)

    2010-11-15

    Launched with enthusiasm and determination in 1957, The European Atomic Energy Community (EAEC - EURATOM), which aimed to promote the development of a 'powerful nuclear industry' in Europe, has not ultimately fulfilled the wishes of its founding fathers. Rapidly, and on a topic as strategic as the peaceful use of the atom, national reflexes prevailed. The Chernobyl disaster, in 1986, also substantially slowed down the use of nuclear energy in Europe. Nuclear safety and radiation protection have followed two different paths. Backed by Chapter III of the EURATOM treaty, over time the EAEC has developed a substantial legislative corpus on radiation protection. Meanwhile, and strange as it may seem, nuclear safety has remained the poor relation, on the grounds that the treaty does not grant EURATOM competence in the area. It is true that legislation was adopted in reaction to Chernobyl, but for a long time there was no specific regulation of nuclear safety in the EU. The European nuclear safety and radiation protection area owes its construction to Community mechanisms as well as to informal initiatives by safety authorities. Today, more than ever, this centre provides consistency, an overall balance which should both strengthen it and impose it as an international reference. Progress can now be expected on waste management, radiation protection and the safety objectives of new reactors. (author)

  8. Project-Based Learning in the Masters degree in Nuclear Engineering at BarcelonaTECH. Experience gained in the area of Management of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Reventos, F.; Vives, E.; Brunet, A.; Sabate, R.; Calvino, F.; Batet, L.

    2014-01-01

    From its first edition, that took place in 2011-2012, the Masters degree in Nuclear Engineering from BarcelonaTECH has been using techniques of Project-Based Learning to fulfill the purpose of training nuclear engineers with a profile suitable for positions in the industry. The Master is sponsored by ENDESA and relies on the collaboration with institutions and companies. The Master is embedded in EMINE, the European Master in Innovation in Nuclear Energy, supported by KIC-InnoEnergy and the European Institute of Technology. (Author)

  9. Project-Based Learning in the Masters degree in Nuclear Engineering at BarcelonaTECH. Experience gained in the area of Management of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Reventos, F.; Vives, E.; Brunet, A.; Sabate, R.; Calvino, F.; Batet, L.

    2014-07-01

    From its first edition, that took place in 2011-2012, the Masters degree in Nuclear Engineering from BarcelonaTECH has been using techniques of Project-Based Learning to fulfill the purpose of training nuclear engineers with a profile suitable for positions in the industry. The Master is sponsored by ENDESA and relies on the collaboration with institutions and companies. The Master is embedded in EMINE, the European Master in Innovation in Nuclear Energy, supported by KIC-InnoEnergy and the European Institute of Technology. (Author)

  10. Variação mensal da deposição de serapilheira em povoamento de Pinus taeda L. em área de campo nativo em Cambará do Sul-RS Monthly variation of litter deposition in Pinus taeda L. stand in native grass area in Cambará do Sul-RS

    Directory of Open Access Journals (Sweden)

    Márcio Viera

    2010-06-01

    Full Text Available Objetivou-se com este trabalho avaliar a deposição de serapilheira em Pinus taeda L., implantado em área de campo nativo, durante um período de três anos (5º ao 7º ano de idade da floresta, no Município de Cambará do Sul, na região dos Campos de Cima da Serra, no Rio Grande do Sul. Foram alocadas quatro parcelas de 18 m x 50 m, de forma ale