WorldWideScience

Sample records for na area nuclear

  1. 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)

  2. 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)

  3. 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

  4. 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)

  5. 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)

  6. 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)

  7. 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

  8. Development of methodologies used in the areas of safeguards and nuclear forensics based on LA-HR-ICP-MS technique; Desenvolvimento de metodologias utilizadas nas areas de salvaguardas e forense nuclear baseadas na tecnica LA-HR-ICP-MS

    Energy Technology Data Exchange (ETDEWEB)

    Marin, Rafael Coelho

    2013-07-01

    Environmental sampling performed by means of swipe samples is a methodology frequently employed by International Atomic Energy Agency (IAEA) to verify if the signatory States of the Safeguards Agreements are conducing unauthorized activities. Swipe samples analysis is complementary to the Safeguards ordinary procedures used to verify the information given by the States. In this work it was described a methodology intending to strengthen the nuclear safeguards and nuclear forensics procedures. The proposal is to study and evaluate the laser ablation high resolution inductively coupled plasma mass spectrometry (LA-HR-ICP-MS) technique as an alternative to analyze the real-life swipe samples. The precision achieved through the standard (CRM - 125A) measurements, represented by the relative standard deviation (RSD), was respectively 1.3 %, 0.2 % e 7.6 % for the {sup 234}U/{sup 238}U, {sup 235}U/{sup 238}U e {sup 236}U/{sup 238}U isotopes ratios. The percent uncertainties (u %), which covers the RSD, ranged from 3.5 % to 29.8 % to the {sup 235}U/{sup 238}U measurements and from 16.6 % to 42.9 % to the {sup 234}U/{sup 238}U isotope ratio. These results were compatible with former studies performed by the LA-HR-ICP-MS that analyzed real-life swipe samples collected at a nuclear facility. Swipe samples collected from several points of the nuclear facility presented enrichment level ranging from (2.3 ± 0.7) % (sample 3) to (17.3 ± 2.8) % (sample 18). They also allowed detecting different enrichment levels within the facility. (author)

  9. A simplified study of public perception in the nuclear field: suggestions for educational campaign for different segments of society; Um estudo simplificado sobre a percepcao publica na area nuclear: sugestoes para campanhas educativas para os diferentes segmentos da sociedade

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Renata Araujo de

    2011-07-01

    During the last years the need for the increase in the electricity energy production as much as in Brazil as in the rest of the world, has raised the tone o the debate about the environmental impacts as a result of these debates, the government and the Non-Governmental Organizations (NGO's) have requested several opinion researches aiming at measuring and evaluating the knowledge and perception of the public in relation to the best non-polluting energy sources. Prior to 2001 these researches would not make any sense in Brazil as the majority of its power grid is made of hydroelectric plants, a renewable energy source. However, when in that year it occurred a drought, the competent authorities have faced the necessity of developing a plan, the National Energy Plan (PNE2030) which recommends, among other objectives, finalizing the construction of the Angra 3 plant and the implementation Df new nuclear plants in places still to be determined. Even considering the complexity of the subject, this paper presents a field research realized from September 28th, 2010 to October 28th, 2010 of the current level of perception of the Brazilian population, specifically the residents of three cities of Rio de Janeiro, about the nuclear area. As a result of this work, it is suggested how the competent authorities should proceed to reach in an efficient manner, by means of communication campaigns both informative and educational, a greater understanding of the population about the proposed subject. (author)

  10. 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

  11. 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

  12. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo Neves Gomes da

    2016-07-01

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

  17. 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)

  18. 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)

  19. 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

  20. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Corbiniano

    2013-07-01

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

  2. 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

  3. 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.

  4. 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

  5. Fishes of Saco do Piraquara de Fora, in a discharge area of liquid effluents from Angra-1 Nuclear Power Plant (CNAAA); Peixes do Saco Piraquara de Fora, ocorrentes na area sob influencia dos efluentes liquidos da CNAAA - indicador biologico e radiologico

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Ademar Ferrari Vaz de; Santoro, Maria Dulce Novaes [Furnas Centrais Eletricas S.A., Angra dos Reis, RJ (Brazil). Lab. de Monitoracao Ambiental

    1996-07-01

    Because the thermal effluents, released from the Unit I condenser system, it was implanted, at discharge area (Saco Piraquara de Fora), a Marine Fauna and Flora Monitoring Program, been necton area part of this, to verify possible impact over fish population, quantitative and qualitative studies were performed. Trichiurus lipeturus and Diapterus rhombeus were chosen as indicators because the high frequencies and abundances. Besides this, Furnas implanted a Radiological Monitoring Program, where samples of fish were collected and analysed by gamma spectrometry, showing the presence of Cs-137 since the pre-operational period, caused by fall out process at the region, from nuclear weapons test at atmosphere. (author)

  6. 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...

  7. 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

  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. 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.)

  10. 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.)

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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).

  16. 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).

  17. 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)

  18. 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)

  19. Pelletizing of NaF granules as adsorbent for fluorides of nuclear fuel materials, (1)

    International Nuclear Information System (INIS)

    Kimura, Syojiro; Tsutsui, Tenson; Kanagawa, Akira.

    1976-01-01

    The pelletizing of NaF granules on laboratory scale used for recovery and purification of fluorides of nuclear fuel materials are investigated, particularity experimental studies on how to pelletize, fluidity of granules and flow rate of the granules in mortar of tablet machine are carried out. As result, added quantity of H 2 O as binder at granulation process of spherical NaF granule influence to yield of NaF granules. The proper quantity of H 2 O to NaF powder is about 18--19%. Friction coefficient of unfixed shape NaF granule is higher than that of spherical granule, in opposition, density of the former granule is lower. So fluidity of unfixed shape NaF granule is low, flow rate of the granules through feeder of tablet machine is slow, and arching on mortar of the tablet machine occurs. Then, some further operation for getting better fluidity needs for pelletizing of NaF granules using unfixed shape granule. The other hand, using spherical NaF granule, continuous pelletizing by commercial tablet machine can be carried out. (auth.)

  20. Centro de Energia Nuclear na Agricultura (CENA) - Sao Paulo, Brazil, - Annual report, 1978

    International Nuclear Information System (INIS)

    Anon.

    The activities carried out at 'Centro de Energia Nuclear na Agricultura (CENA) S.P., Brazil, in 1978 are related, such as : development of research on the use of radioisotopes in crop improvement and plant breeding, as well as in the improvement of animal production; works in collaboration with other entities; personnel formation and scientific exchange with other countries. (M.A.) [pt

  1. 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

  2. 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.

  3. {sup 23}Na nuclear magnetic resonance study of the structure and dynamic of natrolite

    Energy Technology Data Exchange (ETDEWEB)

    Paczwa, Mateusz; Olszewski, Marcin; Sergeev, Nikolaj [Szczecin Univ. (Poland). Inst. of Physics; Sapiga, Aleksej A.; Sapiga, Aleksej V. [Taurida National V.I. Vernadsky Univ., Simferopol, Crimea (Ukraine)

    2015-07-01

    The temperature dependences of nuclear magnetic resonance (NMR) and magic angle spinning (MAS) NMR spectra of {sup 23}Na nuclei in natrolite (Na{sub 2}Al{sub 2}Si{sub 3}O{sub 10} . 2H{sub 2}O) have been studied. The temperature dependences of the spin-lattice relaxation times T{sub 1} in natrolite have also been studied. It has been shown that the spin-lattice relaxation of the {sup 23}Na is governed by the electric quadrupole interaction with the crystal electric field gradients modulated by translational motion of H{sub 2}O molecules in the natrolite pores. The dipolar interactions with paramagnetic impurities become significant as a relaxation mechanism of the {sup 23}Na nuclei only at low temperature (<270 K).

  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. The Na+ transport in gram-positive bacteria defect in the Mrp antiporter complex measured with 23Na nuclear magnetic resonance.

    Science.gov (United States)

    Górecki, Kamil; Hägerhäll, Cecilia; Drakenberg, Torbjörn

    2014-01-15

    (23)Na nuclear magnetic resonance (NMR) has previously been used to monitor Na(+) translocation across membranes in gram-negative bacteria and in various other organelles and liposomes using a membrane-impermeable shift reagent to resolve the signals resulting from internal and external Na(+). In this work, the (23)Na NMR method was adapted for measurements of internal Na(+) concentration in the gram-positive bacterium Bacillus subtilis, with the aim of assessing the Na(+) translocation activity of the Mrp (multiple resistance and pH) antiporter complex, a member of the cation proton antiporter-3 (CPA-3) family. The sodium-sensitive growth phenotype observed in a B. subtilis strain with the gene encoding MrpA deleted could indeed be correlated to the inability of this strain to maintain a lower internal Na(+) concentration than an external one. Copyright © 2013 Elsevier Inc. All rights reserved.

  6. 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)

  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 studies in Goiania urban area: review; Estudos radioecologicos na area urbana de Goiania: revisao

    Energy Technology Data Exchange (ETDEWEB)

    Rio, Monica Pires do; Amaral, Eliana [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    Studies on the behaviour and transport of {sup 137} Cs in urban areas, including, resuspension and deposition experiments, {sup 137} Cs uptake by leafy vegetables and small domestic animals that accidentally ingested contaminated soil, were performed in a house located at 57{sup t}h Street near the main focus of contamination. The resuspension of surface soil did not contribute much to the spreading of the radionuclide in Goiania, but can lead to the local contamination of vegetables, equipment, structures and other environmental surfaces. The mechanism also presented a seasonal effect. The soil is an important medium for the uptake of {sup 137} Cs by small domestic animals. The street dust sampling is a suitable method to assess the dispersion of {sup 137} Cs in urban areas. After 10 years, the radionuclide activity concentration is restricted only to the initially impacted area an it is decreasing with time. (author) 9 refs., 2 figs, 2 tabs.

  11. 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.

  12. 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)

  13. 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)

  14. Reuse of nuclear byproducts, NaF and HF in metal glass industries

    Energy Technology Data Exchange (ETDEWEB)

    Park, J.W.; Lee, H.W. [Korea Power Engineering Co., Inc., Kyunggi-do (Korea, Republic of); Yoo, S.H.; Moon, H.S.; Cho, N.C. [Korea Nuclear Fuel Co., Ltd., Daejon (Korea, Republic of)

    1997-02-01

    A study has been performed to evaluate the radiological safety and feasibility associated with reuse of NaF(Sodium Fluoride) and HF(Hydrofluoric Acid) which are generated as byproducts from the nuclear fuel fabrication process. The investigation of oversea`s experience reveals that the byproduct materials are most often used in the metal and glass industries. For the radiological safety evaluation, the uranium radioactivities in the byproduct materials were examined and shown to be less than radioactivities in natural materials. The radiation doses to plant personnel and the general public were assessed to be very small and could be ignored. The Korea nuclear regulatory body permits the reuse of NaF in the metal industry on the basis of associated radioactivity being {open_quote}below regulatory concern{close_quote}. HF is now under review for reuse acceptability in the steel and glass industries.

  15. 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

  16. Nuclear astrophysics with DRAGON at ISAC: the 21Na(p, γ)22Mg reaction

    International Nuclear Information System (INIS)

    D'Auria, J.M.

    2003-01-01

    The DRAGON facility at the new intense radioactive beams facility, ISAC, is now operational. It was built to perform studies of radiative alpha and proton capture reactions involving radioactive reactants, and of interest to nuclear astrophysics. The rate of the 21 Na(p, γ) 22 Mg reaction has been measured using inverse kinematics. Resonance strengths have been measured for states of importance for novae explosions. This report will summarize aspects of this study and its impact. (orig.)

  17. Nuclear spin polarized alkali beams (Li and Na): Production and acceleration

    International Nuclear Information System (INIS)

    Jaensch, H.; Becker, K.; Blatt, K.; Leucker, H.; Fick, D.

    1987-01-01

    Recent improvements of the Heidelberg source for polarized heavy ions (PSI) are described. By means of optical pumping in combination with the existing multipole separation magnet the beam figure of merit (polarization 2 x intensity) was doubled. 7 Li and 23 Na atomic beams can now be produced in pure hyperfine magnetic substates. Fast switching of the polarization is achieved by an adiabatic medium field transition. The hyperfine magnetic substate population is determined by laser-induced fluorescence spectroscopy. In routine operation atomic beams with nuclear polarization p α ≥0.85 (α=z, zz) are obtained. The acceleration of polarized 23 Na - ions by a 12 MV tandem accelerator introduces a new problem: the energy at the terminal stripper foil is not sufficient to produce a usable yield of naked ions. For partially stripped ions hyperfine interaction of the remaining electrons with the nuclear spin reduces the nuclear polarization. Using in addition the Heidelberg postaccelerator 23 Na 9+ beams of energies between 49 and 184 MeV were obtained with an alignment on target of P zz ≅0.45. 7 Li beams have also been accelerated up to 45 MeV with an alignment of P zz =0.69. (orig.)

  18. 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.)

  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. Nuclear quadrupole interaction measurements of 19F* and 22Na* on Graphite

    International Nuclear Information System (INIS)

    Djoko-Surono, Th; Martin, Peter W

    1996-01-01

    Time differential perturbed angular distribution (TDPAD) technique has been used to investigate nuclear quadrupole interactions of 19 F * and 22 Na * in graphite. We concentrated the measurements on pseudo single crystal graphite called Highly Oriented Pyrolytic Graphite for it has an ordered structure in which the c-axes of the microcrystals aligned in a certain direction with the mosaic spread less than 1 o , while the a- and b-axes randomly oriented on a plane perpendicular to the c-axes. Interactions between quadrupole moment of 19 F * and 22 Na * with its surroundings electric field gradient were studied by detecting the γ-rays distribution, W(Θ,t). For 1 9F * we found one static interaction. The corresponding electric field gradient was V zz =3.24(19)x10 22 V/m 2 . In the case of 22 Na * we found no evidence of nuclear quadrupole interaction, however, we were able to conclude that |QV 22 | 19 bV/m 2 . Using theoretical calculation Q=0.06 barn, we find that |V zz | 20 V/m 2 . These results indicate that the value efg depend on two factors, the host crystal and the core electrons. The core electrons contribution to the total efg is considerably large

  4. Securing a better future for all: Nuclear techniques for global development and environmental protection. NA factsheet on nuclear physics: Facilitating the peaceful and practical uses of nuclear science

    International Nuclear Information System (INIS)

    2012-01-01

    When properly applied, nuclear science - the study of atomic nuclei and other subatomic particles - can contribute in many ways to the health, development and security of communities around the world. In this context, the IAEA plays an important role in helping interested Member States develop the capabilities and infrastructure necessary to manage their own programmes devoted to nuclear and radiological applications. The IAEA's nuclear science programme helps Member States to establish sound frameworks for the efficient, safe and secure use of new nuclear technologies, including accelerator facilities, research reactors and future nuclear fusion facilities. By applying nuclear technologies in a wide variety of areas such as energy production, health care, food and agriculture, industry and the environment, Member States can benefit immensely from the ensuing socioeconomic developments, as well as providing better living conditions for their citizens.

  5. Pulse-shape discrimination between electron and nuclear recoils in a NaI(Tl) crystal

    Energy Technology Data Exchange (ETDEWEB)

    Lee, H.S. [Department of Physics, Ewha Womans University,Seoul 120-750 (Korea, Republic of); Adhikari, G.; Adhikari, P. [Department of Physics, Sejong University,Seoul 143-747 (Korea, Republic of); Choi, S. [Department of Physics and Astronomy, Seoul National University,Seoul 151-747 (Korea, Republic of); Hahn, I.S. [Department of Science Education, Ewha Womans University,Seoul 120-750 (Korea, Republic of)

    2015-08-18

    We report on the response of a high light-output NaI(Tl) crystal to nuclear recoils induced by neutrons from an Am-Be source and compare the results with the response to electron recoils produced by Compton-scattered 662 keV γ-rays from a {sup 137}Cs source. The measured pulse-shape discrimination (PSD) power of the NaI(Tl) crystal is found to be significantly improved because of the high light output of the NaI(Tl) detector. We quantify the PSD power with a quality factor and estimate the sensitivity to the interaction rate for weakly interacting massive particles (WIMPs) with nucleons, and the result is compared with the annual modulation amplitude observed by the DAMA/LIBRA experiment. The sensitivity to spin-independent WIMP-nucleon interactions based on 100 kg⋅year of data from NaI detectors is estimated with simulated experiments, using the standard halo model.

  6. Pulse-shape discrimination between electron and nuclear recoils in a NaI(Tl) crystal

    International Nuclear Information System (INIS)

    Lee, H.S.; Adhikari, G.; Adhikari, P.; Choi, S.; Hahn, I.S.

    2015-01-01

    We report on the response of a high light-output NaI(Tl) crystal to nuclear recoils induced by neutrons from an Am-Be source and compare the results with the response to electron recoils produced by Compton-scattered 662 keV γ-rays from a 137 Cs source. The measured pulse-shape discrimination (PSD) power of the NaI(Tl) crystal is found to be significantly improved because of the high light output of the NaI(Tl) detector. We quantify the PSD power with a quality factor and estimate the sensitivity to the interaction rate for weakly interacting massive particles (WIMPs) with nucleons, and the result is compared with the annual modulation amplitude observed by the DAMA/LIBRA experiment. The sensitivity to spin-independent WIMP-nucleon interactions based on 100 kg⋅year of data from NaI detectors is estimated with simulated experiments, using the standard halo model.

  7. 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

  8. 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.)

  9. Effect of Na{sub 2}O on aqueous dissolution of nuclear waste glasses

    Energy Technology Data Exchange (ETDEWEB)

    Farooqi, Rahmat Ullah, E-mail: rufarooqi@live.com [Division of Advanced Nuclear Engineering, Pohang University of Science and Technology, 77 Cheongam-Ro, Nam-Gu, Pohang, Gyeongbuk 790-784 (Korea, Republic of); Hrma, Pavel [Division of Advanced Nuclear Engineering, Pohang University of Science and Technology, 77 Cheongam-Ro, Nam-Gu, Pohang, Gyeongbuk 790-784 (Korea, Republic of); Pacific Northwest National Laboratory, Richland, WA (United States)

    2017-04-15

    Sodium oxide is present in the majority of commercial and waste glasses as a viscosity-reducing component. In some nuclear waste glasses, its source is the waste itself. As such, it can limit the waste loading because of its deleterious effect on the resistance of the glass to attack by aqueous media. The maximum tolerable content of Na{sub 2}O in glass depends on the presence and concentration of components that interact with it. To assess the acceptability limits of Na{sub 2}O in the composition region of nuclear waste glasses, we formulated 11 baseline compositions by varying the content of oxides of Si, B, Al, Ca, Zr, and Li. In each of these compositions, we varied the Na{sub 2}O fraction from 8–16 mass% to 23–30 mass%. To each of 146 glasses thus formulated, we applied the seven-day Product Consistency Test (PCT) to determine normalized B and Na releases (r{sub i}, where i ≡ B or Na). Fitting approximation functions ln(r{sub i}/gm{sup −2}) = Σb{sub ij}g{sub j} to r{sub i} data (g{sub j} is the j-th component mass fraction and b{sub ij} the corresponding component coefficient), we showed that the r{sub B} (and, consequently, the initial glass alteration rate) was proportional to the glass component mass fractions in the order Al{sub 2}O{sub 3}Na{sub 2}O

  10. 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)

  11. 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.

  12. 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

  13. 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)

  14. 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)

  15. 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)

  16. Study On Analytical Methods Of Tellurium Content In Natriiodide (Na131I) Radiopharmaceutical Solution Produced In The Dalat Nuclear Reactor

    International Nuclear Information System (INIS)

    Vo Thi Cam Hoa; Duong Van Dong; Nguyen Thi Thu; Chu Van Khoa

    2007-01-01

    This report describes the practical methods for analyzing of Tellurium content in Na 131 I solution produced at the Dalat Nuclear Research Institute. We studied analytical methods to control Tellurium content in final Na 131 I solution product used in medical purposes by three methods such as: spot test, gamma spectrometric and spectrophotometric methods. These investigation results are shown that the spot test method is suitable for controlling Tellurium trace in the final product. This spot test can be determinate Tellurium trace less than 10 ppm and are used to quality control of Na 131 I solution using in medical application. (author)

  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. /sup 14/N nuclear quadrupole resonance in ferroelectric sodium nitrite NaNO/sub 2/

    Energy Technology Data Exchange (ETDEWEB)

    Singh, S; Singh, K [Defence Science Lab., Delhi (India)

    1974-06-01

    Nuclear quadrupole resonance has been studied in ferroelectric sodium nitrite (NaNO/sub 2/) from 77 K to its phase transition point 437 K. The three rotational frequencies ..omega../sub c/ = 190 cm/sup -1/, ..omega../sub b/ = 120 cm/sup -1/ and ..omega../sub c/ = 227 cm/sup -1/ and their temperature variation when fitted in the Bayer-Kushida theory predict the temperature dependence of nqr frequencies reasonably well. A second order phase transition is found to occur at 180 K which is in confirmity with the one found earlier from thermal expansion and dielectric studies. The shift in resonance frequencies is seen to occur mainly by rotation around the 'c' axis and hence it is inferred that the mechanism of polarization reversal is intimately connected with orientational motion about 'c' axis. (auth)

  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. Contamination monitoring of Na 131 I levels in therapy unit of Research Institute for Nuclear Medicine, Tehran University of Medical Sciences by indirect method (Wipe test)

    International Nuclear Information System (INIS)

    Beiki, D.; Shahhosseini, S.; Eftekhari, M.; Takavar, A.; Fard-Esfahani, A.

    2003-01-01

    Contamination with radiopharmaceuticals in nuclear medicine centres in addition to being a health concern requires time consuming decontamination efforts. According to Nuclear Regulatory Commission Contamination should be monitored in nuclear medicine centers where radiopharmaceuticals are prepared and administrated at the end of each working session; otherwise, contamination spread to other areas not only equipment but also personnel and other people will be expected. The wipe test for the presence of radioactivity is accomplished by wiping the surface over an area approximately 100 cm 2 with an absorbent paper, then counting it in an appropriate radiation detector. In this study, contamination monitoring of patient's rooms (4 rooms), entrance corridor, patient's corridor, waiting room, control room (nursing station), radiopharmaceutical storage room in therapy unit of Research Institute for Nuclear Medicine, Shariati hospital was performed by indirect method. Based on the results, some areas including storage room were contaminated. There was also a direct relationship between dose administrated and levels of contamination in patient's rooms. Regarding high uptake of iodine by thyroid gland and damaging effects of Na 131 I, weekly wipe tests are required to determine the level of contamination. Patient's rooms after discharging the patients and before re hospitalization specially should be checked. If these tests reveal contamination over standard levels, appropriate decontamination procedures should be carried out immediately

  1. 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.)

  2. 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

  3. 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)

  4. 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

  5. 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

  6. 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

  7. 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)

  8. 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)

  9. 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)

  10. 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

  11. 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

  12. 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

  13. Influence of communication on public opinion about nuclear energy; Influencia da comunicacao na aceitacao publica da energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Everton de Almeida [ELETROBRAS Termonuclear S.A., (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    Public opinion on risks and benefits associated to nuclear energy is depending on psychological and social factors and mainly on the communication strategy used to transfer knowledge and facts about nuclear technology to the public. In this work, the individual and collective communication process and the influences on the public opinion on nuclear energy will be analyzed. (author) 3 refs., 1 fig.

  14. 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)

  15. Professional Nuclear Materials Management; Gestion Industrielle des Matieres Nucleaires; Obrashchenie s yadernymi materialami na professional'nom urovne; Administracion Eficiente de Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Forcella, A. A.; O' Leary, W. J. [Allis-Chalmers Manufacturing Company, Bethesda, MD (United States)

    1966-02-15

    This paper describes the scope of nuclear materials management for a typical power reactor in the United States of America. Since this power reactor is financed by private capital, one of the principal obligations of the reactor operator is to ensure that the investment is protected and will furnish an adequate financial return. Because of the high intrinsic value of nuclear materials, appropriate security and accountability must be continually exercised to minimize losses beyond security and accountability for the nuclear materials. Intelligent forethought and planning must be employed to ensure that additional capital is not lost as avoidable additional costs or loss of revenue in a number of areas. The nuclear materials manager must therefore provide in advance against the following contingencies and maintain constant control or liaison against deviations from planning during (a) pre-reactor acquisition of fuel and fuel elements, (b) in-reactor utilization of the fuel elements, and (c) post-reactor recovery of fuel values. During pre-reactor planning and operations, it is important that the fuel element be designed for economy in manufacture, handling, shipping, and replaceability. The time schedule for manufacturing operations must minimize losses of revenue from unproductive dead storage of high cost materials. For in-reactor operations, the maximum achievable burn-up of the fissionable material must be obtained by means of appropriate fuel rearrangement schemes. Concurrently the unproductive down-time of the reactor for fuel rearrangement, inspections, and the like must be minimized. In the post-reactor period, when the fuel has reached a predetermined depletion of fissionable material, the nuclear materials manager must provide for the most economical reprocessing and recovery of fissionable values and by-products. Nuclear materials management is consequently an essential factor in achieving competitive fuel cycle and unit energy costs with power reactors

  16. 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

  17. 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

  18. 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)

  19. 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)

  20. 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

  1. 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.

  2. 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.

  3. 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

  4. Pelletizing of NaF granules as adsorbent for fluorides of nuclear fuel materials, (2)

    International Nuclear Information System (INIS)

    Kimura, Syojiro; Tsutsui, Tenson; Kanagawa, Akira.

    1976-01-01

    Experimental studies on compressibility of NaF granules are investigated. Brittleness and porosity of a tableted pellet depend on compressive power applied to the granules. Relation of the compressive power and distortion of NaF granules agree with Kawakita's formula. About the brittleness of NaF pellet tableted with optional pressure, the follow experimental formula is formed between axial destructive power and compressive power. Dsub(p)=f.psup(n) Then, relation of the axial destructive power and porosity of NaF pellet is given from the above mentioned experimental formula and Kawakita's formula. At the lower value of the porosity than 0.4, the axial destructive power varies steeply as compared with variation of the porosity. At optional porosity, the brittleness of the tableted NaF pellet are lower than Harshow Chem. Co. NaF.HF pellet. So it requires some process raising the brittleness of the pellet after the compression. (auth.)

  5. 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

  6. 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)

  7. 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)

  8. 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.

  9. 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

  10. 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

  11. 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

  12. 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.).

  13. 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.)

  14. 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

  15. Radiological respiratory protection in Angra-1 Nuclear Power Plant; Protecao respiratoria radiologica na Usina Nuclear de Angra

    Energy Technology Data Exchange (ETDEWEB)

    Amaral, Marcos A. do [Furnas Centrais Eletricas S.A., Angra dos Reis, RJ (Brazil). Central Nuclear de Angra I. Div. de Protecao Radiologica e Ambiental

    1996-07-01

    The present paper has the purpose to describe the actual situation of the Radiological respiratory Protection in Angra I Nuclear Power Plant, the difficulties found and the goals to achieve, in order of the radiological protection excellence. (author)

  16. 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)

  17. 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.

  18. 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)

  19. 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

  20. 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

  1. 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.

  2. Estimation of radioactive effluents concentrations in the vicinity of nuclear power plant; Predviduvanje na koncentraciite na radioaktivni aerozagaduvaci vo okolinata na nuklearni energetski postrojni

    Energy Technology Data Exchange (ETDEWEB)

    Arsov, Lj [Elektrostopanstvo, Skopje (Yugoslavia)

    1977-07-01

    This paper deals with the problem of mathematical prediction of radioactive effluent concentrations around nuclear power plants. This mathematical model which describes the behaviour of the effluent in the atmosphere here in after is expanded and adapted for radioactive effluent treatment. In this way the mathematical model includes the description of the following effects: the rise of plume caused by its vertical momentum and its heat content, wind velocity profile and vertical growth of the coefficient of diffusion, fallout under gravity, ground deposition, precipitation scavenging, and radioactive decay. The advanced computer program DIFFUS has been applied to evaluate the ground concentration of the nuclides of I, which constitute the greatest risk for population.(author)

  3. 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)

  4. 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.

  5. 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

  6. 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

  7. 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

  8. 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.)

  9. 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.

  10. 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

  11. 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

  12. Repercussoes do pet-saude na formacao de estudantes da area da saude

    Directory of Open Access Journals (Sweden)

    Paula Hubner Freitas

    2013-09-01

    Full Text Available OBJETIVO: O estudo teve como objetivo conhecer as repercussões do Programa de Educação pelo Trabalho para a Saúde/PET-Saúde na formação de estudantes da área da saúde. METODOS: Configura-se como exploratório-descritivo, com abordagem qualitativa.Fizeram parte do estudo, vinte estudantes participantes do PET-Saúde. A técnica de coleta de dados foi a entrevista semi-estruturada e o método de análise dos dados empregado, a análise de conteúdo temática. RESULTADOS: Os dados sinalizam que o PET-Saúde configura-se como um programa facilitador para a busca da integralidade e que proporciona articulação teórica-prática entre estudantes, serviço de saúde e comunidade, o que é imprescindível para a reorientação da formação em saúde. CONCLUSÃO: Conclui-se que o desafio centra-se na formação crítico-reflexiva de profissionais da área da saúde, apontando para novos comportamentos e atitudes.

  13. 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)

  14. 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)

  15. Securing a better future for all: Nuclear techniques for global development and environmental protection. NA factsheet on nuclear sciences and applications partnerships: Making a difference together

    International Nuclear Information System (INIS)

    2012-01-01

    The IAEA has a long history of cooperation with other international organizations, regional agencies, non-governmental organizations (NGOs), local and national governments, research and academic institutions. These cooperative efforts make it possible for the IAEA to implement many of its projects undertaken in the area of nuclear applications for peaceful purposes.

  16. 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)

  17. 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

  18. 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)

  19. 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.)

  20. 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)

  1. Flow Components in a NaK Test Loop Designed to Simulate Conditions in a Nuclear Surface Power Reactor

    Science.gov (United States)

    Polzin, Kurt A.; Godfroy, Thomas J.

    2008-01-01

    A test loop using NaK as the working fluid is presently in use to study material compatibility effects on various components that comprise a possible nuclear reactor design for use on the lunar surface. A DC electromagnetic (EM) pump has been designed and implemented as a means of actively controlling the NaK flow rate through the system and an EM flow sensor is employed to monitor the developed flow rate. These components allow for the matching of the flow rate conditions in test loops with those that would be found in a full-scale surface-power reactor. The design and operating characteristics of the EM pump and flow sensor are presented. In the EM pump, current is applied to a set of electrodes to produce a Lorentz body force in the fluid. A measurement of the induced voltage (back-EMF) in the flow sensor provides the means of monitoring flow rate. Both components are compact, employing high magnetic field strength neodymium magnets thermally coupled to a water-cooled housing. A vacuum gap limits the heat transferred from the high temperature NaK tube to the magnets and a magnetically-permeable material completes the magnetic circuit. The pump is designed to produce a pressure rise of 5 psi, and the flow sensor's predicted output is roughly 20 mV at the loop's nominal flow rate of 0.5 GPM.

  2. Low-Surface-Area Hard Carbon Anode for Na-Ion Batteries via Graphene Oxide as a Dehydration Agent

    Energy Technology Data Exchange (ETDEWEB)

    Luo, W; Bommier, C; Jian, ZL; Li, X; Carter, R; Vail, S; Lu, YH; Lee, JJ; Ji, XL

    2015-02-04

    Na-ion batteries are emerging as one of the most promising energy storage technologies, particularly for grid-level applications. Among anode candidate materials, hard carbon is very attractive due to its high capacity and low cost. However, hard carbon anodes often suffer a low first-cycle Coulombic efficiency and fast capacity fading. In this study, we discover that doping graphene oxide into sucrose, the precursor for hard carbon, can effectively reduce the specific surface area of hard carbon to as low as 5.4 m(2)/g. We further reveal that such doping can effectively prevent foaming during caramelization of sucrose and extend the pyrolysis burnoff of sucrose caramel over a wider temperature range. The obtained low-surface-area hard carbon greatly improves the first-cycle Coulombic efficiency from 74% to 83% and delivers a very stable cyclic life with 95% of capacity retention after 200 cycles.

  3. 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

  4. Thermogravimetric and nuclear magnetic resonance study of hydrated Na-β''-alumina

    International Nuclear Information System (INIS)

    Donoso, P.; Panepucci, H.; Gobato, Y.G.; Oliveira, L.N.; Souza, D.P.F. de

    1990-01-01

    This paper reports thermogravimetric and proton spin-lattice relaxation times measurement of hydrated Na-β''-alumina, which yield information about the identification of the sites where the loosely bound water molecules are located in the polycrystalline sample. It examines also the influence of impurities on the motion of the protons. (autor) [pt

  5. Crystalline phase of sodium germanate system determined by x-ray diffraction and 23Na magic angle spinning nuclear magnetic resonance

    International Nuclear Information System (INIS)

    Hussin, R.; Holland, D.; Dupree, R.

    2000-01-01

    Crystalline products of sodium germanate glasses system with composition from 10 mol% to 50 mol% Na 2 O have been investigated using 23 Na magic angle spinning (MAS) nuclear magnetic resonance (NMR) spectroscopy and x-ray diffraction (XRD). Fitting of the 23 Na NMR spectra of the crystalline phases concerning different crystallographically sodium atom in sodium germanate system are reasonably reproducible as observed by the spectra obtained. The line shape simulations of the 23 Na NMR spectra yielded NMR quadrupolar parameters such as nuclear quadrupole coupling constants (C Q ), asymmetry parameters (η), and isotropic chemical shifts (δ i ). 23 Na NMR isotropic chemical shift may also provide further information on the structural environment of the sodium atom. A simple correlation between structure and NMR parameters to be tested can be used to probe the structure of sodium germanate glasses. The experimental 23 Na chemical shifts correlate well with an empirical shift parameter based on the total oxygen-cation bond valence and Na-O distances of all oxygen atoms in the first coordination sphere of the sodium cation. In this study the different phases in the sodium germanate system were identified. These results show that 23 Na NMR can provide examples of the types of structural information for sodium germanate system. (Author)

  6. 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

  7. 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

  8. 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.

  9. 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)

  10. 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

  11. Application of nuclear magnetic resonance in osteoporosis evaluation; Aplicacoes de ressonancia magnetica nuclear na avaliacao de osteoporose

    Energy Technology Data Exchange (ETDEWEB)

    Giannoni, Ricardo A., E-mail: giannoni@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Montrazi, Elton T.; Bonagamba, Tito J., E-mail: elton.montrazi@gmail.com, E-mail: tito@ifsc.usp.br [Universidade de Sao Paulo (IFSC/USP), Sao Carlos, SP (Brazil). Inst. de Fisica; Cesar, Reinaldo, E-mail: reinaldofisica@gmail.com [Universidade de Sao Paulo (EESC/USP), Sao Carlos, SP (Brazil). Escola de Engenharia

    2013-07-01

    In this work, initially ceramic samples of known porosity were used. These ceramic samples were saturated with water. The nuclear magnetic resonance signal due to relaxation processes that the hydrogen nucleus water contained in the pores of this ceramic material was measured. Then these samples were subjected to a process of drying and measures successively. As the water contained in pores greater evaporates the intensity of signal decreases and shows the sign because of the smaller pores. The analysis of this drying process gives a qualitative assessment of the pore size of the material. In a second step, bones of animals of unknown porosity underwent the same methodology for evaluating osteoporosis. Also a sample of human vertebra in a unique manner, with the same purpose was measured. Combined with other techniques is a quantitative evaluation of the possible porosity.

  12. 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

  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. Diffusion and the dynamics of displacive phase transitions in cryolite (Na3AlF6) and chiolite (Na5Al3F14): Multi-nuclear NMR studies

    Science.gov (United States)

    Spearing, Dane R.; Stebbins, Jonathan F.; Farnan, Ian

    1994-10-01

    Cryolite is a mixed-cation perovskite (Na2(NaAl)F6) which undergoes a monoclinic to orthorhombic displacive phase transition at ˜550° C. Chiolite (Na5Al3F14) is associated with cryolite in natural deposits, and consists of sheets of corner sharing [AlF6] octahedra interlayered with edge-sharing [NaF6] octahedra. Multi-nuclear NMR line shape and relaxation time (T1) studies were performed on cryolite and chiolite in order to gain a better understanding of the atomic motions associated with the phase transition in cryolite, and Na diffusion in cryolite and chiolite. 27Al, 23Na, and 19F static NMR spectra and T1's in cryolite suggest that oscillatory motions of the [AlF6] octahedra among four micro-twin and anti-phase domains in α-cryolite begin at least 150° C below the transition temperature and persist above it. Variable temperature 23Na MAS NMR further indicates diffusional exchange at a rate of at least 13 kHz between the Na sites by the time the transition temperature is reached. 27Al and 23Na T1's show the same behavior with increasing temperature, indicating the same relaxation mechanisms are responsible for both. The first order nature of the cryolite transition is apparent as a jump in the 23Na and 27Al T1's. Above the transition temperature, the T1's decrease slightly indicating that the motions responsible for the drop in T1, are still present above the transition, further supporting the dynamic nature of the high temperature phase of cryolite. Chiolite 23Na static spectra decrease in linewidth with increasing temperature, indicating increased Na diffusion, which is interpreted as occurring within the [NaF6] sheets in the chiolite structure, but not between the two different Na sites. 27Al and 23Na T1's show similar behavior as in cryolite, but there is no discontinuity due to a phase transition. 19F T1's are constant from room temperature to 150° C indicating no oscillatory motion of the [AlF6] octahedra in chiolite.

  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. Securing a better future for all: Nuclear techniques for global development and environmental protection. NA factsheet on nuclear sciences and applications collaborating centres: Establishing a culture of cooperation

    International Nuclear Information System (INIS)

    2012-01-01

    As a large international organization with a variety of programmes, initiatives and laboratories, one of the mandates of the IAEA is to promote the peaceful use of nuclear techniques worldwide while also collaborating with other institutions in its Member States in order to implement part of its approved activities. In this regard, the IAEA designates selected institutions as official IAEA collaborating centres (IAEA-CCs). Recognizing the need to preserve and transfer nuclear knowledge, the IAEA-CCs are dedicated to furthering the research, development and training in peaceful applications of nuclear science and technology. By working alongside various nuclear related institutions from around the world, the IAEA contributes to reaching important targets laid out by the United Nations Millennium Development Goals. The IAEA-CCs are, in general, scientific institutions such as laboratories, universities, research facilities, etc., that receive public recognition by the IAEA and have been designated to collaborate with the IAEA in a variety of fields, such as food safety, environmental protection, water resources and human health. In line with the objectives of the IAEA, IAEA-CCs are expected to further the research, development and training in the peaceful applications of nuclear science and technology. Through these research and academic institutions, Member States can assist the IAEA with their own original research, development and training in nuclear technologies. As a cooperative mechanism, the IAEA-CC is also efficient, as it encourages centres to share resources, knowledge and expertise. One of the goals of the IAEA-CC is also to help developing Member States expand their capabilities in these areas and thus improve the quality of life of their citizens. So far, the IAEA-CC has led to socioeconomic benefits in many parts of the world, from Asia to Latin America.

  20. R2NA: Received Signal Strength (RSS Ratio-Based Node Authentication for Body Area Network

    Directory of Open Access Journals (Sweden)

    Yang Wu

    2013-12-01

    Full Text Available The body area network (BAN is an emerging branch of wireless sensor networks for personalized applications. The services in BAN usually have a high requirement on security, especially for the medical diagnosis. One of the fundamental directions to ensure security in BAN is how to provide node authentication. Traditional research using cryptography relies on prior secrets shared among nodes, which leads to high resource cost. In addition, most existing non-cryptographic solutions exploit out-of-band (OOB channels, but they need the help of additional hardware support or significant modifications to the system software. To avoid the above problems, this paper presents a proximity-based node authentication scheme, which only uses wireless modules equipped on sensors. With only one sensor and one control unit (CU in BAN, we could detect a unique physical layer characteristic, namely, the difference between the received signal strength (RSS measured on different devices in BAN. Through the above-mentioned particular difference, we can tell whether the sender is close enough to be legitimate. We validate our scheme through both theoretical analysis and experiments, which are conducted on the real Shimmer nodes. The results demonstrate that our proposed scheme has a good security performance.

  1. 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)

  2. 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

  3. 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

  4. 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)

  5. 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)

  6. 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)

  7. 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.

  8. 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)

  9. 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.)

  10. 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

  11. Nuclear spin phonon relaxation by Raman process in Na{sub 3}H(SO{sub 4}){sub 2} single crystals with the electric-quadrupole-type interaction using {sup 1}H and {sup 23}Na NMR

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Ae Ran [Department of Science Education, Jeonju University, Jeonju 560-759, Chonbuk (Korea, Republic of)], E-mail: aeranlim@hanmail.net; Shin, Chang Woo [Solid State Analysis Team, Korea Basic Science Institute, Daegu 702-701 (Korea, Republic of)

    2008-11-30

    Successive phase transitions in a Na{sub 3}H(SO{sub 4}){sub 2} single crystal were found at 296, 513, and 533 K. To investigate the mechanism of the phase transition at 296 K, the {sup 1}H and {sup 23}Na spin-lattice relaxation time and the spin-spin relaxation time of Na{sub 3}H(SO{sub 4}){sub 2} were measured near the phase transition temperature using a FT NMR spectrometer. The spin-lattice relaxation time, T{sub 1}, for {sup 1}H in Na{sub 3}H(SO{sub 4}){sub 2} crystals exhibits a minimum below T{sub C1} (=296 K) indicating the presence of distinct molecular motion governed by the Bloembergen-Purcell-Pound (BPP) theory. Although the results for the {sup 1}H and {sup 23}Na relaxation times provide no evidence of the phase transition at T{sub C1}, the separation of the {sup 23}Na resonance lines changes abruptly at T{sub C1}. The phase transition at 296 K produces a change in the separation of the Na resonance line that is associated with a change in the atomic positions in the vicinity of the Na ions. Also, the nuclear spin-lattice relaxation process in Na{sub 3}H(SO{sub 4}){sub 2} crystals with the electric-quadrupole-type interaction proceed via Raman process. These results are compared with those obtained for other M{sub 3}H(SO{sub 4}){sub 2} (M=K, Rb, and Cs) crystals, which have similar hydrogen-bonded structures.

  12. 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.

  13. 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.

  14. 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)

  15. 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)

  16. 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

  17. 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

  18. 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)

  19. 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)

  20. 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

  1. Gill area, permeability and Na+ ,K+ -ATPase activity as a function of size and salinity in the blue crab, Callinectes sapidus.

    Science.gov (United States)

    Li, Tiandao; Roer, Robert; Vana, Matthew; Pate, Susan; Check, Jennifer

    2006-03-01

    Juvenile blue crabs, Callinectes sapidus, extensively utilize oligohaline and freshwater regions of the estuary. With a presumptively larger surface-area-to-body weight ratio, juvenile crabs could experience osmo- and ionoregulatory costs well in excess of that of adults. To test this hypothesis, crabs ranging over three orders of magnitude in body weight were acclimated to either sea water (1,000 mOsm) or dilute sea water (150 mOsm), and gill surface area, water and sodium permeabilities (calculated from the passive efflux of 3H2O and 22Na+), gill Na+, K+ -ATPase activity and expression were measured. Juveniles had a relatively larger gill surface area; weight-specific gill surface area decreased with body weight. Weight-specific water and sodium fluxes also decreased with weight, but not to the same extent as gill surface area; thus juveniles were able to decrease gill permeability slightly more than adults upon acclimation to dilute media. Crabs crabs > 5 g in both posterior and anterior gills. Acclimation to dilute medium induced increased expression of Na+, K+ -ATPase and enzyme activity, but the increase was not as great in juveniles as in larger crabs. The increased weight-specific surface area for water gain and salt loss for small crabs in dilute media presents a challenge that is incompletely compensated by reduced permeability and increased affinity of gill Na+, K+ -ATPase for Na+. Juveniles maintain osmotic and ionic homeostasis by the expression and utilization of extremely high levels of gill Na+, K+ -ATPase, in posterior, as well as in anterior, gills. Copyright 2006 Wiley-Liss, Inc.

  2. 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

  3. 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

  4. Measurement of nuclear reactor noise at low power levels; Merenje nuklearnog reaktorskog suma na malim snagama

    Energy Technology Data Exchange (ETDEWEB)

    Velickovic, Lj; Petrovic, M [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1968-11-15

    mogu da se interpretiraju pomocu prostorno-nezavisne reaktorske teorije. Fizicki analiza reaktorskog suma se ogranicila na odredjivanje odnosa {beta}/l iz autokorelaeionih merenja na snazi od 0,5 W (reaktor 'RB' u Vinci). Analizirane su tri razlicite konfiguracije goriva (resetke koraka 8 cm, 11,3 cm i 14 cm). Pokazano je da je moguce odrediti parametar {beta}/l iz autokorelacionih merenja neutronske gustine sa velikom tacnoscu (nekoliko %). (author)

  5. 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)

  6. 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

  7. Radiative heat transfer in the Na mist dispersion over the hot surface of liquid Na in the cooling system of nuclear reactor

    International Nuclear Information System (INIS)

    Kunitomo, T.; Shafey, H.M.

    1980-01-01

    The analysis has been carried out for the radiative heat transfer in the Na mist dispersion enclosed between the hot surface of liquid Na at temperature Tsub(n) and the cold surface of Na deposit at Tsub(c). The model selected for the present study represents the Na mist formed in a sodium cooled fast breeder reactor in which the condensed liquid particles are dispersed in the mixture of the Ar cover gas and the Na vapor. The analysis is based on replacing the inhomogeneous dispersing medium by three discrete homogeneous layers, and formulating the transfer equation for the monochromatic radiation in each layer according to the Chandrasekhar theory. The numerical calculations of the radiative qsub(r) and convective qsub(c) heat transfers have been performed for the wave length range lambda=1.6-30 μm and are compared. The qsub(r) has the same order of magnitude as the qsub(c) for all conditions of the mist dispersions. Both qsub(r) and qsub(c) increase by nearly equal rates with the increase of Tsub(H) and decrease by different rates with increasing Tsub(c). Variations of the particle diameter of the Na mist do not change substantially the qsub(r). Both qsub(r) and qsub(c) decrease slightly with the increase in the total thickness of the Na mist dispersion

  8. 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

  9. 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

  10. 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

  11. 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.

  12. 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

  13. 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)

  14. 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

  15. Characterization of sodium transport in Acholeplasma laidlawii B cells and in lipid vesicles containing purified A. laidlawii (Na+-Mg2+)-ATPase by using nuclear magnetic resonance spectroscopy and 22Na tracer techniques

    International Nuclear Information System (INIS)

    Mahajan, S.; Lewis, R.N.; George, R.; Sykes, B.D.; McElhaney, R.N.

    1988-01-01

    The active transport of sodium ions in live Acholeplasma laidlawii B cells and in lipid vesicles containing the (Na+-Mg2+)-ATPase from the plasma membrane of this microorganism was studied by 23Na nuclear magnetic resonance spectroscopic and 22 Na tracer techniques, respectively. In live A. laidlawii B cells, the transport of sodium was an active process in which metabolic energy was harnessed for the extrusion of sodium ions against a concentration gradient. The process was inhibited by low temperatures and by the formation of gel state lipid in the plasma membrane of this organism. In reconstituted proteoliposomes containing the purified (Na+-Mg2+)-ATPase, the hydrolysis of ATP was accompanied by the transport of sodium ions into the lipid vesicles, and the transport process was impaired by reagents known to inhibit ATPase activity. At the normal growth temperature (37 degrees C), this transport process required a maximum of 1 mol of ATP per mol of sodium ion transported. Together, these results provide direct experimental evidence that the (Na+-Mg2+)-ATPase of the Acholeplasma laidlawii B membrane is the cation pump which maintains the low levels of intracellular sodium characteristic of this microorganism

  16. Thermal expansion of the nuclear fuel-sodium reaction product Na3(U0.84(2),Na0.16(2))O4 - Structural mechanism and comparison with related sodium-metal ternary oxides

    Science.gov (United States)

    Illy, Marie-Claire; Smith, Anna L.; Wallez, Gilles; Raison, Philippe E.; Caciuffo, Roberto; Konings, Rudy J. M.

    2017-07-01

    Na3.16(2)UV,VI0.84(2)O4 is obtained from the reaction of sodium with uranium dioxide under oxygen potential conditions typical of a sodium-cooled fast nuclear reactor. In the event of a breach of the steel cladding, it would be the dominant reaction product forming at the rim of the mixed (U,Pu)O2 fuel pellets. High-temperature X-ray diffraction measurements show that a distortion of the uranium environment in Na3.16(2)UV,VI0.84(2)O4 results in a strongly anisotropic thermal expansion. A comparison with several related sodium metallates Nan-2Mn+On-1 - including Na3SbO4 and Na3TaO4, whose crystal structures are reported for the first time - has allowed us to assess the role played in the lattice expansion by the Mn+ cation radius and the Na/M ratio. On this basis, the thermomechanical behavior of the title compound is discussed, along with those of several related double oxides of sodium and actinide elements, surrogate elements, or fission products.

  17. 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

  18. 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

  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. Activities on nuclear energy introduction in the SR of Serbia without territory of provinces; Aktivnosti na uvodjenju nuklearne energije u SR Srbiji van teritorija SAP

    Energy Technology Data Exchange (ETDEWEB)

    Boljanac, C; Vukovic, D; Putnik, S; Tankosic, D [ZEP, RO ' Nuklearna' u osnivanju, Beograd (Yugoslavia)

    1984-07-01

    In the paper the review of the past and the present activities on nuclear energy introduction in the SR Serbia without territory of provinces is given. The program of the activities in this field includes extensive spectrum of different tasks from investigation of the nuclear raw material and the development in the field of nonconventional uranium production, through studies in fuel cycle area up to the preparatory activities for the nuclear power plant construction. (author)

  2. 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)

  3. 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)

  4. 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)

  5. 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

  6. 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

  7. 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)

  8. 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)

  9. 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)

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. Virtual reality for training of occupationally exposed individuals in nuclear medicine; Realidade virtual para treinamento de indivíduos ocupacionalmente expostos na medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, J.S.; Carvalho, J.B.; Silveira, J.L.; Nascimento, A.C.H.; Mol, A.C.A.; Suita, J.C.; Marins, E.R., E-mail: julianedesacarvalho@gmail.com [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    Applications in virtual environments have been an important tool for education and training of skills in several areas. In Nuclear Medicine Services (NMS), whose environment is susceptible to exposure to ionizing radiation, virtual simulation is a complementary tool to the traditional way of training, able to have the required content by norm, good laboratory practices and radioprotection, interactive form without the exposure of the user. The study consists of the research and unification of recommendations, norms and procedures, collected in the scientific literature and in loco, on the activities of professionals of NMS's radiopharmacy, to define the minimum content for training in order to guide the simulations of a virtual environment.

  18. 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

  19. Experience in training of health personnel for response to radiological and nuclear accidents; Experiencia na capacitacao de profissionais de saude para a resposta a acidentes radiologicos e nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Maurmo, Alexandre M., E-mail: ammaurmo@gmail.com [Fundacao Eletronuclear de Assistencia Medica (CMRI/CTNV/FEAM), Praia Brava, RJ (Brazil). Centro de Medicina das Radiacoes Ionizantes. Centro de Treinamento Prof. Nelson Valverde; Leite, Teresa C.S.B., E-mail: feam@feam-etn.org.br [Fundacao Eletronuclear de Assistencia Medica (CIRA/FEAM), Praia Brava, RJ (Brazil). Centro de Informacoes em Radioepidemiologia

    2013-07-01

    Eletronuclear Healthcare Foundation is the Institution responsible for the actions of health response involving ionizing radiation in the area of Nuclear Power Plant Almirante Alvaro Alberto in Angra dos Reis. Because of their specific assignments and references for being in training health manpower in the field of ionizing radiation developed a range of Training Courses for Professionals Area Health to prepare them for Response to Radiological and Nuclear Accidents. Modules are proposed specifically for the professional response of the Technical Level and Higher Level, the level Pre-hospital and hospital. These modules are further divided into specific levels or modules, Basic or Introductory, Intermediate and Advanced. Are applied pretests and post tests to monitor the content of fixing, maintaining a historical series of reviews. Your content is theoretical and practical applications developed in 30 to 48 hours, with simulations (drills) and distribution of educational materials. We already have more than 80 applications training, focusing on internal staff and external to the institution, developing interesting partner with the Armed Forces and Civil Defense. It still maintained a link on the institution seeking access and download over 400 titles on the subject and exchange of information and experiences. For improving the teaching material, the authors launched in 2011 the first manual in Portuguese on the subject with new revised edition in 2013: 'Manual of Medical Actions In Radiological Emergencies'. The results indicate increased knowledge and appropriateness of the themes and the strategy proposed for this activity, demonstrating yet passed that information can be multiplied and meets the growing demand of the country that has hosted and will host international events relevant at QBNRE risk. (author)

  20. 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

  1. 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

  2. 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)

  3. 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

  4. 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

  5. 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

  6. 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.

  7. 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

  8. Structures and immunolocalization of Na+, K+ -ATPase, Na+ /H+ exchanger 3 and vacuolar-type H+ -ATPase in the gills of blennies (Teleostei: Blenniidae) inhabiting rocky intertidal areas.

    Science.gov (United States)

    Uchiyama, M; Komiyama, M; Yoshizawa, H; Shimizu, N; Konno, N; Matsuda, K

    2012-05-01

    The structure and immunolocalization of the ion transporters Na(+) ,K(+) -ATPase (NKA), Na(+) /H(+) exchanger (NHE3) and vacuolar-type H(+) -ATPase (VHA) were examined in the gills of teleosts of the family Blenniidae, which inhabit rocky shores with vertical zonation in subtropical seas. These features were compared among the following species with different ecologies: the amphibious rockskipper blenny Andamia tetradactylus, the intertidal white-finned blenny Praealticus tanegasimae and the purely marine yaeyama blenny Ecsenius yaeyamaensis. Light and electron microscopic observations indicated that thick gill filaments were arranged close to each other and alternately on two hemibranches of a gill arch in the opercular space of A. tetradactylus. Many mucous cells (MC) and mitochondrion-rich cells (MRC) were present in the interlamellar regions of the gill filament. An immunohistochemical study demonstrated that numerous NKA, NHE3 and some VHA were located predominantly on presumed MRCs of gill filaments and at the base of the lamellae. Analyses using serial (mirror image) sections of the gills indicated that only a few NKA immunoreactive cells (IRC) were colocalized with VHA on some MRCs in the filaments. In the gills of P. tanegasimae, NKA- and NHE3-IRCs were observed in the interlamellar region of the filaments and at the base of the lamellae. VHA-IRCs were located sparsely on the lamellae and filaments. In the gills of E. yaeyamaensis, the lamellae and filaments were thin and straight, respectively. MCs were located at the tip as well as found scattered in the interlamellar region of gill filaments. NKA-, NHE3- and VHA-IRCs were moderately frequently observed in the filaments and rarely on the lamellae. This study shows that the structure and distribution of ion transporters in the gills differ among the three blennid species, presumably reflecting their different ecologies. © 2012 The Authors. Journal of Fish Biology © 2012 The Fisheries Society of the

  9. Brazilian university technology transfer to rural areas Transferência de tecnologia de universidades brasileiras na área rural

    Directory of Open Access Journals (Sweden)

    Enio Marchesan

    2010-10-01

    Full Text Available In agriculture, there is a difference between average yield obtained by farmers and crop potential. There is technology available to increase yields, but not all farmers have access to it and/or use this information. This clearly characterizes an extension and technology transference problem. There are several technology transfer systems, but there is no system to fit all conditions. Therefore, it is necessary to create extension solutions according to local conditions. Another rural extension challenge is efficiency, despite continuous funding reductions. One proposal that has resulted from extension reform worldwide has suggested integration between the public and private sectors. The public universities could play the role of training and updating technical assistance of human resources, which is the one of the main aspects that has limited technology transfer. The objective of this study was to identify approaches to promote technology transfer generated in Brazilian public universities to rural areas through literature review. An experimental approach of technology transfer is presented here where a Brazilian university extension Vice-chancellor incorporates professionals from consolidated research groups according to demand. In this way, public universities take part of their social functions, by integrating teaching, research, and extension.Em agricultura, há diferenças entre a produtividade média obtida pelos produtores e o potencial produtivo dos cultivos. Há informação tecnológica disponível para aumentar a produtividade, mas nem todos os produtores têm acesso e/ou usam a informação. Isso caracteriza claramente um problema de extensão e transferência de tecnologia. Há vários sistemas de transferência de tecnologia, mas, como não há sistema que se ajuste a todas as condições, é necessário criar alternativas adequadas às condições de cada local. Outro desafio da extensão rural é ser eficiente, apesar da cont

  10. 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)

  11. 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

  12. 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

  13. 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.

  14. 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

  15. 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.

  16. 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

  17. Measurement of air dose rates over a wide area around the Fukushima Dai-ichi Nuclear Power Plant through a series of car-borne surveys.

    Science.gov (United States)

    Andoh, Masaki; Nakahara, Yukio; Tsuda, Shuichi; Yoshida, Tadayoshi; Matsuda, Norihiro; Takahashi, Fumiaki; Mikami, Satoshi; Kinouchi, Nobuyuki; Sato, Tetsuro; Tanigaki, Minoru; Takamiya, Koichi; Sato, Nobuhiro; Okumura, Ryo; Uchihori, Yukio; Saito, Kimiaki

    2015-01-01

    A series of car-borne surveys using the Kyoto University RAdiation MApping (KURAMA) and KURAMA-II survey systems has been conducted over a wide area in eastern Japan since June 2011 to evaluate the distribution of air dose rates around the Fukushima Dai-ichi Nuclear Power Plant and to evaluate the time-dependent trend of decrease in air dose rates. An automated data processing system for the KURAMA-II system was established, which enabled rapid analysis of large amounts of data obtained using about 100 KURAMA-II units. The initial data used for evaluating the migration status of radioactive cesium were obtained in the first survey, followed by other car-borne surveys conducted over more extensive and wider measurement ranges. By comparing the measured air dose rates obtained in each survey (until December 2012), the decreasing trend of air dose rates measured through car-borne surveys was found to be more pronounced than those expected on the basis of the physical decay of radioactive cesium and of the air dose rates measured using NaI (Tl) survey meters in the areas surrounding the roadways. In addition, it was found that the extent of decrease in air dose rates depended on land use, wherein it decreased faster for land used as building sites than for forested areas. Copyright © 2014 Elsevier Ltd. All rights reserved.

  18. 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.

  19. 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

  20. 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)

  1. 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

  2. Hydrochemical patterns of a small lake and a stream in an uplifting area proposed as a repository site for spent nuclear fuel, Forsmark, Sweden

    Science.gov (United States)

    Rönnback, Pernilla; Åström, Mats

    2007-10-01

    SummaryThe overall aim of this study was to increase the understanding of the chemical dynamics of small catchments. The focus was on a small oligotropic lake and its major inflow stream in an uplifting area in eastern Sweden (Forsmark) proposed as a repository site for spent nuclear fuel. The hydrochemical sampling campaign lasted for nearly 4 years with sample collection monthly to semi-monthly, and continuous flow measurements carried out over the last 20 months. All this was done as part of the Swedish Nuclear Fuel and Waste Management Company's (SKBs) Site Investigation Programme. The major findings were: (1) as a result of the calcareous overburden caused by redistributed Paleozoic deposits, pH and the Ca and HCO3- concentrations were relatively high in both the stream and lake throughout the period, (2) limnic primary production resulted in decreased concentrations of Ca, HCO3-, NH4+, NO3- and Si, and increased pH and concentrations of chlorophyll a, O 2, DON, POC, PON and POP in the lake in summer, while in other seasons (in winter in particular) when the production was minimal or non-existent the concentrations in the lake and the inflow stream were similar, (3) intrusion of brackish-water resulted in moderately to strongly increased concentrations of Cl -, Na, Mg, Br -, SO42-, K and Sr in the lake: the ratio versus Cl - were for Na and Br - always similar to those in sea water, for Mg and SO42- similar to those in sea water at elevated Cl - concentrations (>3 mM), while K and Sr always occurred in relative excess as compared to sea water, (4) high U concentrations in both the stream and the lake was derived most likely from reduced U-minerals in the overburden and was predicted to be carried to >90% in the form of calcium uranyl carbonate, in a model in which colloidal Fe and Al oxyhydroxides were not considered, (5) the rare earth elements (REEs) had similar concentrations and fractionation patterns in the stream and lake, unlike those found in the

  3. 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

  4. 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

  5. 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

  6. 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)

  7. Ergonomics in the licensing and evaluation of nuclear reactors control room; A ergonomia no licenciamento e na avaliacao de salas de controle de reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Isaac Jose Antonio Luquetti dos [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); Vidal, Mario Cesar Rodriguez [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia de Producao

    2002-07-01

    A nuclear control room is a complex system that controls a thermodynamic process used to produce electrical energy. The operators interact with the control room through interfaces that have significant implications to nuclear plant safety and influence the operator activity. The TMI (Three Mile Island) accident demonstrated that only the anthropometric aspects were not enough for an adequate nuclear control room design. The studies showed that the accident was aggravated because the designers had not considered adequately human factor aspects. After TMI accident, the designers introduce in the nuclear control room development only human factors standards and human factors guidelines. The ergonomics approaches was not considered. Our objective is introduce in nuclear control room design and nuclear control room evaluation, a methodology that. includes human factors standards, human factors guidelines and ergonomic approaches, the operator activity analysis. (author)

  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. 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)

  11. Securing a better future for all: Nuclear techniques for global development and environmental protection. NA factsheet on nuclear sciences and applications: Applying 21st century nuclear science to 21st century problems

    International Nuclear Information System (INIS)

    2012-01-01

    By enhancing the integration across various thematic areas, the IAEA plays a role in helping to address today's emerging challenges. In radiation medicine, for example, nuclear technology is used for the diagnosis and treatment of major non-communicable diseases such as cancer and cardiovascular disorders. The Human Health Campus at http://humanhealth.iaea.org provides on-line resources and learning for health professionals working in radiation medicine. Responding to the world cancer crisis, the IAEA developed a unique initiative, the Programme of Action for Cancer Therapy which works closely with the World Health Organization (WHO) through the WHO-IAEA Joint Programme on Cancer Control. The programme aims at providing assistance to Member States to adopt comprehensive national cancer control programmes that encompass early detection, prevention, cancer diagnosis and treatment and palliative care. In a joint division with the Food and Agriculture Organization of the United Nations, the IAEA assists Member States in applying nuclear techniques to alleviate challenges in food safety, food security and sustainable agricultural development. The IAEA has made significant contributions to helping developing countries adopt sterile insect techniques to suppress and eradicate insect pests that pose a threat to human and to animal health. Using scientific methods based on the tracing of isotopes, the IAEA is improving the management of the world's freshwater resources, a key aspect of sustainable development in the face of climate change. The IAEA also helps Member States monitor known sites of radioactive contamination, as manifested by their ongoing efforts in Japan after the incident at Fukushima. Radioisotope products and radiation technology are essential components for applications across all fields, be it medicine, industry, or agriculture. The demand for the most used radioisotopes has been steadily increasing, such as, for example, fission produced 99Mo and 99m

  12. 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)

  13. 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

  14. 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

  15. 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

  16. 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

  17. 1H nuclear magnetic resonance studies of the conformation of an ATP analogue at the active site of Na,K-ATPase from kidney medulla

    International Nuclear Information System (INIS)

    Stewart, J.M.M.; Grisham, C.M.

    1988-01-01

    1 H nuclear magnetic relaxation measurements have been used to determine the three-dimensional conformation of an ATP analogue, Co(NH 3 ) 4 ATP, at the active site of sheep kidney Na,K-ATPase. Previous studies have shown that Co(NH 4 ) 4 ATP is a competitive inhibitor with respect to MnATP for the Na,K-ATPase and that Mn 2+ bound to a single, high-affinity site on the ATPase can be an effective paramagnetic probe for nuclear relaxation studies of the Na-K-ATPase. From the paramagnetic effect of Mn 2+ bound to the APTase on the longitudinal relaxation rates of the protons of Co(NH 3 ) 4 ATP at the substrate site (at 300 and 361 MHz), Mn-H distances to seven protons on the bound nucleotide were determined. Taken together with previous 31 P nuclear relaxation data, these measurements are consistent with a single nucleotide conformation at the active site. The nucleotide adopts a bent configuration, in which the triphosphate chain lies nearly parallel to the adenine moiety. The glycosidic torsion angle is 35 0 , and the conformation of the ribose ring is slightly N-type. The bound Mn 2+ lies above and in the plane of the adenine ring. The distances from Mn 2+ to N 6 and N 7 are too large for first coordination sphere complexes but are appropriate for second-sphere complexes involving, for example, intervening hydrogen-bonded water molecules. The NMR data also indicate that the structure of the bound ATP analogue is independent of the conformational state of the enzyme

  18. /sup 1/H nuclear magnetic resonance studies of the conformation of an ATP analogue at the active site of Na,K-ATPase from kidney medulla

    Energy Technology Data Exchange (ETDEWEB)

    MacD. Stewart, J.M.; Grisham, C.M.

    1988-06-28

    /sup 1/H nuclear magnetic relaxation measurements have been used to determine the three-dimensional conformation of an ATP analogue, Co(NH/sub 3/)/sub 4/ATP, at the active site of sheep kidney Na,K-ATPase. Previous studies have shown that Co(NH/sub 4/)/sub 4/ATP is a competitive inhibitor with respect to MnATP for the Na,K-ATPase and that Mn/sup 2 +/ bound to a single, high-affinity site on the ATPase can be an effective paramagnetic probe for nuclear relaxation studies of the Na-K-ATPase. From the paramagnetic effect of Mn/sup 2 +/ bound to the APTase on the longitudinal relaxation rates of the protons of Co(NH/sub 3/)/sub 4/ATP at the substrate site (at 300 and 361 MHz), Mn-H distances to seven protons on the bound nucleotide were determined. Taken together with previous /sup 31/P nuclear relaxation data, these measurements are consistent with a single nucleotide conformation at the active site. The nucleotide adopts a bent configuration, in which the triphosphate chain lies nearly parallel to the adenine moiety. The glycosidic torsion angle is 35/sup 0/, and the conformation of the ribose ring is slightly N-type. The bound Mn/sup 2 +/ lies above and in the plane of the adenine ring. The distances from Mn/sup 2 +/ to N/sub 6/ and N/sub 7/ are too large for first coordination sphere complexes but are appropriate for second-sphere complexes involving, for example, intervening hydrogen-bonded water molecules. The NMR data also indicate that the structure of the bound ATP analogue is independent of the conformational state of the enzyme.

  19. Radioactivity of β / γ and the Content of Ca, Fe, Mn, Mg, Na on the Spring of Ponorogo East Java Lime Area

    International Nuclear Information System (INIS)

    Sutjipto

    2002-01-01

    Radioactivity of β / γ and the content of Ca, Fe, Mn, Mg, Na on the source of Ponorogo East-Java lime area has been studied. This research was carried out to know radioactivity of β / γ and the content of Ca, Fe, Mn, Mg, Na on the spring of different three places were Ngebel-lake source, Ngembak source and Gonggang source. Samples taken, preparation and analysis based on the procedures of environmental radioactivity analysis and water sampling guidelines. The instrument used for the analysis radioactivity were low level β counter modified P3TM-BATAN Yogyakarta with detector GM and spectrometer γ with detector Ge(Li). Radioactivity of β (gross) from the source of different three places (β ≤ 1 Bq/L) are lower than the value of PPRI No. 20/1990. Radioactivity of γ comes from the natural radionuclides of Tl-208 and K-40 are lower than 1 Bq/L for the different of three places, respectively. The metals concentration of Ngebel-lake source were Ca ≤ 14.34 ppm; Fe ≤ 0.04 ppm; Mn ≤ 0.02 ppm; Mg ≤ 6.75 ppm; Na ≤ 14.63 ppm, Ngembak source were Ca ≤ 11.6 ppm; Fe ≤ 0.04 ppm; Mn ≤ 0.02 ppm; Mg ≤ 11.13 ppm; Na ≤ 16.75 ppm and Gonggang source were Ca ≤ 13.78 ppm; Fe ≤ 0.26 ppm; Mn ≤ 0.02 ppm; Mg ≤ 6.13 ppm; Na ≤ 15.00 ppm. The water of Ngebel-lake source, Ngembak source and Gonggang source can be classified as B category water based on radioactivity and the content of the metals concentration in its. (author)

  20. 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)

  1. 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.

  2. 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

  3. 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

  4. 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)

  5. Measurement of air dose rates over a wide area around the Fukushima Dai-ichi Nuclear Power Plant through a series of car-borne surveys

    International Nuclear Information System (INIS)

    Andoh, Masaki; Nakahara, Yukio; Tsuda, Shuichi; Yoshida, Tadayoshi; Matsuda, Norihiro; Takahashi, Fumiaki; Mikami, Satoshi; Kinouchi, Nobuyuki; Sato, Tetsuro; Tanigaki, Minoru; Takamiya, Koichi; Sato, Nobuhiro; Okumura, Ryo; Uchihori, Yukio; Saito, Kimiaki

    2015-01-01

    A series of car-borne surveys using the Kyoto University RAdiation MApping (KURAMA) and KURAMA-II survey systems has been conducted over a wide area in eastern Japan since June 2011 to evaluate the distribution of air dose rates around the Fukushima Dai-ichi Nuclear Power Plant and to evaluate the time-dependent trend of decrease in air dose rates. An automated data processing system for the KURAMA-II system was established, which enabled rapid analysis of large amounts of data obtained using about 100 KURAMA-II units. The initial data used for evaluating the migration status of radioactive cesium were obtained in the first survey, followed by other car-borne surveys conducted over more extensive and wider measurement ranges. By comparing the measured air dose rates obtained in each survey (until December 2012), the decreasing trend of air dose rates measured through car-borne surveys was found to be more pronounced than those expected on the basis of the physical decay of radioactive cesium and of the air dose rates measured using NaI (Tl) survey meters in the areas surrounding the roadways. In addition, it was found that the extent of decrease in air dose rates depended on land use, wherein it decreased faster for land used as building sites than for forested areas. - Highlights: • Air dose rates distribution maps were constructed by Car-borne surveys. • KURAMA and KURAMA-II systems have been used for the measurement since 2011. • An automated data processing system for the KURAMA-II system was established. • Decreasing of the dose rates was more pronounced than those of the physical decay. • The dose rates decreased faster for building sites than for forested areas

  6. 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)

  7. The role of nuclear energy in brazilian energy matrix: socioeconomic and environmental aspects; O papel da energia nuclear na matriz energetica brasileira: aspectos socioeconomicos e ambientais

    Energy Technology Data Exchange (ETDEWEB)

    Schirmer, Priscila

    2016-09-01

    With the large increase of energy demand in the world, either for the continued expansion of industrialization, or by the raise of consumption, are increasing the need for energy sources diversification and the search for cleaner alternatives of energy production. Nuclear power has been considered as an option to curb the emission of greenhouse gases and reduce the dependence of fossil fuels. However, nuclear energy is an issue that still causes a lot of doubt and questions, turning the development of this work very important for a better understanding of the lay public as well as to contribute and encourage future research through an assessment of their environmental and socio-economic aspects, discussing the risks, benefits, and an assessment of the expansion of nuclear energy use, including an overview of nuclear energy in Brazil. Concluding that nuclear energy can contribute to the expansion of the Brazilian energy matrix, as the only heat source able to ensure constant supply of energy without emitting greenhouse gases. Considering that Brazil dominates the technology of the nuclear fuel cycle, and has a large reserves of uranium. A larger share of nuclear energy in the Brazilian energy matrix can generate greater diversification of the same, valuing the environmental and economic sustainability of the country and reducing the system's vulnerability. However, nuclear generation should not be considered as the only solution to the energy problems of the country, but make a part of it by the combination with other renewable sources, increasing the diversity and energy security of the country. (author)

  8. 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

  9. 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)

  10. 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)

  11. Use of nuclear magnetic resonance in the characterization of modified clays; Uso da ressonancia magnetica nuclear na caracterizacao de argilas modificadas

    Energy Technology Data Exchange (ETDEWEB)

    Leite, Sidnei Q.M. [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia; Menezes, Sonia M.C. de [PETROBRAS, Rio de Janeiro, RJ (Brazil). Centro de Pesquisas; Gil, Rosane A.S. San [Universidade Federal, Rio de Janeiro, RJ (Brazil). Inst. de Quimica

    1992-12-31

    This work uses NMR spectroscopy with rotation in the {sup 29} Si, {sup 27} Al and {sup 23} Na magic angles for characterization of clays with Si/Al ratio in the range 3.0 - 16,5, obtained by chemical treatment of commercial samples, under different conditions of leaching with mineral acid 5 refs., 2 figs., 2 tabs.

  12. Nuclear pore complex-mediated modulation of TCR signaling is required for naïve CD4+ T cell homeostasis.

    Science.gov (United States)

    Borlido, Joana; Sakuma, Stephen; Raices, Marcela; Carrette, Florent; Tinoco, Roberto; Bradley, Linda M; D'Angelo, Maximiliano A

    2018-05-07

    Nuclear pore complexes (NPCs) are channels connecting the nucleus with the cytoplasm. We report that loss of the tissue-specific NPC component Nup210 causes a severe deficit of naïve CD4 + T cells. Nup210-deficient CD4 + T lymphocytes develop normally but fail to survive in the periphery. The decreased survival results from both an impaired ability to transmit tonic T cell receptor (TCR) signals and increased levels of Fas, which sensitize Nup210 -/- naïve CD4 + T cells to Fas-mediated cell death. Mechanistically, Nup210 regulates these processes by modulating the expression of Cav2 (encoding Caveolin-2) and Jun at the nuclear periphery. Whereas the TCR-dependent and CD4 + T cell-specific upregulation of Cav2 is critical for proximal TCR signaling, cJun expression is required for STAT3-dependent repression of Fas. Our results uncover an unexpected role for Nup210 as a cell-intrinsic regulator of TCR signaling and T cell homeostasis and expose NPCs as key players in the adaptive immune system.

  13. 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.

  14. 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

  15. 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.

  16. 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

  17. 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

  18. 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)

  19. 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

  20. 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

  1. 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

  2. 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.)

  3. 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.

  4. Use of microcontroller in gamma-ray spectrometer construction using NaI(Tl) sensor, with emphasis in multichannel analyzer, to applications in nuclear and environmental geophysics; Uso de microcontrolador na construcao de espectrometro gama com sensor de NaI(Tl), com enfase em analisador multicanal, para aplicacao em geofisica nuclear e ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Nilton

    2005-07-01

    In this work of nuclear geophysical instrumentation the main purpose was the development of a gamma-ray spectrometer prototype with multi channel analyzer, since the spectroscopic amplifier until your firmware. The heart of the digital part was an ATMEL 8 bits microcontroller (AT89S8252). All circuits were made and assembled in the Laboratory of Applied Geophysical Instrumentation (LIGA) of IAG-USP. A microcontroller software was completely developed in C ANSI language using the Small Device C Compiler version 2.4.8, that is a free software distributed under General Public License (GPL). At first, microcontroller was used to change all digital circuit of one classic SCINTREX GAD-6 differential gamma-ray spectrometer. Measurement times with order of 2 days became possible, and it could work in non climate ambient. Then, after this stage, had been started the development of a multichannel analyzer (MCA) working in pulse height analyzer mode with 4096 channels capacity, to use in many kinds of nuclear detection. Besides it, was developed an automatic gain system for photopeak stabilization, by the use of one radioactive source ({sup 133}Ba). This automatic gain system is very important in the case of NaI(Tl) scintillometric detectors, due PMT sensitivity with temperature and aging of some laboratory electronic circuits. Two power supplies with high stability, using pulse width modulation (PWM) techniques were developed, in order to all system became free of electrical line break off. One PWM power polarizes a photo multiplier tube (PMT) with high voltage and another supplies remaining developed circuits. Calibration in energy using standards sources {sup 137}Cs and {sup 60}Co showed that gamma detector developed has a good linearity and low thermal drift, even working in absent of air-conditioned. Concentrations measurements of K, U and Th were made in samples of soils, vegetables, etc. (author)'

  5. 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)

  6. 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)

  7. Determination of Solar Irradiation in Urban Areas with an Open Source GIS Model: Application on the Example of the Rožna dolina in Ljubljana, Slovenia

    Directory of Open Access Journals (Sweden)

    Alen Mangafić

    2017-10-01

    Full Text Available The determination of solar irradiation is crucial when planning the installation of solar systems. There are different GIS models for determining solar irradiation, which differ from each other in terms of input data, hardware requirements, performance, reliability and suitability, depending on the specificity of the study area and the nature of the study. Because of their diversity, urban areas pose a greater challenge for the estimation of the potential of the received solar energy. In the article we offered a methodology for determining the irradiation of urban area roofs using the GRASS GIS model r.sun, which makes the computation with high resolution spatial, atmospheric and meteorological data. The used input data is freely available for the entire territory of Slovenia. The proposed methodological approach was tested in the area of the town quarter Rožna dolina with the northern part of Vič. The area is very diverse according to the typology of the built objects, the land cover and altitude differences.

  8. 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)

  9. 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.

  10. 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)

  11. 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

  12. Estimation of covariances of 16O, 23Na, Fe, 235U, 238U and 239Pu neutron nuclear data in JENDL-3.2

    International Nuclear Information System (INIS)

    Shibata, Keiichi; Nakajima, Yutaka; Kawano, Toshihiko; Oh, Soo-Youl; Matsunobu, Hiroyuki; Murata, Toru.

    1997-10-01

    Covariances of nuclear data have been estimated for 6 nuclides contained in JENDL-3.2. The nuclides considered are 16 O, 23 Na, Fe, 235 U, 238 U, and 239 Pu, which are regarded as important for the nuclear design study of fast reactors. The physical quantities for which covariances are deduced are cross sections, resolved and unresolved resonance parameters, and the first order Legendre-polynomial coefficient for the angular distribution of elastically scattered neutrons. As for 235 U, covariances were obtained also for the average number of neutrons emitted in fission. The covariances were estimated by using the same methodology that had been used in the JENDL-3.2 evaluation in order to keep a consistency between mean values and their covariances. The least-squares fitting code GMA was used in estimating covariances for reactions of which JENDL-3.2 cross sections had been evaluated by taking account of measurements. In nuclear model calculations, the covariances were calculated by the KALMAN system. The covariance data obtained were compiled in the ENDF-6 format, and will be put into the JENDL-3.2 Covariance File which is one of JENDL special purpose files. (author). 193 refs

  13. 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)

  14. Behaviour of semiconductor nuclear-particle detectors; Comportement des semi-conducteurs comme detecteurs de particules nucleaires; Povedenie detektorov yadernykh chastits na poluprovodnikakh; Propiedades de los detectores de particulas nucleares a base de semiconductores

    Energy Technology Data Exchange (ETDEWEB)

    Walter, F J; Dabbs, J W.T.; Roberts, L D [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1962-04-15

    asegurar una coleccion completa, el campo minimo necesario (en la superficie) para los fragmentos de fision seria de mas de 3 {center_dot} 10{sup 4} V/cm, frente a 2 {center_dot} 10{sup 3} V/cm para las particulas alfa en el Ge y el Si. Un estudio detallado del tiempo de elevacion del impulso en el amplificador ha puesto en claro que tanto el tiempo de relajacion como la resistencia correspondiente al material de base no purificado pueden desempenar un papel muy importante en los materiales de elevada resistividad. La memoria presenta una descripcion cuantitativa del efecto de los parametros del detector y del amplificador sobre la forma y el tiempo de elevacion de los impulsos. Se discuten las ventajas y los problemas que presenta la utilizacion de detectores de barrera superficial en varios experimentos muy especiales de alineacion nuclear realizados a baja temperatura, entre otros, referentes a las distribuciones angulares de fragmentos de fision y a la resolucion de la estructura alfa fina con estabilidad a largo plazo. Tambien se describen tecnicas de fabricacion basadas en coeficientes de dilatacion equiparados, que han permitido obtener detectores con areas activas de hasta 8 cm{sup 2}. (author) [Russian] Byli provedeny ehksperimental'nye i teoreticheskie issledovaniya povedeniya detektorov yadernykh chastits na poluprovodnikakh pri temperaturakh ot 0,2{sup o}K do 300{sup o}K. V doklade privoditsya prostaya teoreticheskaya model' povedeniya detektora, kotoraya, kak bylo ustanovleno, otrazhaet nablyudaemoe povedenie pri bol'shoj amplitude parametrov. V doklade obsuzhdaetsya vazhnost' chistoty poluprovodnikov i smeshcheniya napryazheniya v svyazi s amplitudoj impul'sa, vremenem narastaniya impul'sa i zonoj detektsii. EHmpiricheski issledovaniya shuma i ehnergeticheskogo razresheniya svidetel'stvuyut o tom, chto dlya al'fa-chastits nablyudaemaya naimen'shaya shirina pikov znachitel'no bol'she, chem ta, kotoraya ozhidaetsya na osnove ehlektricheskogo shuma

  15. 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)

  16. 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

  17. 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)

  18. 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

  19. Securing a better future for all: Nuclear techniques for global development and environmental protection. NA factsheet on nuclear and atomic data: Providing values for science

    International Nuclear Information System (INIS)

    2012-01-01

    The IAEA supports nuclear research activities in Member States by providing essential nuclear data and serving as the central agency for the collection and dissemination of data from laboratories worldwide. The EXFOR database contains a compilation of experimental reaction data from all around the world, and this effort - led by the IAEA - has been very well received, as it provides invaluable data for nuclear calculations and evaluations to researchers in Member States. ENSDF is a collection of evaluated data on the structure and decay properties of radioactive nuclides collected worldwide through a network coordinated by the IAEA. The IAEA has also developed tools to allow users to visualize data, since visual presentation of data in the form of a plot makes them easier to understand and appreciate. Two important applications are available from the Nuclear Data Services web site: LiveChart interactively presents nuclide properties, and ZVView plots reaction cross-sections, both from evaluated files and from EXFOR, as 2-D or 3-D plots. Concerted efforts by the IAEA include coordination of activities in Member States, such as EXFOR and ENSDF, coordinated research project (CRP) implementation, and also staff efforts, which have resulted in data libraries of immense value. IBANDL and RIPL-3 are examples of two databases resulting from CRPs. IBANDL is a database of experimental and evaluated nuclear cross-sections relevant to ion beam analysis. RIPL-3 is a library of reference input parameters which are essential ingredients of theoretical modelling codes. By providing a complete set of verified parameters, it is ensured that evaluations carried out around the world are compatible and can be produced easily and efficiently.

  20. 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

  1. 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.

  2. Feasibility Study for the Measurement of Nuclear Fragmentation Cross Sections with NA61/SHINE at the CERN SPS

    CERN Document Server

    Aduszkiewicz, A

    2017-01-01

    A detailed knowledge of the fragmentation cross sections of intermediate mass nuclei is of paramount importance to understand the propagation of cosmic rays in our Galaxy and to evaluate the background for dark matter searches with space-based cosmic-ray experiments such as AMS. Therefore, we suggest a one-week test run in 2018 with secondary ions to establish the capabilities of NA61/SHINE to measure fragmentation cross sections at isotope level. No major modifications to the experimental setup of NA61/SHINE are needed to perform this feasibility study. The experience gained during the test run will be used to formulate a comprehensive measurement campaign for cosmic-ray related fragmentation cross sections for the possible extension of the NA61/SHINE physics program beyond 2020. The test data on carbon-proton and oxygen-proton interactions at 13A GeV/c that we intend to collect during the proposed test run have already the potential to reduce the current cross section uncertainties.

  3. Securing a better future for all: Nuclear techniques for global development and environmental protection. NA factsheet on human health: Improving health around the world

    International Nuclear Information System (INIS)

    2012-01-01

    Every year, millions of nuclear medical examinations are conducted around the world using radiopharmaceuticals that assess diseases at molecular levels. Diagnostic images are then generated to help diagnose and treat major disorders and illnesses such as heart disease and cancer. Positron emission tomography in oncology and single photon emission tomography in cardiology (as well as in other areas) provide unique functional information that, when combined with anatomical data obtained by magnetic resonance imaging or computed tomography, allow for more precise localization of cancer or cardiac abnormalities. By facilitating appropriate human resources capacity building, the IAEA helps to establish new, and improve existing, nuclear medicine facilities, and encourages nuclear medicine imaging integration with diagnostic radiology procedures, thus helping its Member States to achieve and maintain high standards of professional practice.

  4. Vplivi turizma v slovenskem alpskem svetu na vode = Impacts of tourism in Slovenian Alpine areas on water

    Directory of Open Access Journals (Sweden)

    Dejan Cigale

    2007-01-01

    Full Text Available Tourism is not only an important economic activity but also a source of pressures on environment,including water. On the other hand appropriate water quality is of great importancefor tourism development. The contribution of tourism to pressures on water is important,but not dominant. Exceptions are impacts of tourism on the uninhabited areas, where tourismand recreation are the main sources of pressures on water resources. Nonetheless, quantitiesof used and sewage water are relatively modest.

  5. 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)

  6. Ghrelin and GHS-R1A signaling within the ventral and laterodorsal tegmental area regulate sexual behavior in sexually naïve male mice.

    Science.gov (United States)

    Prieto-Garcia, Luna; Egecioglu, Emil; Studer, Erik; Westberg, Lars; Jerlhag, Elisabet

    2015-12-01

    In addition to food intake and energy balance regulation, ghrelin mediate the rewarding and motivational properties of palatable food as well as addictive drugs. The ability of ghrelin to regulate reinforcement involves the cholinergic-dopaminergic reward link, which encompasses a cholinergic projection from the laterodorsal tegmental area (LDTg) to the ventral tegmental area (VTA) together with mesolimbic dopaminergic projections from the VTA to the nucleus accumbens (NAc). Recently, systemic ghrelin was shown to regulate sexual behavior and motivation in male mice via dopamine neurotransmission. The present study therefore elucidates the role of ghrelin and ghrelin receptor (GHS-R1A) antagonist treatment within NAc, VTA or LDTg for sexual behavior in sexually naïve male mice. Local administration of the GHSR-1A antagonist, JMV2959, into the VTA or LDTg was found to reduce the preference for female mice, the number of mounts and the duration of mounting as well as to prolong the latency to mount. This was further substantiated by the findings that ghrelin administration into the VTA or LDTg increased the number of mounts and the duration of mounting and decreased the latency to mount. Moreover, ghrelin administered into the LDTg increased the preference for female mice. Accumbal administration of ghrelin increased whereas GHS-R1A antagonist decreased the intake of palatable food, but did not alter sexual behavior. In males exposed to sexual interaction, systemic administration of ghrelin increases whereas JMV2959 decreases the turnover of dopamine in the VTA. These data suggest that ghrelin signaling within the tegmental areas is required for sexual behavior in sexually naïve male mice. Copyright © 2015 The Authors. Published by Elsevier Ltd.. All rights reserved.

  7. 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)

  8. 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

  9. 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

  10. 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)

  11. 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...

  12. 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)

  13. 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)

  14. 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

  15. 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

  16. Raft tectonics in northern Campos Basin; Tectonica de jangada (raft tectonics) na area norte da Bacia de Campos

    Energy Technology Data Exchange (ETDEWEB)

    Castro, Marilia R. de [Universidade Estadual do Norte Fluminense (UENF), Campos dos Goytacases, RJ (Brazil)]|[PETROBRAS, Macae, RJ (Brazil). Unidade de Negocio da Bacia de Campos; Fugita, Adhemar M. [Universidade do Estado, Rio de Janeiro, RJ (Brazil). Programa de Recursos Humanos da ANP

    2004-07-01

    In the northern area of Campos Basin salt gliding/spreading processes promoted the break-up and transport of Cretaceous and Tertiary rocks overlying the evaporites. This process is known as raft tectonics, and it represents the most extreme form of thin-skinned extension above the salt decollement surface. Three distinct geotectonic domains were recognized that formed in response to the raft tectonics. The first one, confined to the shallower shelf portion of the basin, is characterized by minor extension (pre-raft domain), probably because of small salt thickness and low gradient. In the second domain (or disorganized rafts domain), located in distal platformal and slope areas, seismic sections show the occurrence of blocks or rafts with angular shapes, sometimes imbricated and frequently discontinuous. In the third domain, or domain of organized rafts, located in bacinal region, seismic sections show a more continuous raft pattern, often folded because of salt compression in the distal portions of the basin. The main purposes of this work is to characterize these three tectonic domains distinguished by raft tectonics, as well as their importance in hydrocarbon accumulations in calcarenites. (author)

  17. Up-regulation of Na + expression in the area postrema of total sleep deprived rats by TOF-SIMS analysis

    Science.gov (United States)

    Mai, Fu-Der; Chen, Bo-Jung; Ling, Yong-Chien; Wu, Un-In; Huang, Yi-Lun; Chang, Hung-Ming

    2008-12-01

    Area postrema (AP) is a circumventricular organ plays an important role in sodium homeostasis and cardiovascular regulation. Since sleep deficiency will cause cardiovascular dysfunction, the present study aims to determine whether sodium level would significantly alter in AP following total sleep deprivation (TSD). Sodium level was investigated in vivo by time-of-flight secondary ion mass spectrometry (TOF-SIMS). Clinical manifestation of cardiovascular function was demonstrated by mean arterial pressure (MAP) values. Results indicated that in normal rats, TOF-SIMS spectrum revealed a major peak of sodium ion counting as 5.61 × 10 5 at m/ z 23. The sodium ions were homogeneous distributed in AP without specific localization. However, following TSD, the sodium intensity was relatively increased (6.73 × 10 5) and the signal for sodium image was strongly expressed throughout AP with definite spatial distribution. MAP of TSD rats is 138 ± 5 mmHg, which is significantly higher than that of normal ones (121 ± 3 mmHg). Regarding AP is an important area for sodium sensation and development of hypernatremic related sympatho-excitation; up-regulation of sodium expression following TSD suggests that high sodium level might over-activate AP, through complex neuronal networks involving in sympathetic regulation, which could lead to the formation of TSD relevant cardiovascular diseases.

  18. 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.)

  19. 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

  20. Hadron production in nuclear collisions from the NA49 experiment at 158 GeV/c.A

    CERN Document Server

    Bächler, J; Barnby, L S; Bartke, Jerzy; Barton, R A; Betev, L; Bialkowska, H; Billmeier, A; Blume, C; Blyth, C O; Boimska, B; Bracinik, J; Brady, F P; Brun, R; Buncic, P; Carr, L; Cebra, D; Cooper, G E; Cramer, J G; Csató, P; Eckardt, V; Eckhardt, F; Ferenc, D; Fischer, H G; Fodor, Z; Foka, P Y; Freund, P; Friese, V; Ftácnik, J; Gál, J; Ganz, R E; Gazdzicki, M; Gladysz-Dziadus, E; Grebieszkow, J; Harris, J W; Hegyi, S; Hlinka, V; Höhne, C; Igo, G; Ivanov, M; Jacobs, P; Janik, R; Jones, P G; Kadija, K; Kolesnikov, V I; Kowalski, M; Lasiuk, B; Lednicky, R; Lévai, Peter; Malakhov, A I; Margetis, S; Markert, C; Mayes, B W; Melkumov, G L; Molnár, J; Nelson, J M; Odyniec, Grazyna Janina; Oldenburg, M; Pálla, G; Panagiotou, A D; Petridis, A; Pikna, M; Pinsky, L; Poskanzer, A M; Prindle, D J; Pühlhofer, F; Reid, J G; Renfordt, R E; Retyk, W; Ritter, H G; Röhrich, D; Roland, C; Roland, G; Rybicki, A; Sammer, T; Sandoval, A; Sann, H; Semenov, A Yu; Schäfer, E; Schmitz, N; Seyboth, P; Siklér, F; Sitár, B; Skrzypczak, E; Snellings, R; Squier, G T A; Stock, Reinhard; Strmen, P; Ströbele, H; Susa, T; Szarka, I; Szentpétery, I; Sziklai, J; Toy, M; Trainor, T A; Trentalange, S; Ullrich, T S; Varga, D; Vassiliou, Maria; Veres, G I; Vesztergombi, G; Voloshin, S A; Vranic, D; Wang, F; Weerasundara, D D; Wenig, S; Whitten, C; Xu, N; Yates, T A; Yoo, I K; Zimányi, J

    1999-01-01

    With its large acceptance and particle identification coverage the NA49 experiment can study hadron production in a wide range of high energy reactions. Originally aimed at examining central Pb+Pb collisions for signatures of quark-gluon plasma formation, the scope of the experiment has been enhanced with the systematic study of impact parameter and projectile size dependence, as well as the inclusion of the more elementary p+p and p+A interactions. The question is: are predicted signals of the quark-gluon plasma observed and are there discontinuities which would support the concept of hadronic phase transition?. (15 refs).

  1. Hadron production in nuclear collisions from the NA49 experiment at 158GeV/c · A

    International Nuclear Information System (INIS)

    Sikler, F.; Baechler, J.; Barna, D.; Barnby, L.S.; Bartke, J.; Barton, R.A.; Betev, L.; Bialkowska, H.; Billmeier, A.; Blume, C.; Blyth, C.O.; Boimska, B.; Bracinik, J.; Brady, F.P.; Brun, R.; Buncic, P.; Carr, L.; Cebra, D.; Cooper, G.E.; Cramer, J.G.; Csato, P.; Eckardt, V.; Eckhardt, F.; Ferenc, D.; Fischer, H.G.; Fodor, Z.; Foka, P.; Freund, P.; Friese, V.; Ftacnik, J.; Gal, J.; Ganz, R.; Gazdzicki, M.; Gladysz, E.; Grebieszkow, J.; Harris, J.W.; Hegyi, S.; Hlinka, V.; Hoehne, C.; Igo, G.; Ivanov, M.; Jacobs, P.; Janik, R.; Jones, P.G.; Kadija, K.; Kolesnikov, V.I.; Kowalski, M.; Lasiuk, B.; Lednicky, R.; Levai, P.; Malakhov, A.I.; Margetis, S.; Markert, C.; Mayes, B.W.; Melkumov, G.L.; Molnar, J.; Nelson, J.M.; Odyniec, G.; Oldenburg, M.D.; Palla, G.; Panagiotou, A.D.; Petridis, A.; Pikna, M.; Pinsky, L.; Poskanzer, A.M.; Prindle, D.J.; Puehlhofer, F.; Reid, J.G.; Renfordt, R.; Retyk, W.; Ritter, H.G.; Roehrich, D.; Roland, C.; Roland, G.; Rybicki, A.; Sammer, T.; Sandoval, A.; Sann, H.; Semenov, A.Yu.; Schaefer, E.; Schmitz, N.; Seyboth, P.; Sitar, B.; Skrzypczak, E.; Snellings, R.; Squier, G.T.A.; Stock, R.; Strmen, P.; Stroebele, H.; Susa, T.; Szarka, I.; Szentpetery, I.; Sziklai, J.; Toy, M.; Trainor, T.A.; Trentalange, S.; Ullrich, T.; Varga, D.; Vassiliou, M.; Veres, G.I.; Vesztergombi, G.; Voloshin, S.; Vranic, D.; Wang, F.; Weerasundara, D.D.; Wenig, S.; Whitten, C.; Xu, N.; Yates, T.A.; Yoo, I.K.; Zimanyi, J.

    1999-01-01

    With its large acceptance and particle identification coverage the NA49 experiment (Fig. 1) can study hadron production in a wide range of high energy reactions [1]. Originally aimed at examining central Pb+Pb collisions for signatures of quark-gluon plasma formation, the scope of the experiment has been enhanced with a systematic study of impact parameter and projectile size dependence, as well as the inclusion of the more elementary p+p and p+A interactions. The question is: are predicted signals of the quark-gluon plasma observed and are there discontinuities which would support the concept of hadronic phase transition?

  2. 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)

  3. 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.

  4. 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)

  5. 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)

  6. Geochemical dispersion of Si, Al, Fe, Mn, Na, K, Cu and Zn elements in soils and their use for characterization areas geochemically homogeneous

    International Nuclear Information System (INIS)

    Silva, W.R.L. da.

    1982-01-01

    Variations in the chemical composition of soils are used to characterize sub-areas geochemically - homogenous. The application of this methodology in a tropical humid region of accentuated topography constitute the principal objective of the present research. Samples of red latosols (Horizon B) developed over granite, sandstone and basalt occurring in the Central Granite Region of the Serra dos Carajas, Para State, Brazil were analized for the elements Si, Al, Fe, Mn, Na, K, Cu e Zn, by atomic absorption spectrophotometry. Based on the criterion of similarity in the chemical composition (Cluster Analysis, Factor Analysis) the soils were separeted in to different groups. The geographical distribution of the different groups permit the establishment of a close relationship between the different parent lithologies and their corresponding soils. (author)

  7. 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

  8. 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

  9. 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

  10. 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.)

  11. 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.

  12. 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

  13. 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)

  14. 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.

  15. 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)

  16. 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

  17. 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

  18. 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)

  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. Production and sharing of the nuclear knowledge: knowledge management at the Radiopharmaceutical Division of the Instituto de Engenharia Nuclear of Brazilian CNEN; Produção e compartilhamento do conhecimento nuclear: a gestão do conhecimento na Divisão de Radiofármacos do Instituto de Engenharia Nuclear da Comissão Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Bettencourt, Marcia Pires da Luz

    2011-07-01

    The Brazilian nuclear area made great progress in recent years, bringing many benefits to society, not only in producing electric power, but also in agriculture, industry and medicine. One of the problems in this area, nowadays, is the risk losing nuclear knowledge. Although it is difficult to understand how knowledge is created and used, can be seen that the sharing and production are influenced by some factors that provide favorable conditions. This research focused its attention on identifying actions that contribute to the production and sharing of knowledge and information at the Divisão de Radiofármacos of Instituto de Engenharia Nuclear of Comissão Nacional de Energia Nuclear (IEN/CNEN). Knowledge management was chosen as a tool to study the problem identified, because it has methodologies aimed at stimulating the knowledge production process and knowledge and information sharing, both in private companies and public institutions, such as IEN/CNEN. Knowledge management is an interdisciplinary relatively new discipline, and although it had not been born in Information Science, there has been seeking theoretical support and legitimacy at this interdisciplinary science. This research conceptualizes, historically contextualizes and analyzes developments and trends in knowledge management. The study discourses on the peculiarities and aspects in common between the knowledge management and information management and identifies factors that influence the sharing of information and knowledge such as: social networks, communities of practice, collaborative spaces, organizational culture, organizational learning, and storytelling. In reviewing the literature and after data analysis of interviews, some actions have been identified, and it was possible to make some suggestions. It is concluded that institutional incentive for collaboration and knowledge sharing can influence positive results and increase the production of new knowledge. (author)

  5. Impacts of the turbogenerator reactive operation in the nuclear fuel burnup; Impactos da operacao reativa do turbogerador na queima do combustivel nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Helio Ricardo V. de; Martinez, Aquilino S. [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear

    2002-07-01

    The parameterization of the losses in a turbogenerator in function of an operation with the electrical system reactive allowed to model in a simple and exact way the equations that define and they quantify the additional of nuclear potency that it should be generated by a reactor, in order to maintain the commitment with the national system operator, that is, the electric active power contracted. starting from this additional of nuclear power it was modeled the additional burn up of the fuel elements, as well as the numbers of effective days to full power wasted. it was promoted a safety analysis and some limitations due to the reactive operation of the electrical system. inside of this context it was made a financial evaluation in which we ask some questions to companies and government organs in order to define what losses are acceptable and also the reason why we don't use other technician resources such as: increase of the electrical mesh, electrical power injection in strategic points, capacitor banks and increase of the number the electrical plants. (author)

  6. Staff Organization in Nuclear Power Stations; Organisation du personnel des centrales nucleaires; Organizatsiya personala na atomnykh ehlektrostantsiyakh; Organizacion del personal de las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Scuricini, G. B. [Comitato Nazionale Energia Nucleare, Roma (Italy)

    1963-10-15

    This paper deals with the organization of operating and maintenance staff at nuclear power stations in Italy and manpower variations, either because the plants themselves differ or are organized in some special way. Staff doing jobs for which a specific training is required are given special consideration in the paper. (author) [French] Dans le memoire, on examine l'organisation du personnel d'exploitation et d'entretien des centrales nucleaires italiennes et les differences existant dans les effectifs, differences dues soit aux caracteristiques des centrales memes, soit aux particularites d'organisation des entreprises. Le personnel charge de fonctions determinees pour lesquelles un entrainement special est requis, fait l'objet d'une attention particuliere. (author) [Spanish] En la memoria se examina la organizacion del personal de explotacion y conservacion de las centrales nucleares italianas y las diferencias que existen entre sus efectivos, diferencias que se deben a las caracteristicas de las mismas centrales o a las particularidades de organizacion de las empresas. El autor dedica especial atencion al personal encargado de funciones que requieren una formacion profesional especial. (author) [Russian] Issleduyutsya voprosy organizatsii personala, zanimayushchegosya ehkspluatatsiej ital'yanskikh atomnykh ehlektrostantsij i ukhodom za nimi, a takkhe razlichiya v sostave personala, vytekayushchie libo iz kharakternykh osobennostej samikh stantsij, libo iz osobennostej organizatsii predpriyatij. Osoboe vnimanie udelyaetsya personalu, kotoromu porucheny opredelennye funktsii, trebuyushchie spetsial'noj pod go tovki. (author)

  7. 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)

  8. Regulation of Na(+)/K(+)-ATPase by nuclear respiratory factor 1: implication in the tight coupling of neuronal activity, energy generation, and energy consumption.

    Science.gov (United States)

    Johar, Kaid; Priya, Anusha; Wong-Riley, Margaret T T

    2012-11-23

    NRF-1 regulates mediators of neuronal activity and energy generation. NRF-1 transcriptionally regulates Na(+)/K(+)-ATPase subunits α1 and β1. NRF-1 functionally regulates mediators of energy consumption in neurons. NRF-1 mediates the tight coupling of neuronal activity, energy generation, and energy consumption at the molecular level. Energy generation and energy consumption are tightly coupled to neuronal activity at the cellular level. Na(+)/K(+)-ATPase, a major energy-consuming enzyme, is well expressed in neurons rich in cytochrome c oxidase, an important enzyme of the energy-generating machinery, and glutamatergic receptors that are mediators of neuronal activity. The present study sought to test our hypothesis that the coupling extends to the molecular level, whereby Na(+)/K(+)-ATPase subunits are regulated by the same transcription factor, nuclear respiratory factor 1 (NRF-1), found recently by our laboratory to regulate all cytochrome c oxidase subunit genes and some NMDA and AMPA receptor subunit genes. By means of multiple approaches, including in silico analysis, electrophoretic mobility shift and supershift assays, in vivo chromatin immunoprecipitation, promoter mutational analysis, and real-time quantitative PCR, NRF-1 was found to functionally bind to the promoters of Atp1a1 and Atp1b1 genes but not of the Atp1a3 gene in neurons. The transcripts of Atp1a1 and Atp1b1 subunit genes were up-regulated by KCl and down-regulated by tetrodotoxin. Atp1b1 is positively regulated by NRF-1, and silencing of NRF-1 with small interference RNA blocked the up-regulation of Atp1b1 induced by KCl, whereas overexpression of NRF-1 rescued these transcripts from being suppressed by tetrodotoxin. On the other hand, Atp1a1 is negatively regulated by NRF-1. The binding sites of NRF-1 on Atp1a1 and Atp1b1 are conserved among mice, rats, and humans. Thus, NRF-1 regulates key Na(+)/K(+)-ATPase subunits and plays an important role in mediating the tight coupling between

  9. The U.S./IAEA Workshop on Software Sustainability for Safeguards Instrumentation: Report to the NNSA DOE Office of International Nuclear Safeguards (NA-241)

    Energy Technology Data Exchange (ETDEWEB)

    Pepper, Susan E. [Brookhaven National Lab. (BNL), Upton, NY (United States); Pickett, Chris A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Queirolo, Al [Brookhaven National Lab. (BNL), Upton, NY (United States); Bachner, Katherine M. [Brookhaven National Lab. (BNL), Upton, NY (United States); Worrall, Louise G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-04-07

    The U.S Department of Energy (DOE) National Nuclear Security Administration (NNSA) Next Generation Safeguards Initiative (NGSI) and the International Atomic Energy Agency (IAEA) convened a workshop on Software Sustainability for Safeguards Instrumentation in Vienna, Austria, May 6-8, 2014. Safeguards instrumentation software must be sustained in a changing environment to ensure existing instruments can continue to perform as designed, with improved security. The approaches to the development and maintenance of instrument software used in the past may not be the best model for the future and, therefore, the organizers’ goal was to investigate these past approaches and to determine an optimal path forward. The purpose of this report is to provide input for the DOE NNSA Office of International Nuclear Safeguards (NA-241) and other stakeholders that can be utilized when making decisions related to the development and maintenance of software used in the implementation of international nuclear safeguards. For example, this guidance can be used when determining whether to fund the development, upgrade, or replacement of a particular software product. The report identifies the challenges related to sustaining software, and makes recommendations for addressing these challenges, supported by summaries and detailed notes from the workshop discussions. In addition the authors provide a set of recommendations for institutionalizing software sustainability practices in the safeguards community. The term “software sustainability” was defined for this workshop as ensuring that safeguards instrument software and algorithm functionality can be maintained efficiently throughout the instrument lifecycle, without interruption and providing the ability to continue to improve that software as needs arise.

  10. The U.S./IAEA Workshop on Software Sustainability for Safeguards Instrumentation: Report to the NNSA DOE Office of International Nuclear Safeguards (NA-241)

    International Nuclear Information System (INIS)

    Pepper, Susan E.; Pickett, Chris A.; Queirolo, Al; Bachner, Katherine M.; Worrall, Louise G.

    2015-01-01

    The U.S Department of Energy (DOE) National Nuclear Security Administration (NNSA) Next Generation Safeguards Initiative (NGSI) and the International Atomic Energy Agency (IAEA) convened a workshop on Software Sustainability for Safeguards Instrumentation in Vienna, Austria, May 6-8, 2014. Safeguards instrumentation software must be sustained in a changing environment to ensure existing instruments can continue to perform as designed, with improved security. The approaches to the development and maintenance of instrument software used in the past may not be the best model for the future and, therefore, the organizers' goal was to investigate these past approaches and to determine an optimal path forward. The purpose of this report is to provide input for the DOE NNSA Office of International Nuclear Safeguards (NA-241) and other stakeholders that can be utilized when making decisions related to the development and maintenance of software used in the implementation of international nuclear safeguards. For example, this guidance can be used when determining whether to fund the development, upgrade, or replacement of a particular software product. The report identifies the challenges related to sustaining software, and makes recommendations for addressing these challenges, supported by summaries and detailed notes from the workshop discussions. In addition the authors provide a set of recommendations for institutionalizing software sustainability practices in the safeguards community. The term ''software sustainability'' was defined for this workshop as ensuring that safeguards instrument software and algorithm functionality can be maintained efficiently throughout the instrument lifecycle, without interruption and providing the ability to continue to improve that software as needs arise.

  11. 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)

  12. 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

  13. 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

  14. 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

  15. 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.)

  16. 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)

  17. Radiological investigation in the outside area of expedition's room during radiopharmaceuticals' expedition; Avaliacao radiologica na area externa da sala de expedicao durante a expedicao de radiofarmacos

    Energy Technology Data Exchange (ETDEWEB)

    Reina, Luiz C.; Monteiro, Ilka H.T.S.; Silva, Joao Carlos P. da; Teixeira, Danilo L.; Pedro, C.R.; Santos, J. Regis dos, E-mail: reina@ien.gov.br, E-mail: jcarlos@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de janeiro, RJ (Brazil)

    2013-07-01

    Radiopharmaceuticals produced in IEN - Instituto de Engenharia Nuclear of the Brazilian Nuclear Energy Commission, are issued by the radiation protection team, which is responsible for preparing and issuing the packaged documentation required for movement in modal transportation. The documents are: Invoice , Shipper's Declaration of Radioactive Material , Shipper's Declaration of Dangerous Goods - (form IATA ) , Emergency Sheet, sketch of packed. All this documentation is inserted in an envelope of emergency. The Department of Radiological Protection is responsible for issuing such documents except the invoice that is issued by the Commercial Sector (Setcom). A employee of this sector is responsible for delivering it to the shipment sector. The preparation of packaged and documentation is performed in a room located in the building of Radiopharmaceutical Division. The vehicles which are used in the transport are parked outside this building, where are monitored after commissioning of packaged. The present study aims to evaluate potential and occupational radiation risks of people in transit or remain in the area where radioactive material circulates due to the shipment of radiopharmaceuticals for the classification of the area during the operation of dispatch.

  18. 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)

  19. Processing of three-dimensional structures of Nuclear Medicine in PET modality; Processamento de estruturas tridimensionais de medicina nuclear na modalidade PET

    Energy Technology Data Exchange (ETDEWEB)

    Pacheco, Edward Florez; Furuie, Sergio Shiguemi, E-mail: edward.florez@usp.br [Universidade de Sao Paulo (EP/USP), SP (Brazil). Dept. de Engenharia de Telecomunicacoes e Controle. Lab. de Engenharia Biomedica

    2013-03-15

    The nuclear medicine, as a specialty to obtain medical images is very important, and it has became one of the main procedures utilized in health care centers to analyze the metabolic behavior of the patient. This project was based on medical images obtained by the PET modality (Positron Emission Tomography). Thus, we developed a framework for processing Nuclear Medicine three-dimensional images of the PET modality, which is composed of consecutive steps that start with the generation of standard images (gold standard) by using simulated images of the Left Ventricular Heart, such as phantoms obtained from the NCAT-4D software. Then, Poisson quantum noise was introduced into the whole volume to simulate the characteristic noises in PET images. Subsequently, the pre-processing step was executed by using specific 3D filters, such as the median filter, the weighted Gaussian filter, and the Anscombe/Wiener filter. Then the segmentation process, which is based on the fuzzy connectedness theory, was implemented. For that purpose four different 3D approaches were implemented: Generic, LIFO, kTetaFOEMS, and dynamic weight algorithm. Finally, an assessment procedure was used as a measurement tool to quantify three parameters (true positive, false positive and maximum distance) that determined the level of efficiency and precision of our process. It was found that the pair filter - segmenter formed by the Anscombe/Wiener filter together with the Fuzzy segmenter based on dynamic weights provided the best results, with VP and FP rates of 98.49 {+-}0.27% and 2.19 {+-}0.19%, respectively, for the simulation of the left ventricular volume. Along with the set of choices made during the processing structure, the project was finished with the analysis of a small number of volumes that belonged to a real PET test, thus the quantification of the volumes was obtained. (author)

  20. 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)

  1. 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

  2. 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

  3. 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

  4. 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)

  5. 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

  6. Ocena zmiany warunków hydrologicznych na terenach zurbanizowanych z wykorzystaniem technik GIS = GIS-based assessment of changes related to hydrological conditions in urban areas

    Directory of Open Access Journals (Sweden)

    Danuta Szumińska

    2015-05-01

    email: dszum@ukw.edu.pl1   Streszczenie   W artykule zaprezentowano możliwości wykorzystania technik GIS do przeprowadzenia analizy zmiany warunków hydrologicznych. Badania przeprowadzono na terenie zurbanizowanym, na którym dokonano zmian rzeźby oraz sposobu użytkowania terenu. Spowodowało to pojawieniem się problemów z odwodnieniem terenu, przede wszystkim w czasie wzmożonego zasilania z opadów deszczu i roztopów śniegu. W celu określenia przyczyn występujących problemów porównano rzeźbę terenu oraz wyznaczono kierunki odpływu wód powierzchniowych przed i po zagospodarowaniu działki d (Ryc. 1. Czasochłonne i kosztochłonne badania geologiczne wykonano w minimalnym zakresie (Tab. 1 i zostały one wykorzystane jako informacja uzupełniająca, pozwalająca na ocenę możliwości infiltracji wody w podłoże. Na podstawie przeprowadzonych badań stwierdzono, że główne przyczyny problemów z odwodnieniem terenu związane są ze stworzeniem barier w postaci podmurówek ogrodzeń zlokalizowanych prostopadle do kierunków odpływu wody (Fot. 1, Fot. 2. Zmiany rzeźby były w analizowanym przypadku czynnikiem mniej istotnym.   Słowa kluczowe: warunki hydrologiczne, infiltracja, model rzeźby terenu, kierunki odpływu, użytkowanie terenu, tereny zurbanizowane.   Abstract   The paper discusses the possibilities of employing GIS for conducting analysis of changes in hydrological conditions. The study was carried out in an urban area featuring altered relief and use of land. This caused problems with draining the terrain, particularly at times of increased rainwater and meltwater supply. In order to identify the causes of the occurring problems, we compared land relief prior and after the plot was developed, as well as indicated the directions of surface water runoff (Fig. 1. Time-consuming and expensive geological research activities were restricted to minimum (Tab. 2 and the data thus obtained were used as supplementary information to

  7. 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)

  8. 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

  9. 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.

  10. 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

    do cerrado (argiloso e arenoso. Adicionalmente, um material de referência de solo da Agência Internacional de Energia Atômica foi analisado. A concentração de ETR no PG foi, em média, duas vezes maior que a encontrada na maioria dos fertilizantes nacionais (total de 4.000 mg kg-1 , 154 vezes maior que no solo arenoso (26 mg kg-1 e 14 vezes maior que no solo argiloso (280 mg kg-1 . Os resultados obtidos no material de referência confirmaram a exatidão do método com intervalo de confiança de 95%. Foi comprovada a versatilidade da técnica ao serem determinados o La, Ce, Pr, Nd, Pm, Sm, Eu, Tb, Dy, Ho, Er, Tm, Yb e Lu em amostras de solo e fosfogesso de interesse na agricultura.

  11. 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

  12. 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

  13. 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

  14. Management of radioactive waste from {sup 99}Mo production by nuclear fission; Gestao dos rejeitos radioativos gerados na producao do {sup 99}Mo por fissao nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Rego, Maria Eugenia de Melo

    2013-07-01

    Brazil intends to build a facility for the {sup 99}Mo production through {sup 235}U fission, once this radioisotope is largely used in nuclear medicine. This study aimed at estimating the physical, chemical and radiological characteristics of radioactive waste expected to be generated in that facility, and to provide theoretical subsides that can be used on the definition of a proper waste management system. Two production scenarios were established and the radioisotope inventories of the wastes were calculated by Scale®. From the chemical processing of the uranium targets the wastes were characterized on their chemical and radiological features. MicroShield® was used to determine the activity concentrations up to three months of {sup 99}Mo production. In addition, this work presents dose rate calculation for several sizes of shielding and different amount of wastes, collected in a proper package for in-site transportation. Radionuclides responsible for higher doses were identified in order to facilitate choosing the most appropriate method for managing the wastes after their chemical separation and before their storage. These results are part of what is expected on radioactive wastes at a {sup 99}Mo production facility and might help on the development of the waste management planning for that facility. (author)

  15. 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)

  16. 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)

  17. 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

  18. 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

  19. 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

  20. 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)

  1. 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

  2. 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.

  3. 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

  4. Nuclear Overhauser effect studies of the conformation of Co(NH3)4ATP bound to kidney Na,K-ATPase

    International Nuclear Information System (INIS)

    Stewart, J.M.; Jorgensen, P.L.; Grisham, C.M.

    1989-01-01

    Transferred nuclear Overhauser effect measurements (in the two-dimensional mode) have been used to determine the three-dimensional conformation of an ATP analogue, Co(NH3)4ATP, at the active site of sheep kidney Na,K-ATPase. Previous studies have shown that Co(NH3)4ATP is a competitive inhibitor with respect to MnATP for the Na,K-ATPase. Nine unique proton-proton distances on ATPase-bound Co(NH3)4ATP were determined from the initial build-up rates of the cross-peaks of the 2D-TRNOE data sets. These distances, taken together with previous 31P and 1H relaxation measurements with paramagnetic probes, are consistent with a single nucleotide conformation at the active site. The bound (Co(NH3)4ATP) adopts an anti conformation, with a glycosidic torsion angle of 35 degrees, and the conformation of the ribose ring is slightly N-type (C2'-exo, C3'-endo). The delta and gamma torsional angles in this conformation are 100 degrees and 178 degrees, respectively. The nucleotide adopts a bent configuration, in which the triphosphate chain lies nearly parallel to the adenine moiety. Mn2+ bound to a single, high-affinity site on the ATPase lies above and in the plane of the adenine ring. The distances from enzyme-bound Mn2+ to N6 and N7 are too large for first coordination sphere complexes, but are appropriate for second-sphere complexes involving, for example, intervening hydrogen-bonded water molecules. The NMR data also indicate that the structure of the bound ATP analogue is independent of the conformational state of the enzyme

  5. Nuclear Overhauser effect studies of the conformation of Co(NH3)4ATP bound to kidney Na,K-ATPase

    Energy Technology Data Exchange (ETDEWEB)

    Stewart, J.M.; Jorgensen, P.L.; Grisham, C.M. (Univ. of Virginia, Charlottesville (USA))

    1989-05-30

    Transferred nuclear Overhauser effect measurements (in the two-dimensional mode) have been used to determine the three-dimensional conformation of an ATP analogue, Co(NH3)4ATP, at the active site of sheep kidney Na,K-ATPase. Previous studies have shown that Co(NH3)4ATP is a competitive inhibitor with respect to MnATP for the Na,K-ATPase. Nine unique proton-proton distances on ATPase-bound Co(NH3)4ATP were determined from the initial build-up rates of the cross-peaks of the 2D-TRNOE data sets. These distances, taken together with previous 31P and 1H relaxation measurements with paramagnetic probes, are consistent with a single nucleotide conformation at the active site. The bound (Co(NH3)4ATP) adopts an anti conformation, with a glycosidic torsion angle of 35{degrees}, and the conformation of the ribose ring is slightly N-type (C2'-exo, C3'-endo). The delta and gamma torsional angles in this conformation are 100 degrees and 178 degrees, respectively. The nucleotide adopts a bent configuration, in which the triphosphate chain lies nearly parallel to the adenine moiety. Mn2+ bound to a single, high-affinity site on the ATPase lies above and in the plane of the adenine ring. The distances from enzyme-bound Mn2+ to N6 and N7 are too large for first coordination sphere complexes, but are appropriate for second-sphere complexes involving, for example, intervening hydrogen-bonded water molecules. The NMR data also indicate that the structure of the bound ATP analogue is independent of the conformational state of the enzyme.

  6. Videografia digital a?rea: proposta de um sistema e aplica??o no estudo de uso do solo, cobertura vegetal e silvicultura urbana na Amaz?nia Central, munic?pio de Manaus, AM

    OpenAIRE

    Bittencourt, Francisco Fernando Bessa

    2010-01-01

    Tendo em vista a necessidade de planejamento, controle e monitoramento do espa?o urbano e de ?reas verdes, a ?rea de geotecnologias tem desenvolvido m?todos e t?cnicas, bem como softwares especializados que auxiliam na realiza??o destas atividades, buscando solucionar problemas de uso e ocupa??o desordenada da terra. Dentre os m?todos e t?cnicas destaca-se a Videografia Digital A?rea Multiespectral de Alta Resolu??o. Admitindo-se como premissa a possibilidade do uso de imagens a?reas na ident...

  7. 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.

  8. 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)

  9. 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)

  10. 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

  11. 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.

  12. 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.

  13. 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

  14. 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

  15. 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

  16. Use of microcontroller in gamma-ray spectrometer construction using NaI(Tl) sensor, with emphasis in multichannel analyzer, to applications in nuclear and environmental geophysics

    International Nuclear Information System (INIS)

    Silva, Nilton

    2005-01-01

    In this work of nuclear geophysical instrumentation the main purpose was the development of a gamma-ray spectrometer prototype with multi channel analyzer, since the spectroscopic amplifier until your firmware. The heart of the digital part was an ATMEL 8 bits microcontroller (AT89S8252). All circuits were made and assembled in the Laboratory of Applied Geophysical Instrumentation (LIGA) of IAG-USP. A microcontroller software was completely developed in C ANSI language using the Small Device C Compiler version 2.4.8, that is a free software distributed under General Public License (GPL). At first, microcontroller was used to change all digital circuit of one classic SCINTREX GAD-6 differential gamma-ray spectrometer. Measurement times with order of 2 days became possible, and it could work in non climate ambient. Then, after this stage, had been started the development of a multichannel analyzer (MCA) working in pulse height analyzer mode with 4096 channels capacity, to use in many kinds of nuclear detection. Besides it, was developed an automatic gain system for photopeak stabilization, by the use of one radioactive source ( 133 Ba). This automatic gain system is very important in the case of NaI(Tl) scintillometric detectors, due PMT sensitivity with temperature and aging of some laboratory electronic circuits. Two power supplies with high stability, using pulse width modulation (PWM) techniques were developed, in order to all system became free of electrical line break off. One PWM power polarizes a photo multiplier tube (PMT) with high voltage and another supplies remaining developed circuits. Calibration in energy using standards sources 137 Cs and 60 Co showed that gamma detector developed has a good linearity and low thermal drift, even working in absent of air-conditioned. Concentrations measurements of K, U and Th were made in samples of soils, vegetables, etc. (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. 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...

  20. Atendimento médico de urgência na grande São Paulo Medical emergency system in the metropolitan area of São Paulo

    Directory of Open Access Journals (Sweden)

    Sueli Gandolfi Dallari

    2001-12-01

    emergência médica na Grande São Paulo.The present paper analyzed the emergency medical system in the Metropolitan Area of São Paulo during the year 1999 through the exam of all the pertinent laws, the description of the attendance process of the Regional Controlling Unit (Plantão Controlador Regional - PCR, and the verification of the adequacy of the adopted procedures to the norms that regulate the sector and to an efficient attendance of the patients. Documents were analyzed, interviews were carried out and the functioning of the system was observed in the PCR and in three general hospitals. The paper describes the oral history of the creation of the system and the services routine. It was observed that there was personnel shortage in the PCR and that the doctors did not follow the same routine of procedures. It was also verified that many people, including the doctors on duty, did not know what the PCR was, and that transfers were sometimes impossible due to lack of transportation. Furthermore, the Medical Files and Statistics Services of the researched hospitals are outdated and there is shortage of material and human resources. Although the size of the sample does not allow generalizations, it could be observed that there was lack of beds in the Neonatal ICU, and that the most frequent reasons for the request of resources were lack of beds and equipment, faulty equipment and shortage of personnel. These requests often received a negative answer at first, with the most frequent reasons being lack of beds, unavailable equipment or transport. Most cases arrived at the PCR after the professionals in charge had tried to solve the problem on their own under the justification of delay in solving the case. Based on the rules of the system and on the analysis of international experiences, the paper provides suggestions for the efficacious implementation of a metropolitan emergency system in the metropolitan area of São Paulo.

  1. 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.

  2. 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)

  3. 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)

  4. 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)

  5. 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

  6. 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.

  7. 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)

  8. 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

  9. 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

  10. Studies in Low-Energy Nuclear Science

    Energy Technology Data Exchange (ETDEWEB)

    Carl R. Brune; Steven M. Grimes

    2010-01-13

    This report presents a summary of research projects in the area of low energy nuclear reactions and structure, carried out between March 1, 2006 and October 31, 2009 which were supported by U.S. DOE grant number DE-FG52-06NA26187.

  11. Thermal expansion of the nuclear fuel-sodium reaction product Na{sub 3}(U{sub 0.84(2)},Na{sub 0.16(2)})O{sub 4} - Structural mechanism and comparison with related sodium-metal ternary oxides

    Energy Technology Data Exchange (ETDEWEB)

    Illy, Marie-Claire [Chimie ParisTech, PSL Research University, CNRS, Institut de Recherche de Chimie Paris (IRCP), F-75005 Paris (France); European Commission, Joint Research Centre, P.O. Box 2340, 76125 Karlsruhe (Germany); Smith, Anna L. [European Commission, Joint Research Centre, P.O. Box 2340, 76125 Karlsruhe (Germany); Delft University of Technology, Faculty of Applied Sciences, Department of Radiation Science & Technology, Nuclear Energy and Radiation Applications (NERA), Mekelweg 15, 2629 JB, Delft (Netherlands); Wallez, Gilles, E-mail: gilles.wallez@upmc.fr [Chimie ParisTech, PSL Research University, CNRS, Institut de Recherche de Chimie Paris (IRCP), F-75005 Paris (France); Sorbonne University, UPMC Université, Paris 06, 75005 Paris (France); Raison, Philippe E.; Caciuffo, Roberto; Konings, Rudy J.M. [European Commission, Joint Research Centre, P.O. Box 2340, 76125 Karlsruhe (Germany)

    2017-07-15

    Na{sub 3.16(2)}U{sup V,VI}{sub 0.84(2)}O{sub 4} is obtained from the reaction of sodium with uranium dioxide under oxygen potential conditions typical of a sodium-cooled fast nuclear reactor. In the event of a breach of the steel cladding, it would be the dominant reaction product forming at the rim of the mixed (U,Pu)O{sub 2} fuel pellets. High-temperature X-ray diffraction measurements show that a distortion of the uranium environment in Na{sub 3.16(2)}U{sup V,VI}{sub 0.84(2)}O{sub 4} results in a strongly anisotropic thermal expansion. A comparison with several related sodium metallates Na{sub n-2}M{sup n+}O{sub n-1} - including Na{sub 3}SbO{sub 4} and Na{sub 3}TaO{sub 4}, whose crystal structures are reported for the first time - has allowed us to assess the role played in the lattice expansion by the M{sup n+} cation radius and the Na/M ratio. On this basis, the thermomechanical behavior of the title compound is discussed, along with those of several related double oxides of sodium and actinide elements, surrogate elements, or fission products. - Highlights: •Thermal expansion and structural mechanism of Na{sub 3}(U{sub 0.84(2)},Na{sub 0.16(2)})O{sub 4}, main product of the reaction of sodium with nuclear fuel. •Thermomechanical behavior of sodium uranate suggests possible strains on the fuel cladding and risks of de-cohesion with the fuel pin. •Effect of homo- and aliovalent cation substitutions allows to predict the thermomechanical behavior of sodium metallates involving fission products or minor actinide elements. •Crystal structure of new compounds Na{sub 3}SbO{sub 4} and Na{sub 3}TaO{sub 4}.

  12. 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)

  13. Characterisation of Ba(OH){sub 2}–Na{sub 2}SO{sub 4}–blast furnace slag cement-like composites for the immobilisation of sulfate bearing nuclear wastes

    Energy Technology Data Exchange (ETDEWEB)

    Mobasher, Neda; Bernal, Susan A.; Hussain, Oday H. [Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Sheffield S1 3JD (United Kingdom); Apperley, David C. [Solid-State NMR Group, Department of Chemistry, Durham University, Durham DH1 3LE (United Kingdom); Kinoshita, Hajime [Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Sheffield S1 3JD (United Kingdom); Provis, John L., E-mail: j.provis@sheffield.ac.uk [Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Sheffield S1 3JD (United Kingdom)

    2014-12-15

    Soluble sulfate ions in nuclear waste can have detrimental effects on cementitious wasteforms and disposal facilities based on Portland cement. As an alternative, Ba(OH){sub 2}–Na{sub 2}SO{sub 4}–blast furnace slag composites are studied for immobilisation of sulfate-bearing nuclear wastes. Calcium aluminosilicate hydrate (C–A–S–H) with some barium substitution is the main binder phase, with barium also present in the low solubility salts BaSO{sub 4} and BaCO{sub 3}, along with Ba-substituted calcium sulfoaluminate hydrates, and a hydrotalcite-type layered double hydroxide. This reaction product assemblage indicates that Ba(OH){sub 2} and Na{sub 2}SO{sub 4} act as alkaline activators and control the reaction of the slag in addition to forming insoluble BaSO{sub 4}, and this restricts sulfate availability for further reaction as long as sufficient Ba(OH){sub 2} is added. An increased content of Ba(OH){sub 2} promotes a higher degree of reaction, and the formation of a highly cross-linked C–A–S–H gel. These Ba(OH){sub 2}–Na{sub 2}SO{sub 4}–blast furnace slag composite binders could be effective in the immobilisation of sulfate-bearing nuclear wastes.

  14. 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)

  15. 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)

  16. The activity of superoxide dismutase in animal liver and erythrocyte at Sea Area nearby Dayawan Nuclear Power Station

    International Nuclear Information System (INIS)

    Cheng, Ge; Cai, Yana; Chen, Huizhen

    1995-01-01

    Many tests, the effect of ionizing radiation on SOD in vivo and vitro, had proved that the irradiation can cause the SOD activity to decrease with the increase of irradiation dose, change some physicochemical properties and structure. This artical was to study the activity of SOD in Fish (Thearpon jorbua) and Toad(Bufo melanostictus) liver erythrocyte at sea area nearby Dayawan Nuclear Power Station (Nps). We found that the SOD activity in fish liver, after NPS revolved one year, was higher than that of before revoling (7.30 ± 1.35U/mg protein, 5.49 ±1.56 U/mg protein respectively). The SOD activity in the toad liver at NPS revolving one year after was decreased (4.54 ± 0.75 U/mg protein 5.68± 1.49U/mg protein P < 0.001) but in erythrocyte increased (2.32 ± 0.75 U/mg Hb, 0.70 ± 0.33 U/mg Hb P < 0.001). These results indicated that the SOD activity was changed in different with the animal variety. The effect of irradiation on fish at present was absent, on toad need to research in the future

  17. A study of the anthropic activities impact on the Black Sea eco-system (Romanian coast area) using nuclear methods

    International Nuclear Information System (INIS)

    Timofte, L.

    1997-01-01

    This research represents a first step in the direction of a real evaluation of the Black Sea - Romanian Coast pollution level. A continental closed sea, with a special chemism and a specific dynamic regime of its waters, the Black Sea is seriously affected by pollution today, its eco - systems suffering deep restructuring, many of these with an irreversible character and an alarming degradation of the marine life quality. Starting with 1996, a systematic sampling of the principal systemic parts of the Black Sea Eco - System (Romanian Coast Area) was initiated at NIPNE - HH Bucharest. The samples are prepared and analysed by high precision nuclear methods such as: neutron activation analysis, atomic absorption spectrometry, inductively coupled plasma mass spectrometry and others. The results are presented as distribution maps and profiles of different elements (radioactive elements, heavy metals, trace elements etc.) in the investigated parts of the marine environment (water, sediments, vegetation and fauna). The research methodology and the obtained results offer a useful and efficient tool for the followup and permanent evaluation of the eco - system of the Black Sea. Monitoring this eco - system using a network and an efficient programme allows the storage of valuable data which are further used to make short - term and long - term prognosis referring to its evaluation. The results fit into the newest research programmes initiated by the international scientific community in the line of environment surveillance (The Programme of the International Board for Scientific Exploration of the Mediterranean supported by the European Community and US). (author)

  18. Off-site environmental monitoring report: radiation monitoring around United States nuclear test areas, calendar year 1984

    International Nuclear Information System (INIS)

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

    1985-04-01

    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 1984. 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 radionuclides releases yield an estimated dose of 1 x 10 -3 person-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 0.6 mrem per year. Plutonium in air was still detectable along with krypton-85, which continued its gradual increase, as has been reported previously. Cesium and strontium in air were near their 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. 32 refs., 36 figs., 27 tabs

  19. 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). The general Task continued to coordinate project activities to meet general deadlines and responsibilities. The central office provided general secretarial support. The activities that were started during the first project period included expansion of the central copying facilities, growth of the central reprint, map, aerial and photograph collections, and some expansion of personal computer capabilities. The research and review accomplishments are mainly under the following tasks: quaternary tectonics, geochemical, mineral deposits, volcanic geology, seismology, tectonics, neotectonics, remote sensing, geotechnical assessments, geotechnical rock mass assessment, basinal studies, and strong ground motion

  20. Protection of people living in long-term contaminated areas after a nuclear accident: the guidance of ICRP Publication 111

    International Nuclear Information System (INIS)

    Lochard, Jacques

    2012-01-01

    The International Commission on Radiological Protection provides guidance for the protection of people living in long-term contaminated areas after nuclear accidents or radiological emergencies in ICRP Publication 111 (Ann. ICRP 2009, 39(3)). The prolonged exposures resulting from such events are defined as existing exposure situations and the driving principle for managing exposure situations is the optimization of protection. In conjunction with optimization, the Commission recommends the use of reference levels to restrict individual doses. To be effective, protection strategies to maintain and reduce exposure as low as reasonably achievable should include actions implemented by public authorities and private businesses, but also by the affected population itself. The process through which inhabitants living in a contaminated environment identify problems and apply their own protective actions has been named 'self-help protection' by the Commission. Such a process supposes that affected individuals are fully aware of the situation and are well informed. It is the responsibility of the authorities to establish programmes for continuous radiation monitoring, information and education of the population. The involvement of local professionals and inhabitants in the definition and implementation of protection strategies is a key factor for the sustainability of long-term rehabilitation programmes. (note)

  1. [Cytochemical parameters of myeloperoxidase activity and catecholamine level in blood of postpartum women living in areas near the Semipalatinsk nuclear test site].

    Science.gov (United States)

    Kokabaeva, A E; Bazeliuk, L T

    2002-01-01

    The activity of neitrophil myeloperoxidase and content of blood etyrhrocyte cathecholamines in the blood of women in early postpartum period in dependence on distance of their living area from Semipalatinsk nuclear testing were studied. It was found that women who live closer to Semipalatinsk were characterised by significantly lower neitrophil myeloperoxidase activity and content of cathecholamines in erythrocytes than in control.

  2. The structural evolution of the coastal area between Danger Point and Struisbaai in the southern Cape Fold Belt, with implications for the siting of a nuclear power station

    International Nuclear Information System (INIS)

    Andersen, N.J.B.; Andreoli, M.A.G.

    1990-01-01

    A structural analysis of the coastal area between Danger Point and Struisbaai in the Southern Cape has been undertaken, using the technique of structural domain analysis coupled with geophysical interpretation and geological mapping. This study forms part of the country-wide geological investigations that are being carried out for the purpose of siting South Africa's future nuclear power stations. 30 refs., 18 figs

  3. Nuclear medicine

    International Nuclear Information System (INIS)

    Lentle, B.C.

    1986-01-01

    Several growth areas for nuclear medicine were defined. Among them were: cardiac nuclear medicine, neuro-psychiatric nuclear medicine, and cancer diagnosis through direct tumor imaging. A powerful new tool, Positron Emission Tomography (PET) was lauded as the impetus for new developments in nuclear medicine. The political environment (funding, degree of autonomy) was discussed, as were the economic and scientific environments

  4. Consolidated progress report for 1975 on nuclear data activities outside the NDS service area: Austria, Belgium, Greece, Spain, Switzerland, Turkey

    International Nuclear Information System (INIS)

    1975-12-01

    A consolidated progress report for 1975 on nuclear data activities in the following countries and institutes is presented: Austria: Atominstitut der Oesterreichischen Hochschulen, Vienna; Institut fuer Radiumforschung und Kernphysik; Oesterreichische Studiengesellschaft fuer Atomenergie, Seibersdorf; Gesellschaft zur Foerderung der Kernenergie, Graz; Belgium: University of Ghent, Ghent; University of Louvain, Louvain; Nuclear Energy Center, Mol; Greece: N.R.C. ''Demokritos'', Athens; Spain: Junta de Energia Nuclear, Madrid; Universidad Complutense, Madrid; Universidad Autonoma de Madrid, Madrid; Instituto de Fisica Corpuscular, Valencia; Universidad de Valladolid; Universidad de Zaragoza; Switzerland: University of Neuchatel, Neuchatel; University of Fribourg, Fribourg; University of Zuerich, Zuerich; Eidgenoessische Technische Hochschule, Zuerich; Institute for Reactor Research, Wuerenlingen; Turkey: Cekmece Nuclear Research Center, Istanbul

  5. Activities of radionuclides in the Pacific coastal area of Fukushima since the TEPCO Fukushima Daiichi Nuclear Power Station accident - Activities of radionuclides in the coast area off Fukushima after TEPCO's Fukushima Daiichi Nuclear Power Station accident

    Energy Technology Data Exchange (ETDEWEB)

    Aono, Tatsuo; Fukuda, Miho; Yoshida, Satoshi [National Institute of Radiological Sciences, 263-8555, Chiba (Japan); Sohtome, Tadahiro; Mizuno, Takuji [Fukushima Prefecture Fisheries Experimental Station, 970-0316, Fukushima (Japan); Igarashi, Satoshi [Fukushima Prefecture Fisheries Experimental Station, 970-0316, Fukushima (Japan); Fukushima Prefecture Sea-Farming Association, 970-8044, Fukushima (Japan); Ito, Yukari; Kanda, Jota; Ishimaru, Takashi [Tokyo University of Marine Science and Technology, 108-0075, Tokyo (Japan)

    2014-07-01

    The accident of TEPCO's Fukushima Daiichi Nuclear Power Station (FDNPS) has caused the release of the huge quantities of radionuclide by the 2011 Great East Japan Earthquake and Tsunami, and then the serious problems gave rise to pollution in marine environment widely in the coast area off Fukushima. Monitoring of radioactivity in seawater and biota are important for understanding the dispersion of radionuclides and the effects of radioecology in the marine environment around the coast of Fukushima and the Pacific. The activities of Cs-134 and Cs-137 in seawater decreased exponentially and then were almost same levels before the accident around off Fukushima after about three years from the accident. However, the high activities of radio caesium (Cs) have been monitored in marine biota off Fukushima. The aims of the present study were to examine the temporal changes in radioactivity and to clarify the variation factor and the effect of radioecology in marine biota. Cs-134 and Cs-137, and Ag-110m, were released by this accident, determined in biota sample such as the plankton, fish and benthos, although it is well-known that molluscs and crustaceans concentrate silver in visceral parts. However, Sr-90 was not detected and the activities of plutonium were almost same level before this accident in the marine biota around off Fukushima. Concentration ratios of Cs (CR-Cs) in marine organism were from 2.6 E+1 in the muscle part of squid to 1.0 E+4 in the viscera of clam. The large differences in CR-Cs by the parts of marine organism were not observed. It is suggested that rapid change in the activities of radio Cs and silver in seawater, resuspension of particles from sediments and food chain effects led to high radionuclide activities in marine biota after this accident. CR-Cs in plankton was also calculated with the activities in seawater, which were collected around sampling area during this monitoring period. These resulting values ranged from 5.8 E+1 to 7.8 E+2

  6. Dose evaluation on the basis of {sup 24}Na activity in the human body for the criticality accident at JCO Tokai nuclear fuel processing plant

    Energy Technology Data Exchange (ETDEWEB)

    Momose, T.; Tsujimura, N.; Tasaki, T.; Kanai, K.; Hayashi, N.; Shinohara, K. [Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)

    2000-07-01

    Sodium-24({sup 24}Na) generated in human body due to neutron activation was measured by whole body counter (WBC) in JNC Tokai works. Total 148 persons (JCO employees and contractor, public member, fire fighters, etc.) were measured and {sup 24}Na was detected in the 62 persons. Neutron energy spectrum around the facility was calculated using ANISN and MCNP code and estimated mean capture probability {xi} of neutron for human body at this accident was around 0.25-0.28 at any distance from the center of the precipitation tank. Effective dose equivalent for the 62 persons were estimated based on the calculated conversion factors from {sup 24}Na specific activity to neutron dose. Maximum {sup 24}Na activity was 7.7 kBq (83 Bq({sup 24}Na)/g({sup 23}Na)) in total body and the evaluated effective dose equivalent was 47 mSv. (author)

  7. AIDS e doenças oportunistas transmissíveis na faixa de fronteira Brasileira AIDS and transmissible opportunistic diseases in the Brazilian border area

    Directory of Open Access Journals (Sweden)

    Antonio Luiz Rodrigues-Júnior

    2010-10-01

    Full Text Available INTRODUÇÃO: A transmissão do HIV e de outras doenças transmissíveis, de pessoa a pessoa, pode ser associada à mobilidade humana. Este trabalho avaliou a incidência de doenças oportunistas transmissíveis entre os casos de AIDS, nos municípios da faixa de fronteira brasileira. MÉTODOS: Os municípios da faixa de fronteira brasileira foram agrupados em três regiões culturais; foram consideradas as notificações feitas ao Ministério da Saúde, entre 1990 e 2003, que tenham sido feitas com os critérios de definição CDC adaptado, Rio de Janeiro/Caracas e óbito; as doenças oportunistas detectadas foram agrupadas de acordo com o tipo de transmissão: 1 inalação do agente; 2 ingestão de água/alimento contaminado e 3 contato interpessoal. A análise descritiva considerou regiões culturais, anos de escolaridade, categoria de transmissão, sexo e faixa etária. RESULTADOS: Houve diferentes padrões de incidência de AIDS nos grupos de doenças oportunistas em cada região cultural. A região extremo-sul apresentou a maior incidência de AIDS; o número de casos de AIDS do sexo feminino foi maior na categoria heterossexual; o número de casos de AIDS do sexo masculino foi maior entre usuários de drogas injetáveis; as doenças transmitidas pelo contato interpessoal foram as mais frequentes, destacando a incidência de monilíases; a tuberculose e a pneumonia foram as mais frequentes dentre as doenças transmitidas pela inalação do agente; as doenças transmitidas pela ingestão de água/alimentos contaminados mostraram um padrão de incidência estável. CONCLUSÕES: A fronteira brasileira é um espaço geográfico importante e heterogêneo; o enfrentamento da AIDS deve reconhecer as diferentes geografias culturais.INTRODUCTION: Person-to-person transmission of HIV and other communicable diseases may be associated with human geographic mobility. This article evaluated the incidence of transmissible opportunistic diseases among

  8. Semantic integration of scientific publications and research data: proposal of model of expanded publication for the area of nuclear sciences

    International Nuclear Information System (INIS)

    Sales, Luana Farias

    2014-01-01

    applied to the specificity of Nuclear Sciences. This was accomplished in two ways: through a literature review, for purposes of analysis and qualitative interpretation of the general concepts; and through the domain analysis approach that allowed empirically analyze the particular application area. As a final result was obtained a proposal of guidelines for a national policy for digital curation, and a model of scientific publication to the Nuclear Sciences area, in which the research data are linked to the academic publications by means of semantic relations systematized into taxonomy built for this purpose. Graphic models are used as a tool to represent and synthesize the resulting concepts. As a conclusion it is observed: changes in the scholarly communication cycle, the possibility of building a new scientific model as relevant standard to the practice of a more open and more collaborative science, and feasibility of incorporating the principles and theories of librarianship and Information Science for the organization of technical and scientific knowledge in the world of eScience. (author)

  9. Fire barrier evaluation of the wall between spent nuclear fuel storage basins and reactor areas, 105KE and 105KW

    International Nuclear Information System (INIS)

    Johnson, B.H.

    1994-01-01

    This evaluation is intended to provide a comprehensive assessment of the risks from fire and fire related perils for the fire barriers between spent nuclear fuel storage basins and reactor areas, 105KE and 105KW. As a result of this fire barrier evaluation the present walls and the components thereof are not a true listed fire rated assembly. However, due to the construction of these barriers and the components thereof, these barriers will provide an equivalent level of protection provided the recommendations in Section 8.0 of this report are completed. These recommended upgrades are based upon sound engineering practice by a Registered Fire Protection Engineer. The construction of the barrier are substantial enough to provide the required 2-hr fire resistance rating. The primary concern is the numerous penetrations in the barrier. There are many penetrations that are adequate and no additional work is required. These penetrations are the ones that were poured-in-place at the time of construction. The penetrations that are of concern are some of the doors, the HVAC ducts, and the unsealed piping and conduit penetrations. There are several metal doors that should be replaced because the existing doors have either a non-approved window or louver that will not limit the spread of fire to one side of the barrier. All unsealed piping and conduit penetrations should be firestopped with an approved firestopping material. The existing non-active ducts that pass through the barrier should be disconnected at the barrier and the opening sealed with an approved firestopping method

  10. In-Containment Signal Acquisition and Data Transmission via Power Lines within High Dose Areas of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Mueller Steffen; Wibbing Sascha; Weigel Robert; Koelpin Alexander; Dennerlein, Juergen; Janke, Iryna; Weber, Johannes

    2015-01-01

    Signal acquisition and data transmission for innovative sensor systems and networks inside the containment of nuclear power plants (NPPs) is still a challenge with respect to safety, performance, reliability, availability, and costs. This especially applies to equipment upgrades for existing plants, special measurements, but also for new builds. This paper presents a novel method for efficient and cost-effective sensor signal acquisition and data transmission via power lines, in order to cope with the disadvantages of common system architectures that often suffer from poor signal integrity due to raw data transmissions via long cables, huge efforts and costs for installation, and low flexibility with respect to maintenance and upgrades. A transmitter-receiver architecture is proposed that allows multiplexing of multiple sensor inputs for unidirectional point-to-point transmission by superimposing information signals on existing AC or DC supply lines, but also on active and inactive sensor wires, or spare cables, using power line communication (PLC) technology. Based on commercial off-the-shelf (COTS) electronic parts, a radiation hard transmitter hardware is designed to operate in harsh environment within the containment during full plant operation. The system's modular approach allows application specific trade-offs between redundancy and throughput regarding data transmission, as well as various sensor input front-ends which are compatible with state of the art systems. PLC technology eliminates the need for costly installation of additional cables and wall penetrations, while providing a complementary and diverse communication technology for upgrades of existing systems. At the receiver side in low dose areas, signals are extracted from the power line, demodulated, and de-multiplexed, in order to regain the original sensor signal information and provide it either in analog or digital output format. Successful laboratory qualification tests, field trails

  11. In-Containment Signal Acquisition and Data Transmission via Power Lines within High Dose Areas of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Mueller Steffen; Wibbing Sascha; Weigel Robert; Koelpin Alexander [Institute for Electronics Engineering, University of Erlangen-Nuremberg (Germany); Dennerlein, Juergen; Janke, Iryna; Weber, Johannes [AREVA GmbH, Paul-Gossen-Str. 100, 91052 Erlangen (Germany)

    2015-07-01

    Signal acquisition and data transmission for innovative sensor systems and networks inside the containment of nuclear power plants (NPPs) is still a challenge with respect to safety, performance, reliability, availability, and costs. This especially applies to equipment upgrades for existing plants, special measurements, but also for new builds. This paper presents a novel method for efficient and cost-effective sensor signal acquisition and data transmission via power lines, in order to cope with the disadvantages of common system architectures that often suffer from poor signal integrity due to raw data transmissions via long cables, huge efforts and costs for installation, and low flexibility with respect to maintenance and upgrades. A transmitter-receiver architecture is proposed that allows multiplexing of multiple sensor inputs for unidirectional point-to-point transmission by superimposing information signals on existing AC or DC supply lines, but also on active and inactive sensor wires, or spare cables, using power line communication (PLC) technology. Based on commercial off-the-shelf (COTS) electronic parts, a radiation hard transmitter hardware is designed to operate in harsh environment within the containment during full plant operation. The system's modular approach allows application specific trade-offs between redundancy and throughput regarding data transmission, as well as various sensor input front-ends which are compatible with state of the art systems. PLC technology eliminates the need for costly installation of additional cables and wall penetrations, while providing a complementary and diverse communication technology for upgrades of existing systems. At the receiver side in low dose areas, signals are extracted from the power line, demodulated, and de-multiplexed, in order to regain the original sensor signal information and provide it either in analog or digital output format. Successful laboratory qualification tests, field trails

  12. Collective dose estimation in Portuguese population due to medical exams of diagnostic radiology and nuclear medicine; Estimativa da dose coletiva na populacao portuguesa devido a exames medicos de radiologia de diagnostico e de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Teles, Pedro; Vaz, Pedro [Instituto Tecnologico e Nuclear, Sacavem (Portugal). Instituto Superior Tecnico; Sousa, M. Carmen de [Instituto Portugues de Oncologia de Coimbra (Portugal); Paulo, Graciano; Santos, Joana [Escola Superior de Tecnologia da Saude de Coimbra (Portugal); Pascoal, Ana [Kings College Hospital, London (United Kingdom). Kings Health Partners; Cardoso, Gabriela; Santos, Ana isabel [Hospital Garcia de Orta, Almada (Portugal); Lanca, Isabel [Administracao Regional de Saude, Coimbra (Portugal); Matela, Nuno [Universidade de Lisboa (Portugal). Fac. de Ciencias. Instituto de Biofisica e Engenharia Biomedica; Janeiro, Luis [Escola superior de Saude da Cruz Vermelha Portuguesa, Lisboa (Portugal); Sousa, Patrick [Laboratorio de Instrumentacao e Fisica Experimental de Particulas, Lisboa (Portugal); Carvoeiras, Pedro; Parafita, Rui [Medical Consult, SA, Lisboa (Portugal); Simaozinho, Paula [Administracao Regional de Saude, Faro (Portugal)

    2013-11-01

    In order to assess the exposure of the Portuguese population to ionizing radiation due to medical examinations of diagnostic radiology and nuclear medicine, a working group, consisting of 40 institutions, public and private, was created to evaluation the coletive dose in the Portuguese population in 2010. This work was conducted in collaboration with the Dose Datamed European consortium, which aims to assess the exposure of the European population to ionizing radiation due to 20 diagnostic radiology examinations most frequent in Europe (the 'TOP 20') and nuclear medicine examinations. We obtained an average value of collective dose of Almost-Equal-To 1 mSv/caput, which puts Portugal in the category of countries medium to high exposure to Europe. We hope that this work can be a starting point to bridge the persistent lack of studies in the areas referred to in Portugal, and to enable the characterization periodic exposure of the Portuguese population to ionizing radiation in the context of medical applications.

  13. Portable in situ NaI(Tl) γ spectroscopy system

    International Nuclear Information System (INIS)

    Wang Bairong; Dong Binjiang; Zeng Liping; Shen Tingyun

    2000-01-01

    The author describes a portable in situ NaI(Tl) γ spectroscopy system, which consists of a NaI (Tl) scintillation detector, an integrative spectroscopy card, a notebook computer and spectroscopy software. The spectrometer addresses applications in environmental or nuclear accident in situ γ spectroscopy measurements, and gives valid quantitative results of radionuclide concentrations per unit volume (Bq/kg) or unit area (Bq/cm 2 ) in the soil and absorbed dose rate in air at 1 m above ground (Gy/h)

  14. 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

  15. Guidelines for Nordic co-operation concerning nuclear installations in the border areas between Denmark, Finland, Norway and Sweden in respect of nuclear safety conditions

    International Nuclear Information System (INIS)

    1976-01-01

    These Guidelines were established by an Agreement between the Nordic countries. Their purpose is to set up a consultation mechanism between those countries regarding the projected setting up of nuclear facilities near borders which would be likely to affect their respective territories [fr

  16. Influência das gonadotrofinas na regulação da maturação nuclear de oócitos eqüinos Influence of gonadotropins on nuclear maturation of equine oocytes

    Directory of Open Access Journals (Sweden)

    Juan Manuel Larre Borges

    1998-06-01

    Full Text Available A maturação in vitro, fecundação e as técnicas de cultivo de embriões na espécie eqüina são extremamente importantes e necessárias para se examinar as causas de repetição de cio, redução de concepção em éguas velhas e também para a preservação da espécie eqüina. Para avaliar o efeito das gonadotrofinas na regulação da maturação nuclear de oócitos eqüinos, folículos com diâmetro entre 5 a 20mm foram aspirados de 551 ovários provenientes de matadouro obtendo-se 408 oócitos aptos para cultivo. Após a aspiração, os oócitos foram avaliados no próprio líquido folicular quanto a sua integridade e distribuídos nos diferentes tratamentos. No Tratamento I (T1 - grupo controle - os oócitos (n=92 foram cultivados em TCM-199 modificado (mod., com 25mM de HEPES, 2,2mg/ml de bicarbonato de sódio, 1 mi g/ml 17-beta estradiol, 250mi M de piruvato de sódio e 0,4% de albumina sérica bovina. No tratamento 2 (T2, os oócitos (n= 108 foram cultivados no mesmo meio TC M-199 mod. acrescido de lug/ml de hormônio luteinizante suíno (LHs. No Tratamento 3 (T3, os oócitos (n=102 também foram cultivados em TCM-199 mod. porém com 0,5mi g/ml de hormônio folículo estimulante suíno (FSHs e no Tratamento 4 (T4 os oócitos (n= 106 foram cultivados com 1mi g/ml de LHs e 0,5mi g/ml, de FSHs. Os oócitos dos quatros tratamentos foram cultivados em estufa a 39°C com 5% de CO2 , e 95% de umidade relativa no ar, durante 24 h. Após este período, as células do Cumulus oophorus foram removidas e os oócitos fixados em solução de ácido acético glacial-metanol (1:3 em placas de Petri 10 x 35mm por 24h sendo posteriormente corados com aceto-orceína. O percentual de oócitos em telófase I / metáfase II foi de 55,6% (59/106 para o T4 (FSHs/LHs e de 53,9% (55/102 para o T3 (FSHs, os quais não diferiram significativamente. No entanto, estes percentuais foram significativamente superiores (pIn vitro maturation, in vitro fertilization

  17. The CERES / NA45 experiment

    CERN Multimedia

    Laurent Guiraud

    2000-01-01

    Ceres is one of the second generation heavy ion experiments at CERN's SPS. It is dedicated to the study of electron-positron pairs in relativistic nuclear collisions. NA45 is one of the seven experiments (NA44, NA45, NA49, NA50, NA52, WA97/NA57 and WA98) involved in CERN's Heavy Ion programme which provided evidence for the existence of a new state of matter, the quark-gluon plasma. In this state, quarks, instead of being bound up into more complex particles such as protons and neutrons, are liberated and roam freely. Theory predicts that this state must have existed at about 10 microseconds after the Big Bang, before the formation of matter as we know it today.

  18. Case Study in Internal Audit of Nuclear Material; Etude d'un Systeme de Verification Comptable Interne des Matieres Nucleaires; Izuchenie primera organizatsii vnutrennego ucheta yadernykh materialov na predpriyatii; Estudio de la Fiscalizacion Interna de los Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Kops, S. [United States Atomic Energy Commission, Argonne, IL (United States)

    1966-02-15

    The general need for the internal audit function and the basic principles of management underlying this need are briefly discussed. The size, complexity and degree of centralization, or decentralization, are usually the main factors in determining the need for a conventional internal audit. Here, the more specialized needs and characteristics of an internal audit peculiar to an organization handling source or special fissionable material (nuclear material) are discussed and contrasted with an audit of the standard type. The necessity of a special audit, because of the high monetary and strategic value, is demonstrated. Planning the internal audit within a production plant is discussed in detail. This includes the rationale of timing the review together with the records and physical inventory to be tested and verified. Quality and types of professional skills of the personnel to be used in internal audit are also discussed. A qualified statistical plan in choosing the items to be tested is discussed. The application of the plans in the actual performance of the internal audit are described in detail. Possible variances from a recognized norm and possible approaches to audit resolution are discussed. Although in many other manufacturing situations there are variations in the methods of verifying inventories without physically doing so, the necessity for physically testing inventories of nuclear material is demonstrated. The various means of reporting the results of the internal audit are presented. The needs of individual groups within the organization are considered in determining the format of the report, as well as the basic content. Distribution of the report and its variations are discussed. (author) [French] L'auteur etudie brievement la necessite de la verification comptable interne en general, et les principes essentiels de gestion auxquels repond cette necessite. La taille de l'installation, la complexite et le degre de centralisation ou de decentralisation

  19. Informal Progress Report Contract Number: DE-FG03-02NA00074/A000

    International Nuclear Information System (INIS)

    Brune, Carl R.; Grimes, Steven M.

    2003-01-01

    OAK B127 We report on work performed under contract DE-FG03-03NA00074 since January 1,2003. The research is in the area of low energy nuclear reactions and nuclear structure. The progress on research on level densities and improvement to R-Matrix calculations are presented. The preparations to begin high resolution experiments on p-shell nuclei are reviewed

  20. Geological Mapping and Identification of Active Fault in Site Candidate of Nuclear Power Plant Installation at Ketapang Area and Its Surroundings, Madura

    International Nuclear Information System (INIS)

    Ngadenin; Lilik-Subiantoro; Kurnia-Setiawan-W; Agus-Sutriyono; P Widito

    2004-01-01

    The result of economical study about demand of electric and water supply in Madura Island in 2015 will increase double for domestic or support industry in Madura Island which have to be solved sooner. One way which is considered to solve the problem is Desalination with nuclear electrical plant. In order to support the installation of nuclear Desalination plant, it is needed site free or far from active fault. Active fault is mainly factor to reject the area on site selection process. Aim of the research is to get geological information and identify of active fault in the site candidate of nuclear Desalination plant at Ketapang area and its surrounding by interpretation of air photos and Landsat imagery, geological and structure geological mapping as well as trenching. The lithology of Ketapang and Sokobana site candidate consists of reef and chalky limestone with form of morphology is undulating hills. Structurally, research areas forms a mono cline with east-westerly trending axis, plunging 10 o to E, the direction of strike is W-E, dip 10 o -30 o to the north. This research concludes that an active fault was not found in the area. (author)

  1. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    Short communication. Full text included in abstract. The general manager of the Cigar Lake uranium mine in northern Saskatchewan, George Peebles, says high radiation levels in the mine will prevent miners from working in direct contact with the underground ore. The exceptionally high grade of uranium will force Cigar Lake Mining Corp. to adopt unconventional mining methods in which the equipment is controlled from remote locations. Mr. Peebles said that the uranium deposits at Cigar Lake are 100 times richer than the deposits at older uranium mines in Ontario, where workers can spend a full shift in direct contact with the uranium. Because the deposits are so rich, workers cannot be exposed to the gamma radiation and radon gas for more the a few hours at a time. The mining corporation will probably use the 'raise-boring' method, in which a drill is located in a tunnel above the ore zone. A vertical hole is then drilled through the ore. Under this method, several metres of rock will separate the drill operator from the uranium. The method is commonly used in hard-rock mining, but it has never been required in uranium mining. In addition, the corporation will have to use extensive ventilation to get rid of the radon gas in the mine. Moreover, because of ground stability problems at Cigar Lake, the corporation will find it difficult to use conventional drilling and blasting techniques. Special ground-support measures will be needed. Finally, the corporation will have to take precautions to deal with groundwater in the area. If the flow is not restricted, the mine would receive 2,000 cubic metres of water an hour, Mr. Peebles said. The Cigar Lake mine is the largest high-grade uranium deposit in the world. It contains an estimated 150,000 metric tons of uranium, mostly in ore with an average grade of 12% uranium. The uranium deposits are so rich that the mine can produce 5.5 million kilograms of uranium annually from slightly more than 90 tons of ore excavated each day

  2. The SSK recommendation 'planning areas for the surroundings of nuclear power plants'; Die SSK-Empfehlung 'Planungsgebiete fuer den Notfallschutz in der Umgebung von Kernkraftwerken'

    Energy Technology Data Exchange (ETDEWEB)

    Welte, Ulrike; Michel, Rolf; Mueller, Wolfgang-Ulrich

    2014-07-01

    After the Fukushima nuclear accident the BMU asked the SSK to check the guidelines for radiation emergency preparedness. Based on the information gained by the Japanese experience the SSK recommended to plan nuclear emergencies irrespective of the calculated probability of occurrence, but according to the effects of an INES 7 event. The SSK has recommended new planning areas for the surroundings of nuclear power plants based on a method developed by the SSK. This approach requires enlarged planning areas.

  3. Around Semipalatinsk nuclear test site: progress of dose estimations relevant to the consequences of nuclear tests (a summary of 3rd Dosimetry Workshop on the Semipalatinsk nuclear test site area, RIRBM, Hiroshima University, Hiroshima, 9-11 of March, 2005).

    Science.gov (United States)

    Stepanenko, Valeriy F; Hoshi, Masaharu; Bailiff, Ian K; Ivannikov, Alexander I; Toyoda, Shin; Yamamoto, Masayoshi; Simon, Steven L; Matsuo, Masatsugu; Kawano, Noriyuki; Zhumadilov, Zhaxybay; Sasaki, Masao S; Rosenson, Rafail I; Apsalikov, Kazbek N

    2006-02-01

    calculations. A possible explanation of the differences between ESR and RLD/calculations doses is the following: for interpretation of ESR data the "shielding and behaviour" factors for investigated persons should be taken into account. The "upper level" of the combination of "shielding and behaviour" factors of dose reduction for inhabitants of Dolon' village of about 0.28 was obtained by comparing the individual ESR tooth enamel dose estimates with the calculated mean dose for this settlement. The biological dosimetry data related to the settlements near SNTS were presented at the Workshop. A higher incidence of unstable chromosome aberrations, micronucleus in lymphocytes, nuclear abnormalities of thyroid follicular cells, T-cell receptor mutations in peripheral blood were found for exposed areas (Dolon', Sarjal) in comparison with unexposed ones(Kokpekty). The significant greater frequency of stable translocations (results of analyses of chromosome aberrations in lymphocytes by the FISH technique) was demonstrated for Dolon' village in comparison with Chekoman(unexposed village). The elevated level of stable translocations in Dolon' corresponds to a dose of about 180 mSv, which is close to the results of ESR dosimetry for this village. The importance of investigating specific morphological types of thyroid nodules for thyroid dosimetry studies was pointed out. In general the 3rd Dosimetry Workshop has demonstrated remarkable progress in developing an international level of common approaches for retrospective dose estimations around the SNTS and in understanding the tasks for the future joint work in this direction. In the framework of a special session the problems of developing a database and registry in order to support epidemiological studies around SNTS were discussed. The results of investigation of psychological consequences of nuclear tests, which are expressed in the form of verbal behaviour, were presented at this session as well.

  4. Molecular characterization of Fasciola spp. from the endemic area of northern Iran based on nuclear ribosomal DNA sequences.

    Science.gov (United States)

    Amor, Nabil; Halajian, Ali; Farjallah, Sarra; Merella, Paolo; Said, Khaled; Ben Slimane, Badreddine

    2011-07-01

    Fasciolosis caused by Fasciola spp. (Platyhelminthes: Trematoda: Digenea) is considered as the most important helminth infection of ruminants in tropical countries, causing considerable socioeconomic problems. In the endemic regions of the North of Iran, Fasciola hepatica and Fasciola gigantica have been previously characterized on the basis of morphometric differences, but the use of molecular markers is necessary to distinguish exactly between species and intermediate forms. Samples from buffaloes and goats from different localities of northern Iran were identified morphologically and then genetically characterized by sequences of the first (ITS-1) and second (ITS-2) Internal Transcribed Spacers (ITS) of nuclear ribosomal DNA (rDNA). Comparison of the ITS of the northern Iranian samples with sequences of Fasciola spp. from GenBank showed that the examined specimens had sequences identical to those of the most frequent haplotypes of F. hepatica (n=25, 48.1%) and F. gigantica (n=20, 38.45%), which differed from each other in different variable nucleotide positions of ITS region sequences, and their intermediate forms (n=7, 13.45%), which had nucleotides overlapped between the two Fasciola species in all the positions. The ITS sequences from populations of Fasciola isolates in buffaloes and goats had experienced introgression/hybridization as previously reported in isolates from other ruminants and humans. Based on ITS-1 and ITS-2 sequences, flukes are scattered in pure F. hepatica, F. gigantica and intermediate Fasciola clades, revealing that multiple genotypes of Fasciola are able to infect goats and buffaloes in North of Iran. Furthermore, the phylogenetic trees based upon the ITS-1 and ITS-2 sequences showed a close relationship of the Iranian samples with isolates of F. hepatica and F. gigantica from different localities of Africa and Asia. In the present study, the intergenic transcribed spacers ITS-1 and ITS-2 showed to be reliable approaches for the genetic

  5. Social safety and medical maintenance of the labour pool in surveillance areas of the nuclear power plants.

    Science.gov (United States)

    Prylipko, V A; Ozerova, Yu Yu; Kotsubinskij, O V; Morozova, M M; Petrychenko, O O; Bondarenko, I V

    2017-12-01

    To study the contentment of population of NPP surveillance areas i.e. monitoring zones with specific components of quality of life, namely the social security, medical care, and socio economic compensation of risk. A sociological study of public opinion about the specific components of quality of life has been conducted in population of the NPP monitoring zone. A questionnaire with independent question blocks was developed. A non repeatable probabilistic selection was applied in population opinion poll. The sampled population was calculated on the basis of the total population living in the NPP monitoring zone. Sample error not exceeded 7.0%. A comparative assessment of the responses of various groups of the able bodied population on issues of social security, medical care, socio economic compensation of risk and analysis of statistical data for 2011-2015 on the resource potential of medical facility of the nuclear power plant overspill town has been conducted. The safety and security status is rated at below the average. Documents regulating the life safety of pop ulation of NPP monitoring zone provide them no confidence in their security. Probability estimates of man made accidents are higher in urban population and depend on education level. The socialized health care is assessed on low and average levels according to the studied parameters. Among the types of medical care the providing of nec essary medical goods, preventive examinations, scheduled medical examination service, ambulance activity, and medical psychological aid need to be improved. There was no significant change in resource potential of special ized healthcare infirmary of NPP overspill town for the last 5 years. Low rating by the monitoring zone population of work efficiency of health facilities is determined by a set of factors, some of which lies in the plane of state socio economic problems. Choice priority of the direct sub ventions in population of monitoring zone depends on the place of

  6. Átomos na integração: a aproximação Brasil-Argentina no campo nuclear e a construção do Mercosul

    OpenAIRE

    Vargas, Everton Vieira

    1997-01-01

    Este trabalho tenciona ser uma reflexão sobre a importância da aproximação entre o Brasil e a Argentina no campo nuclear, na segunda metade da década de 80 e no início dos anos 90, como fundamento para a construção de um relacionamento novo que suplantou uma rivalidade histórica entre ambos. O processo de aproximação encetado com um propósito aparentemente econômico, tinha uma dimensão estratégica. As repercussões desse esforço iam além dos interesses bilaterais imediatos e se refletiram na b...

  7. Development of environmental monitoring robot against nuclear hazard and establishment of its wide-area transportation method using a cargo plane

    International Nuclear Information System (INIS)

    Magara, Shigenori; Kimura, Norio; Onishi, Ryoichi; Yamasaki, Hitoshi; Kimura, Toshimasa; Sugisaki, Norihiko; Maeyama, Hiroshi

    2008-01-01

    In case of nuclear hazard, collecting images and radiological information around the epicenter are strongly anticipated for making evacuation plans and securing residents' safety. In order to meet with this requirement, Nuclear Safety Technology Center has developed the two types of environmental monitoring robots; MONIROBO-A and -B, which work for gathering the images and monitoring the radiation doses in hazardous area through the remote-control by the operator in distant secured area. MONIROBO-A collects the images of hazard center using laser scanner and infrared camera, while MONIROBO-B monitors the atmospheric condition using neutron measurement device, flammable gas detector and dust sampler. Also the both types have gamma ray measurement instruments and manipulators. They are sized almost 1.5 m in length and height, and weighed 600kg in mass. (author)

  8. Aerial radiological survey of the Davis-Besse Nuclear power Station and surrounding area, Oak Harbor, Ohio. Date of survey: 26-29 May 1980

    International Nuclear Information System (INIS)

    Hilton, L.K.

    1980-12-01

    An airborne radiological survey of a 130 km 2 area centered on the Davis-Besse Nuclear Power Station was made 26-29 May 1980. Count rates observed at 90 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 station

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

    International Nuclear Information System (INIS)

    Almeida, A.F.V. de

    1995-01-01

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

  10. Dose evaluation on the basis of {sup 24}Na activity in the human body for the criticality accident at JCO Tokai nuclear fuel processing plant

    Energy Technology Data Exchange (ETDEWEB)

    Momose, T.; Tsujimura, N.; Tasaki, T.; Kanai, K.; Hayashi, N.; Shinohara, K. [Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)

    2001-11-01

    {sup 24}Na in the human body, activated by neutrons emitted at the JCO criticality accident, was observed for 62 subjects, where 148 subjects were measured by the whole body counter of JNC Tokai Works. The 148 subjects, including JCO employees and the contractors, residents neighboring the site and emergency service officers, were measured by the whole-body counter. The neutron-energy spectrum around the facility was calculated using neutron transport codes (ANISN and MCNP), and the relation between an amount of activated sodium in human body and neutron dose was evaluated from the calculated neutron energy spectrum and theoretical neutron capture probability by the human body. The maximum {sup 24}Na activity in the body was 7.7 kBq (83 Bq({sup 24}Na)/g({sup 23}Na)) and the relevant effective dose equivalent was 47 mSv. (author)

  11. Dose evaluation on the basis of 24Na activity in the human body for the criticality accident at JCO Tokai nuclear fuel processing plant

    International Nuclear Information System (INIS)

    Momose, T.; Tsujimura, N.; Tasaki, T.; Kanai, K.; Hayashi, N.; Shinohara, K.

    2001-01-01

    24 Na in the human body, activated by neutrons emitted at the JCO criticality accident, was observed for 62 subjects, where 148 subjects were measured by the whole body counter of JNC Tokai Works. The 148 subjects, including JCO employees and the contractors, residents neighboring the site and emergency service officers, were measured by the whole-body counter. The neutron-energy spectrum around the facility was calculated using neutron transport codes (ANISN and MCNP), and the relation between an amount of activated sodium in human body and neutron dose was evaluated from the calculated neutron energy spectrum and theoretical neutron capture probability by the human body. The maximum 24 Na activity in the body was 7.7 kBq (83 Bq( 24 Na)/g( 23 Na)) and the relevant effective dose equivalent was 47 mSv. (author)

  12. Gestão participativa na recuperação de área degradada pela agricultura / Participatory management in recovery degraded area by agriculture

    Directory of Open Access Journals (Sweden)

    Carlos Henrique Bonsi Checoli

    2016-09-01

    Full Text Available Pesquisadores da Universidade Federal de Mato Grosso (UFMT subsidiaram uma estratégia de gestão participativa, visando o planejamento e implantação de um plano de recuperação de área degradada (PRAD em área de preservação permanente degradada pelo uso agrícola, na bacia hidrográfica do rio São Lourenço, em Campo Verde, município de destaque no agronegócio mato-grossense e brasileiro. A pesquisa ocorreu mediante dinâmicas de grupo no contexto de algumas técnicas de gestão da qualidade utilizadas na norma ISO 9001. Verificou-se pouca interação entre os atores locais em termos da implantação de ações de recuperação ambiental. O custo econômico de implantação e manutenção do PRAD representaram fatores limitantes. A falta de perspectiva de considerar o PRAD como fornecedor de área produtiva, também foi considerado um entrave na perspectiva dos produtores rurais. A pesquisa fortaleceu as ações da UFMT, visando diminuir a degradação que ocupa em torno de um terço do território de Mato Grosso.

  13. Childhood leukemia near nuclear plants in the United Kingdom: The evolution of a systematic approach to studying rare disease in small geographic areas

    International Nuclear Information System (INIS)

    Beral, V.

    1990-01-01

    A cluster of childhood leukemia in a village near a nuclear plant in northern England prompted further studies of cancer in the vicinity of other nuclear plants in the United Kingdom. These studies demonstrated that the risk of childhood leukemia was increased near certain other nuclear plants. Although the reasons for the increase are still unclear, the scientific debate stimulated by these findings has clarified some of the special methodological problems encountered when studying rare diseases in small areas. Firstly, unless a specific hypothesis is defined in advance, the relevance of a single geographic cluster of disease can rarely be interpreted. Even when a prior hypothesis exists, the small number of cases which generally occur in a small area make the findings highly sensitive to reporting, diagnostic, or classification errors. The statistical power of such investigations is also usually low and only marked increases in risk can be detected. Furthermore, conventional statistical tests may be inappropriate if the underlying spatial distribution of the disease is not random; and little is known about the background distribution of disease in small areas. Investigations of specific hypotheses about defined sources of environmental contamination, especially if they can be replicated, are more likely to result in conclusive findings that are in-depth studies of individual clusters

  14. Fishes of Saco do Piraquara de Fora, in a discharge area of liquid effluents from Angra-1 Nuclear Power Plant (CNAAA)

    International Nuclear Information System (INIS)

    Almeida, Ademar Ferrari Vaz de; Santoro, Maria Dulce Novaes

    1996-01-01

    Because the thermal effluents, released from the Unit I condenser system, it was implanted, at discharge area (Saco Piraquara de Fora), a Marine Fauna and Flora Monitoring Program, been necton area part of this, to verify possible impact over fish population, quantitative and qualitative studies were performed. Trichiurus lipeturus and Diapterus rhombeus were chosen as indicators because the high frequencies and abundances. Besides this, Furnas implanted a Radiological Monitoring Program, where samples of fish were collected and analysed by gamma spectrometry, showing the presence of Cs-137 since the pre-operational period, caused by fall out process at the region, from nuclear weapons test at atmosphere. (author)

  15. Investigation on U - O - Na, Pu - O - Na and U,Pu - O - Na phase diagrams

    International Nuclear Information System (INIS)

    Pillon, S.

    1989-03-01

    The thermochemical interaction between the nuclear fuel (uranium and plutonium mixed oxides) and the sodium has been investigated and particularly the three phase diagrams: U - O - Na; Pu - O - Na; U,Pu - O - Na. High temperature neutron diffraction, microcalorimetry and powder X-ray diffraction were used for the characterization of the compounds synthetized. This study allowed to complete the knowledge about each of these diagrams and to measure some physical and thermal properties on the compounds. The limits on the modelization of the fuel-sodium interaction are discussed from the results of the UO 2 - Na reaction [fr

  16. An aerial radiological survey of the Perry Nuclear Power Plant and surrounding area, North Perry, Ohio: Date of survey: April 1987

    International Nuclear Information System (INIS)

    Fritzsche, A.E.

    1987-01-01

    An aerial radiological survey was conducted over the Perry Nuclear Power Plant, North Perry, Ohio. The purpose of the 234-square-kilometer (91-square-mile) survey was to document the terrestrial gamma environment of the plant and surrounding area. An exposure rate contour map at 1 meter above ground level was constructed from the gamma data and overlaid on an aerial photograph and map of the area. Exposure rates increased from 0 microroentgens per hour (μR/h) over Lake Erie to 9 μR/h as the distance from Lake Erie increased. Only one anomalous area appears on the map, which is due to an excess of Bi-214 in a landfill area. Ground-based exposure rate measurements and soil samples were obtained to support the aerial data. Oblique aerial photographs of the plant were also acquired during the survey. 6 refs., 6 figs., 1 tab

  17. Aerial radiological survey of the Diablo Canyon Nuclear Power Plant and surrounding area, Diablo Canyon, California. Date of survey: September-October 1984

    International Nuclear Information System (INIS)

    1985-03-01

    An aerial radiological survey was conducted over the area surrounding the Diablo Canyon Nuclear Power Plant in Diablo Canyon, California. The survey was conducted between 20 September and 3 October 1984. A series of flight lines parallel to the coastline were flown at an altitude of 91 meters (300 feet) and were spaced 152 meters (500 feet) apart. The survey covered an area of 250 square kilometers (100 square miles). The resulting background exposure rates over the survey area ranged from 5 to 21 microroentgens per hour (μR/h). The reported exposure rate values include an estimated cosmics ray contribution of 3.6 μR/h. Soil samples were also collected at several locations within the survey areas and analyzed in the laboratory for isotopic composition. The results of the survey showed only the presence of naturally occurring background radiation. No man-made radioactivity was detected. 4 refs., 4 figs., 4 tabs

  18. Nuclear proliferation and terrorism

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    This section of the book, Part III, has two chapters (9 and 10). Chapter 9, Nuclear Power and Proliferation of Nuclear Weapons, is disucssed under these subjects: nuclear nonproliferation: origins and status; requirements for nuclear weapons manufacture; current nuclear programs and proliferation capabilities; encouraging decisions to forego weapons; arms control; safeguards; attitudes and expectations. Chapter 10, Nuclear Terrorism, discusses these areas: theft of nuclear materials; attacks on nuclear reactors; responding to nuclear terrorism; security and civil liberties

  19. System approach for evaluation of air pollution toxic compounds in the 30-km area of nuclear power plants

    International Nuclear Information System (INIS)

    Shevtsova, O.V.; Zhigunova, L.N.; Makovskaya, N.A.; Pavlovich, E.L.

    2012-01-01

    The article shows the importance of a systematic approach to address environmental problems that arise during the construction of nuclear power plants, and identified the need to consider the transformation and biotransformation of primary pollutants and monitoring secondary pollutants. The basic pathways of pollutants in the air a 30-km zone of nuclear power plants established. The content of primary and secondary air pollutants identified. The evaluation of general toxic risk from primary pollutant and the calculation of the carcinogenic risk of secondary pollutants entering the body by inhalation are carried out. (authors)

  20. The activities of the Institute of Nuclear Physics and Uzbekistan INIS Centre on attracting a young generation into the nuclear area

    International Nuclear Information System (INIS)

    Kadirova, M.; Salimov, M.I.; Ananchenkov, V.I.; Gurvich, L.G.; Tillaev, T.S.; Trofimova, R.B.

    2004-01-01

    In order to attract young scientists to the research works in the field of nuclear physics the Institute of Nuclear Physics develop its own programme on education and training of staff and young generation. Leading researchers of the Institute are involved in the preparation of the masters, PhD and doctorate students. Scientists of the Institute deliver lectures in the National University of Uzbekistan, Tashkent State Pedagogical University, Tashkent State University of Arts, Tashkent State University of Economics, and give physics, mathematics and chemistry lessons in the lyceum classes of the school 286 of the Ulugbek village. The Small University organized to improve qualification of the young scientists continues its activities. The Institute computer center with e-mail and Internet services, Uzbekistan INIS Center and the Institute scientific technical library in cooperation create an united information complex to provide both scientists of the Institute and bachelor and masters and PhD students of the Tashkent Higher Education Institutions, as well as researches from the other scientific organization of the Republic the opportunity to access the INIS database, Internet and library information. INIS Database on CD-ROM is available on the institute's local network. IRBIS software is used for the automation of the library system

  1. KASAM project for detailed study of the decision making process and basis for decisions in the nuclear waste area

    International Nuclear Information System (INIS)

    Hedberg, Bjoern

    2008-01-01

    The idea of the transparency programme is that it should increase the transparency, and thereby the quality, of the decision process and the document basis for the up coming decisions related to the SKB (Swedish Nuclear Fuel and Waste Management Company) license applications for a final repository for high level nuclear waste and an encapsulation plant for spent nuclear fuel. KASAM (Swedish National Council for Nuclear Waste) was in charge of the transparency program. The pre-study proposes that KASAM uses the RISCOM-model to support the transparency programme. During the pre-study a number of stakeholders were approached to give their views about the format and contents of the transparency programme and a large number of new issues were raised that could be included in transparency creating activities. Among these issues we got for instance: the role of responsible authorities, on what basis for site selection? or socio-economic issues or critical assumptions in the safety assessment or safety philosophy. Recurrent elements in the transparency programme would then be: -) a clear description of the background for the issue being addressed, -) knowledge building activities, and -) a hearing where the KASAM committee members and staff meet the stakeholders to discuss the issue

  2. Information on the activity of the Atomehnergo permanent commettee of CMEA in the area of peaceful use of nuclear energy

    International Nuclear Information System (INIS)

    Malek, Z.

    1984-01-01

    Activity of the CMEA permanent committee on the peaceful use of nuclear energy is briefly outlines. It is pointed out, that data, presented to the conferences and consultations of the Committee, can be used as numerical, when constructing data retrieval systems

  3. Persistent pre-seismic signature detected by means of Na-K-Mg geothermometry records in a saline spring of Vrancea area (Romania

    Directory of Open Access Journals (Sweden)

    H. Mitrofan

    2010-02-01

    Full Text Available A six year-long hydrochemical monitoring operation was conducted in Vrancea seismic zone (Romania, addressing a saline spring that proved to be suitable for Na-K-Mg geothermometry diagnosis. During the considered time-interval (2003–2009, only one important earthquake (mb=5.8 occurred in Vrancea region, this circumstance providing an unambiguous reference-moment between pre-seismic and post-seismic periods. On occurrence of that earthquake, an anomalous fluctuation of the Na-K temperature was detected – a result largely similar to previous ones recorded worldwide (California, southwest Egypt, northeast India. Yet such fluctuations may not necessarily be induced by earthquake-associated processes: they can occur also "routinely", possibly reflecting some environmental, meteorologically-induced "noise". It was therefore important to examine whether the variations observed in the data values could be plausibly related to a seismogenesis process. By additionally investigating (in a "scattterplot" diagram the correlation between the Na-K temperatures and the values of a so-called "maturity index", a specific pattern emerged, with pre-seismic data-points plotting in a distinct domain of the diagram; moreover, those data-points appeared to describe a "drift away" pathway with respect to the remaining data-points "cluster", recorded during the subsequent 4 years of post-seismic monitoring. The "drift away" pattern persistently evolved for at least 18 months, ending just before the mb=5.8 earthquake and consequently suggesting the existence of some kind of long-term precursory phenomenon.

  4. Decontamination work in the area surrounding Fukushima Dai-ichi Nuclear Power Plant: another occupational health challenge of the nuclear disaster.

    Science.gov (United States)

    Wada, Koji; Yoshikawa, Toru; Murata, Masaru

    2012-01-01

    This article describes occupational health measures for workers involved in decontamination of radioactive material discharged around Fukushima Dai-ichi Nuclear Power Plant after the explosions in 2011. Decontamination is performed by removing radioactive particles (mainly cesium) from surfaces of soil, grass and trees, and buildings. Measurement of radiation doses is necessary to reduce exposure, and to determine whether workers can work below dose limits. Protective equipment for decontamination is determined based on the concentration of radiation in contaminated soil and the exposure to dust. Health examinations by physicians are mandated for decontamination workers upon hiring and every 6 months. While there is no possibility of acute radiation injury from decontamination, workers may be anxious about the unclear effects of chronic low level radiation exposure on health. Measures to protect the decontamination workers are the top priority.

  5. Hand calculation of safe separation distances between natural gas pipelines and boilers and nuclear facilities in the Hanford site 300 Area

    International Nuclear Information System (INIS)

    Daling, P.M.; Graham, T.M.

    1999-01-01

    The US Department of Energy has undertaken a project to reduce energy expenditures and improve energy system reliability in the 300 Area of the Hanford Site near Richland, Washington. This project replaced the centralized heating system with heating units for individual buildings or groups of buildings, constructed a new natural-gas distribution system to provide a fuel source for many of these units, and constructed a central control building to operate and maintain the system. The individual heating units include steam boilers that are housed in individual annex buildings located in the vicinity of a number of nuclear facilities operated by the Pacific Northwest National Laboratory (PNNL). The described analysis develops the basis for siting the package boilers and natural-gas distribution system used to supply steam to PNNL's 300 Area nuclear facilities. Minimum separation distances that would eliminate or reduce the risks of accidental dispersal of radioactive and hazardous materials in nearby nuclear facilities were calculated based on the effects of four potential fire and explosion (detonation) scenarios involving the boiler and natural-gas distribution system. These minimum separation distances were used to support siting decisions for the boilers and natural-gas pipelines

  6. Cellular proliferation in the urorectal septation complex of the human embryo at Carnegie stages 13-18: a nuclear area-based morphometric analysis.

    Science.gov (United States)

    Nebot-Cegarra, Josep; Fàbregas, Pere Jordi; Sánchez-Pérez, Inma

    2005-10-01

    In order to analyse the patterns of cellular proliferation both in the mesenchyme of the urorectal septum (URS) and in the adjacent territories (posterior urogenital mesenchyme, anterior intestinal mesenchyme and cloacal folds mesenchyme), as well as their contribution to the process of cloacal division, a computer-assisted method was used to obtain the nuclear area of 3874 mesenchymal cells from camera lucida drawings of nuclear contours of selected sections of human embryos [Carnegie stages (CSs) 13-18]. Based on changes in the size of the nucleus during the cellular cycle, we considered proliferating cells in each territory to be those with a nuclear area over the 75th percentile. The URS showed increasing cell proliferation, with proliferation patterns that coincided closely with cloacal folds mesenchyme, and with less overall proliferation than urogenital and intestinal mesenchymes. Furthermore, at CS 18, we observed the beginning of the rupture in the cloacal membrane; however, no fusion has been demonstrated either between the URS and the cloacal membrane or between the cloacal folds. The results suggest that cloacal division depends on a morphogenetic complex where the URS adjacent territories could determine septal displacement at the time that their mesenchymes could be partially incorporated within the proliferating URS.

  7. An aerial radiological survey of the Point Beach Nuclear Power Plant and surrounding area. Final report, October 19, 1996 - October 24, 1996

    International Nuclear Information System (INIS)

    Feimster, E.L.

    1997-12-01

    Radioactivity surrounding the Point Beach Nuclear Power Plant was measured using aerial radiological surveying techniques. The purpose of this survey was to document exposure rates and identify radiation sources within the survey area. The surveyed area included a 25-square-mile (65-square-kilometer) area, which encompasses the plant site. Data were acquired using an airborne detection system that employed sodium iodide, thallium-activated detectors. Exposure rates at 1 meter above ground level were computed from these data and plotted on a U.S. Geological Survey topographic map of the survey area. Several ground-based exposure-rate measurements were made for comparison with the aerial survey results. Exposure rates in areas surrounding the plant site varied (a) from 10-14 microroentgens per hour (μR/h) in cultivated fields, (b) from 8-10 μR/h in adjacent areas and along roadways, and (c) below 6 μR/h over waterways and wetland areas. Man-made radiation (102-202 μR/h) was found at the plant site; cobalt-60 was the primary source of activity found at the Point Beach site. No other detectable sources of man-made radioactivity were found. The exposure rates measured during this survey agreed well with those measured during the 1970 survey even though the survey methodology and parameters were significantly different

  8. The use of nuclear prospecting measurements for characterizing the radioactive status of Al-Bayyarat and Sabkhet Mouh areas, southern Palmyrides, Syria

    International Nuclear Information System (INIS)

    Asfahani, J.; Al-Hent, R.; Aissa, M.

    2014-01-01

    Al-Bayyarat and Sabkhet Mouh areas in southern Palmyride have been radioactively characterized by using different nuclear prospecting measurements. Those measurements include the application of airborne, carborne spectrometric gamma, radon emanation and borehole techniques. The merging of airborne, carborne spectrometric gamma data enables to establish the normalized eU, eTh, and K% maps in the study area. Radon emanation and spectrometric gamma measurements have been applied only in Al- Bayyarat area, where radioactive anomalous zone has been observed. The radioactive characteristics of the study area has been explained through studying and analyzing a profile of 30 Km long, where a plausible geo-radioactive model has been proposed for the uranium leaching and its transport. - Highlights: • Determine the radioactive characteristics of the study area. • Explain the radioactive anomaly observed in Al-Bayarat area. • Analysis of a profile of 30 Km and propose a plausible geo-radioactive model. • Discus the radioactive disequilibrium occurred in the study area

  9. Geology and hydrogeology of the proposed nuclear waste repository at Yucca Mountain, Nevada and the surrounding area

    International Nuclear Information System (INIS)

    Mattson, S.R.; Broxton, D.E.; Buono, A.; Crowe, B.M.; Orkild, P.P.

    1989-01-01

    In late 1987 Congress issued an amendment to the Nuclear Waste Policy Act of 1982 which directed the characterization of Yucca Mountain, Nevada as the only remaining potential site for the Nation's first underground high-level radioactive waste repository. The evaluation of a potential underground repository is guided and regulated by policy established by the Department of Energy (DOE), Nuclear Regulatory Commission (NRC), Environmental Protection Agency (EPA), Department of Transportation (DOT), and the US Congress. The Yucca Mountain Project is the responsibility of the DOE. The purpose of this field trip is to introduce the present state of geologic and hydrologic knowledge concerning this site. This report describes the field trip. 108 refs., 6 figs., 1 tab

  10. Development of methodologies used in the areas of safeguards and nuclear forensics based on LA-HR-ICP-MS technique

    International Nuclear Information System (INIS)

    Marin, Rafael Coelho

    2013-01-01

    Environmental sampling performed by means of swipe samples is a methodology frequently employed by International Atomic Energy Agency (IAEA) to verify if the signatory States of the Safeguards Agreements are conducing unauthorized activities. Swipe samples analysis is complementary to the Safeguards ordinary procedures used to verify the information given by the States. In this work it was described a methodology intending to strengthen the nuclear safeguards and nuclear forensics procedures. The proposal is to study and evaluate the laser ablation high resolution inductively coupled plasma mass spectrometry (LA-HR-ICP-MS) technique as an alternative to analyze the real-life swipe samples. The precision achieved through the standard (CRM - 125A) measurements, represented by the relative standard deviation (RSD), was respectively 1.3 %, 0.2 % e 7.6 % for the 234 U/ 238 U, 235 U/ 238 U e 236 U/ 238 U isotopes ratios. The percent uncertainties (u %), which covers the RSD, ranged from 3.5 % to 29.8 % to the 235 U/ 238 U measurements and from 16.6 % to 42.9 % to the 234 U/ 238 U isotope ratio. These results were compatible with former studies performed by the LA-HR-ICP-MS that analyzed real-life swipe samples collected at a nuclear facility. Swipe samples collected from several points of the nuclear facility presented enrichment level ranging from (2.3 ± 0.7) % (sample 3) to (17.3 ± 2.8) % (sample 18). They also allowed detecting different enrichment levels within the facility. (author)

  11. Overview of long-term observations of radioactivity in the area around Institute of nuclear physics of Uzbekistan Academy of Sciences

    International Nuclear Information System (INIS)

    Salikhbaev, U.S.; Yuldashev, B.S.; Radyuk, R.I.

    2006-01-01

    Full text: The radiation protection problem is mainly important with its relation with potential radioactivity threat to society and environment. Therefore, development of nuclear science in Uzbekistan since foundation of the Institute of Nuclear Physic (INP) is directly related to radiation protection of the personnel, population and environment. One of the major tasks highlighted in this report, importance of complex approach to the radiation protection and security, is worth of mentioning. Development of such an approach allows creation of a concept to predict the radiation situation and transition to radiation monitoring around the research nuclear centre. The aim of this complex approach to the solution of the radiation protection task is to find the methods for making predictions and managing the radiation situation around the nuclear centre. Complex approach to this research implies integration of theoretical and experimental activities. Theoretical studies involve primarily radiation prediction models. Experimental works are, on one hand, the data to approve the theoretical models, the obtained empirical parameters, and, on the other hand, information on the radiation situation for its forecasting. Lack of reliable information on the radioactivity level creates various rumours and is the major reason for radiophobia. The aim of this report is to present realistic information on the radioactivity level at the INP AS RU site and at the surrounding area, which is based on long-term measurements provided by the radiation protection department. In this work the following results of the research are presented: -total beta and gamma-activity of herbs and soil; - specific activity of waters (waste, underground, and surface); - activity of the air aerosols; - activity of the atmospheric precipitations; - background at the site of the INP, at the sanitary-protection area and observation area. What has been accomplished for these years? Firstly, the model for cobalt

  12. Nuclear structure

    International Nuclear Information System (INIS)

    Eastham, D.A.; Joy, T.

    1986-01-01

    The paper on 'nuclear structure' is the Appendix to the Daresbury (United Kingdom) Annual Report 1985/86, and contains the research work carried out at the Nuclear Structure Facility, Daresbury, within that period. During the year a total of 74 experiments were scheduled covering the main areas of activity including: nuclear collective motion, nuclei far from stability, and nuclear collisions. The Appendix contains brief reports on these experiments and associated theory. (U.K.)

  13. Imprezy biegowe na obszarach wiejskich w Polsce a poziom uczestnictwa Polaków w kulturze fizycznej = Running events in rural areas in Poland and the level of citizen participation in physical culture

    Directory of Open Access Journals (Sweden)

    Joanna Poczta

    2016-12-01

      STRESZCZENIE   Celem artykułu jest wykazanie potencjału obszarów wiejskich do aktywności sportowo-rekreacyjnej w Polsce. Zagospodarowanie tego potencjału może natomiast wypełnić niszę i mieć utylitarny wpływ na kształtowanie postaw wobec zdrowia i kultury fizycznej jej uczestników, a także mieszkańców obszarów recepcji turystycznej. W artykule wskazano, że polityka zdrowotna w coraz większym zakresie koncentruje się na promowaniu prozdrowotnego modelu zachowań, który wspiera osiąganie dobrego stanu zdrowia ogółu populacji oraz, że interwencje z zakresu promocji zdrowia poprzez aktywność fizyczną są coraz częściej ukierunkowywane na zmiany w stylu życia i dotyczą również czasu wolnego                        i turystyki, w ostatnim czasie coraz częściej także na obszarach wiejskich w kraju.   Słowa kluczowe: wydarzenia sportowe, imprezy biegowe, turystyka sportowa, obszary wiejskie, promocja zdrowia, kultura fizyczna.       ABSTRACT   The aim of this article is to demonstrate the potential of rural areas for sports and recreation activities in Poland. Development of this potential may, however, fill a niche and have a utilitarian influence on attitudes towards health and physical culture of the participants, as well as residents of reception areas. The article indicated that health policy increasingly focused on promoting healthy behavior model, which supports the achievement of a good state of health of the general population and that interventions in health promotion through physical activity are increasingly being channeled to changes in lifestyle and also concern leisure and tourism, recently increasingly also in rural areas in the country.   Key words: sporting events, running events, sports tourism, rural areas, health promotion, physical culture.

  14. Analysis of gamma ray intensity on the S/C vent pipes area in the unit 2 reactor building of the Fukushima Daiichi Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Jai Wan; Choi, Young Soo; Jeong, Kyung Min [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The robot is equipped with cameras, a dosimeter, and 2 DOF (degree of freedom) manipulation arms. It loads a small vehicle equipped with a camera that can access and inspect narrow areas. TEPCO is using the four-legged walking robot to inspect the suppression chamber (S/C) area of the unit 2 reactor building basement in the Fukushima Daiichi Nuclear Power Plant. The robot carried out 6 missions for about four months, from 11 December, 2012 to 15 March, 2013, where it examined an evidence of a leakage of radioactivity contaminated water in the S/C area of unit 2 reactor building. When a camera's signal processing unit, which is consist of ASIC and FPGA devices manufactured by a CMOS fabrication process, is exposed to a higher dose rate gamma ray, the speckle distribution in the camera image increase more. From the inspection videos, released by TEPCO, of the underground 8 vent pipes in the unit 2 reactor building, we analyzed the speckle distribution from the high dose-rate gamma rays. Based on the distribution of the speckle, we attempted to characterize the vent pipe with much radioactivity contaminated materials among the eight vent pipes connected to the PCV. The numbers of speckles viewed in the image of a CCD (or CMOS) camera are related to an intensity of the gamma ray energy emitted by a nuclear fission reaction from radioactivity materials. The numbers of speckles generated by gamma ray irradiation in the camera image are calculated by an image processing technique. Therefore, calculating the speckles counts, we can determine the vent pipe with relatively most radioactivity-contaminated materials among the other vent pipes. From the comparison of speckles counts calculated in the inspection image of the vent pipe with the speckles counts extracted by gamma ray irradiation experiment of the same small vehicle camera model loaded with the four-legged walking robot, we can qualitatively estimate the gamma ray dose-rate in the S/C vent pipe area of the

  15. Summary of Survey and Workshop Results on Areas of Research in Human Factors for the Design and Operation of New Nuclear Plant Technology - Final Report

    International Nuclear Information System (INIS)

    Persensky, Julius J.; Joe, Jeffrey; Richards, Robert E.; Barnes, Valerie; Gonzalez, Michelle

    2012-01-01

    The nuclear community is currently at a stage where existing reactor control stations are undergoing various forms of modernization, new reactors are being built in many countries with computer-based control rooms, and advanced reactors are being designed through international cooperation to support power generation for decades to come. With the introduction of advanced plants, we will see new reactor and system designs, new tools to support plant personnel, and changes to nuclear power plant (NPP) staffing configurations. The concepts of operation and maintenance for this new generation of plants are likely to be quite different from those employed in today's plants. It is important that the potential impact of these developments is evaluated and understood by prospective operators and regulators responsible for determining the acceptability of new designs to support human performance in maintaining plant safety. The introduction of new technology is viewed as having promise for improving the safe and efficient operation of NPPs. To ensure the appropriate application of technology to support human performance and plant safety, it is important to evaluate the technological advances in terms of both potential negative and positive effects. Research described in this paper can provide the technical basis to help ensure that the benefits of new technology are realized and that the potential negative effects are minimized. The impetus for the current effort grew out of a Nuclear Energy Agency, Committee on the Safety of Nuclear Installations, Working Group on Human and Organizational Factors, Technical Opinion Paper (TOP) titled, 'Research on Human Factors in New Nuclear Plant Technology' [NEA/CSNI/R(2009)7], which identified eight broad topic areas that warrant further research: 1. Operating Experience (OpEx) from New and Modernized Plants. 2. Evolving Concepts for the Operation of Nuclear Power Plants. 3. The Role of Automation and Personnel: New Concepts of Teamwork

  16. Agricultura orgânica em áreas urbanas e periurbanas com base na agroecologia Challenges of organic agriculture in urban and suburban areas

    Directory of Open Access Journals (Sweden)

    Adriana Maria de Aquino

    2007-06-01

    Full Text Available A agricultura orgânica com base na agroecologia é o mote tecnológico adequado à realidade dos agroecossistemas urbanos. Este artigo ressalta a necessidade de se desenvolver tecnologias e insumos específicos. A partir de experiências com agricultura urbana em diferentes países em desenvolvimento, evidencia-se a necessidade de se buscar capacidades locais e apoio do poder público, especialmente nas iniciativas da sociedade organizada e mobilizada para a produção agrícola urbana.This article presents organic agriculture, based on agroecology, as the appropriate technology for the urban agro-ecosystem. It also points out the need for appropriate technologies and amendments development. Looking at experiences with urban agriculture in development countries, it shows the need for local capacity development and a search for the public sector support, specially of organized groups mobilized for urban agriculture production.

  17. The use of CH3OH additive to NaOH for etching alpha particle tracks in a CR-39 plastic nuclear track detector

    International Nuclear Information System (INIS)

    Ashry, A.H.; Abdalla, A.M.; Rammah, Y.S.; Eisa, M.; Ashraf, O.

    2014-01-01

    Fast detection of alpha particles in CR-39 detectors was investigated using a new chemical etchant. 252 Cf and 241 Am sources were used for irradiating samples of CR-39 SSNTDs with fission fragments and alpha particles in air at normal temperature and pressure. A series of experimental chemical etching are carried out using new etching solution (8 ml of 10N NaOH+1 ml CH 3 OH) at 60 °C to detect alpha particle in short time in CR-39 detectors. Suitable analyzing software has been used to analyze experimental data. From fission and alpha track diameters, the value of bulk etching rate is equal to 2.73 μm/h. Both the sensitivity and etching efficiency were found to vary with the amount of methanol in the etching solution. Pure NaOH was used as a control to compare with the result from etching in NaOH with different concentrations of CH 3 OH. The etching efficiency is determined and compared with conventional aqueous solution of 6.25N NaOH at 70 °C for etching time equals 5 h. In this study, the obtained etching efficiency shows a considerable agreement with the previous work. - Highlights: • The value of bulk etching rate is equal to 2.73 μm/h. • Fast detection of alpha particles in CR-39 detectors. • Samples of CR-39 have been irradiated with fission fragments. • Etching efficiency was determined

  18. FAO/IAEA international conference on area-wide control of insect pests: Integrating the sterile insect and related nuclear and other techniques. Book of extended synopses

    International Nuclear Information System (INIS)

    2005-01-01

    The successful implementation of area-wide pest control programmes integrating the use of sterile insects with other control technologies against a number of key veterinary, medical and plant insect pests, such as various fruit flies, moths, screwworms, and tsetse species, clearly demonstrates a peaceful application of nuclear technology. Over the last 40 years, FAO and IAEA have played, and they will continue to play, a critical role in supporting their Member States in the development and application of these environment-friendly pest control methods. The concept of area-wide integrated pest management, in which the total population of a pest in an area or region is targeted, is central to the effective application of the Sterile Insect Technique (SIT) and is increasingly being considered for related genetic, biological and other pest control technologies. Insect movement, occurring sometimes over long distances, is generally underestimated. As a consequence, most conventional pest control can be described as localized, un-coordinated action against segments of a pest population, resulting very often in an unsustainable spiral of insecticide application and eventual resistance. However, an area-wide integrated approach adopts a preventive rather than a reactive tactic, whereby all individuals of the pest population are targeted, requiring fewer inputs and resulting in more cost effective and sustainable control. In June 1998 FAO and IAEA sponsored the First International Conference on Area-Wide Control of Insect Pests Integrating the Sterile Insect and Related Nuclear and other Techniques in Penang, Malaysia with the participation of almost 300 participants from 63 Member States and 5 international organizations. This Conference greatly increased awareness concerning the area-wide approach for insect pest control programmes. Since then, many new technical innovations have been introduced and a better regulatory framework is being developed for integrating SIT

  19. FAO/IAEA international conference on area-wide control of insect pests: Integrating the sterile insect and related nuclear and other techniques. Book of extended synopses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The successful implementation of area-wide pest control programmes integrating the use of sterile insects with other control technologies against a number of key veterinary, medical and plant insect pests, such as various fruit flies, moths, screwworms, and tsetse species, clearly demonstrates a peaceful application of nuclear technology. Over the last 40 years, FAO and IAEA have played, and they will continue to play, a critical role in supporting their Member States in the development and application of these environment-friendly pest control methods. The concept of area-wide integrated pest management, in which the total population of a pest in an area or region is targeted, is central to the effective application of the Sterile Insect Technique (SIT) and is increasingly being considered for related genetic, biological and other pest control technologies. Insect movement, occurring sometimes over long distances, is generally underestimated. As a consequence, most conventional pest control can be described as localized, un-coordinated action against segments of a pest population, resulting very often in an unsustainable spiral of insecticide application and eventual resistance. However, an area-wide integrated approach adopts a preventive rather than a reactive tactic, whereby all individuals of the pest population are targeted, requiring fewer inputs and resulting in more cost effective and sustainable control. In June 1998 FAO and IAEA sponsored the First International Conference on Area-Wide Control of Insect Pests Integrating the Sterile Insect and Related Nuclear and other Techniques in Penang, Malaysia with the participation of almost 300 participants from 63 Member States and 5 international organizations. This Conference greatly increased awareness concerning the area-wide approach for insect pest control programmes. Since then, many new technical innovations have been introduced and a better regulatory framework is being developed for integrating SIT

  20. Development of a multi-criteria tool to support decision-making process on decontamination of urban areas after a nuclear accident

    Energy Technology Data Exchange (ETDEWEB)

    Rochedo, Elaine R.R.; Luca, Christiano de [Instituto Militar de Engenharia, Pc. Gen. Tiburcio, 80, Praia Vermelha, Rio de Janeiro, 22290-270 RJ (Brazil); Silva, Diogo N.G. [Universidade Federal do Rio de Janeiro, Instituto de Biofisica Carlos Chagas Filho, Rio de Janeiro 21941-902 RJ (Brazil); Wasserman, Maria Angelica V. [Instituto de Engenharia Nuclear, Cidade Universitaria, Ilha do Fundao, 21941-906, Rio de Janeiro RJ (Brazil)

    2014-07-01

    This work describes the main efforts to derive criteria for classifying technical aspects related to decontamination procedures to feed a multi-criteria tool to support decisions on remediation of urban areas after nuclear accidents. After listing procedures already tested or used in previous accident, technical aspects to be considered were derived. The relevance of each aspect was determined based on questionnaires answered by experts with experience on remediation after an accident. The questionnaire included 12 aspects and for each of them one or more technical criteria where developed to allow the classification of remediation procedures for urban areas. The criteria described in this work relate to the effects of each procedure on doses to the public, doses to remediation workers, waste generation and infrastructure needed. The aim of this project was to increase public concerns by turning the decision making process more reliable and transparent. In this work, the list of criteria and associated values are described. This list is now being included in a previously developed dose assessment computer program to allow the optimization of actions to be used considering all justifiable procedures based on the current experience on dealing with urban areas contamination after a nuclear or radiological accident. (authors)

  1. Indicator value of certain aquatic organisms for radioactive substances in the sea areas off the Loviisa and Ilkiluoto nuclear power plants (Finland)[Radioecology

    Energy Technology Data Exchange (ETDEWEB)

    Ilus, E.; Klemola, S.; Ikaeheimonen, T.K.; Vartti, V.P.; Mattila, J. [STUK - radiation and Nuclear Safety Authority, Helsinki (Finland)

    2006-04-15

    The results of the marine radioecology studies carried out in 2000-2001 in the sea areas off the Loviisa and Olkiluoto Nuclear Power Plants (South and West coast of Finland) are reported. Extensive regular monitoring programmes of environmental radioactivity have been carried out already for about 30 years in these areas. The aim of the present study was to compare the indicator value of the various members of the aquatic ecosystem with respect to environmental monitoring. Samples were taken from 27 species including phytoplankton (9 samples), zooplankton (9 samples), periphyton (12 samples), macroalgae and vascular plants (16 samples), benthic animals (8 samples), fish (20 samples) and birds (6). Special attention was paid to different tissues and organs of fish and birds, such as flesh, liver, entrails, bones, milt, spawn, eggs, egg shells etc. (in total 64 samples), because there has been a lot of debate among the opponents of nuclear power in the course of time about the role these objects in the environmental monitoring of the power plants. The samples were taken from relatively small areas both in Loviisa and Olkiluoto, which makes the results well comparable inside each of the sites. (au)

  2. Indicator value of certain aquatic organisms for radioactive substances in the sea areas off the Loviisa and Olkiluoto nuclear power plants (Finland)[Radioecology

    Energy Technology Data Exchange (ETDEWEB)

    Ilus, E.; Klemola, S.; Ikaeheimonen, T.K.; Vartti, V.P.; Mattila, J. [STUK - radiation and Nuclear Safety Authority, Helsinki (Finland)

    2006-04-15

    The results of the marine radioecology studies carried out in 2000-2001 in the sea areas off the Loviisa and Olkiluoto Nuclear Power Plants (South and West coast of Finland) are reported. Extensive regular monitoring programmes of environmental radioactivity have been carried out already for about 30 years in these areas. The aim of the present study was to compare the indicator value of the various members of the aquatic ecosystem with respect to environmental monitoring. Samples were taken from 27 species including phytoplankton (9 samples), zooplankton (9 samples), periphyton (12 samples), macroalgae and vascular plants (16 samples), benthic animals (8 samples), fish (20 samples) and birds (6). Special attention was paid to different tissues and organs of fish and birds, such as flesh, liver, entrails, bones, milt, spawn, eggs, egg shells etc. (in total 64 samples), because there has been a lot of debate among the opponents of nuclear power in the course of time about the role these objects in the environmental monitoring of the power plants. The samples were taken from relatively small areas both in Loviisa and Olkiluoto, which makes the results well comparable inside each of the sites. (au)

  3. Real-time high-resolution X-ray imaging and nuclear magnetic resonance study of the hydration of pure and Na-doped C3A in the presence of sulfates

    KAUST Repository

    Kirchheim, A. P.

    2011-02-21

    This study details the differences in real-time hydration between pure tricalcium aluminate (cubic C3A or 3CaO·Al2O 3) and Na-doped tricalcium aluminate (orthorhombic C3A or Na2Ca8Al6O18), in aqueous solutions containing sulfate ions. Pure phases were synthesized in the laboratory to develop an independent benchmark for the reactions, meaning that their reactions during hydration in a simulated early age cement pore solution (saturated with respect to gypsum and lime) were able to be isolated. Because the rate of this reaction is extremely rapid, most microscopy methods are not adequate to study the early phases of the reactions in the early stages. Here, a high-resolution full-field soft X-ray imaging technique operating in the X-ray water window, combined with solution analysis by 27Al nuclear magnetic resonance (NMR) spectroscopy, was used to capture information regarding the mechanism of C3A hydration during the early stages. There are differences in the hydration mechanism between the two types of C3A, which are also dependent on the concentration of sulfate ions in the solution. The reactions with cubic C3A (pure) seem to be more influenced by higher concentrations of sulfate ions, forming smaller ettringite needles at a slower pace than the orthorhombic C3A (Na-doped) sample. The rate of release of aluminate species into the solution phase is also accelerated by Na doping. © 2011 American Chemical Society.

  4. Okoljevarstvena problematika zaseznih zelenjavnih vrtov na vodovarstvenih območjih Ljubljane = Environmental protection: Private v