Accidental safety analysis methodology development in decommission of the nuclear facility

Energy Technology Data Exchange (ETDEWEB)

Park, G. H.; Hwang, J. H.; Jae, M. S.; Seong, J. H.; Shin, S. H.; Cheong, S. J.; Pae, J. H.; Ang, G. R.; Lee, J. U. [Seoul National Univ., Seoul (Korea, Republic of)

2002-03-15

Decontamination and Decommissioning (D and D) of a nuclear reactor cost about 20% of construction expense and production of nuclear wastes during decommissioning makes environmental issues. Decommissioning of a nuclear reactor in Korea is in a just beginning stage, lacking clear standards and regulations for decommissioning. This work accident safety analysis in decommissioning of the nuclear facility can be a solid ground for the standards and regulations. For source term analysis for Kori-1 reactor vessel, MCNP/ORIGEN calculation methodology was applied. The activity of each important nuclide in the vessel was estimated at a time after 2008, the year Kori-1 plant is supposed to be decommissioned. And a methodology for risk analysis assessment in decommissioning was developed.

Nuclear power plant system environmental design and decision methodology

International Nuclear Information System (INIS)

Zendehrouh, Z.; Shinozuka, M.; Schauer, F.P.

1975-01-01

The methodology described is concerned with a system reliability analysis by which the correlation among the level of design for the environmental and natural phenomena (earthquake, flood, tornado, etc.), reasonable practical measure of safety (such as conventional safety factor), and damage (radioactivity release) probability are established. In fact, the methodology indicates how the risk of environmental and natural hazard is combined with a specific design in order to evaluate damage probability associated with the design. This leads to the optimum design decision when combined further with the cost considerations involving the radioactivity release. This fundamental approach is essential in the design of nuclear plant structures, because, unlike the convential structures, the architectural considerations and structural analysis requirements alone cannot, by themselves, result in a balanced design in the framework of social requirements. The proposed methodology incorporates the different methods of environmental load determinations with their respective probabilistic formulations as well as detailed and advanced multi-discipline (structural, mechanical, soil, nuclear physics, biology, etc.) theoretical and empirical analysis including the effect of probabilistic nature of design variables, to establish a sound and reasonable design decision model for nuclear power plants. The information required for the analysis is also described and the areas for which further research is desirable are pointed out. Furthermore, the proposed methodology can very well be utilized to determine the requirements of standardized plants to facilitate the speed of their design and review process

An integrated methodology to evaluate a spent nuclear fuel storage system

International Nuclear Information System (INIS)

Yoon, Jeong Hyoun

2008-02-01

This study introduced a methodology that can be applied for development of a dry storage system for spent nuclear fuels. It consisted of several design activities that includes development of a simplified program to analyze the amount of spent nuclear fuels from reflecting the practical situation in spent nuclear fuel management and a simplified program to evaluate the cost of 4 types of representing storage system to choose the most competitive option considering economic factor. As verification of the implementation of the reference module to practical purpose, a simplified thermal analysis code was suggested that can see fulfillment of limitation of temperature in long term storage and oxidation analysis. From the thermal related results, the reference module can accommodate full range of PHWR spent nuclear fuels and significant portion of PWR ones too. From the results, the reference storage system can be concluded that has fulfilled the important requirements in terms of long term integrity and radiological safety. Also for the purpose of solving scattered radiation along with deep penetration problems in cooling storage system, small but efficient design alternation was suggested together with its efficiency that can reduce scattered radiation by 1/3 from the original design. Along with the countermeasure for the shielding problem, in consideration of PWR spent nuclear fuels, simplified criticality analysis methodology retaining conservativeness was proposed. The results show the reference module is efficient low enrichment PWR spent nuclear fuel and even relatively high enrichment fuels too if burnup credit is taken. As conclusive remark, the methodology is simple but efficient to plan a concept design of convective cooling type of spent nuclear fuels storage. It can be also concluded that the methodology derived in this study and the reference module has feasibility in practical implementation to mitigate the current complex situation in spent fuel

A review on nuclear forensic methodology for analysis of nuclear material of unknown origin

International Nuclear Information System (INIS)

Deshmukh, A.V.; Raghav, N.K.; Fatangare, N.M.; Jagtap, S.S.

2014-01-01

With the growing use of nuclear power and threat from illegal nuclear smuggling nuclear forensic provides an aid to the law enforcement to trace back modus operandi of such threats. Extensive nuclear proliferation, race among countries to acquire nuclear capability and global terrorism scenario has mandated Nuclear Forensic Science technology to tackle nuclear threats. Gamma spectrometry, alpha spectrometry, thermal ionization mass spectrometry, inductively coupled plasma mass spectrometry are employed for characterization and relative isotopic composition determinant of Nuclear material and techniques like SEM transmission electron TEM, FT-IR, GC-MS, Electrophoretic technique are used to characterize the contaminated materials in order to deceive investigative agencies. The present paper provide systematic forensic methodology for nuclear and radioactive materials encountered at any crime scene due to any accidental discharges or military activities. (author)

Methodologies for evaluating the proliferation resistance of nuclear fuel cycles

International Nuclear Information System (INIS)

Shiotani, Hiroki; Hori, Kei-ichiro; Takeda, Hiroshi

2001-01-01

The Japan Nuclear Cycle Development Institute (JNC) believes that the development of future nuclear fuel cycle technology should be conducted with careful consideration given to non-proliferation. JNC is studying methodologies for evaluating proliferation resistance of nuclear fuel cycle technologies. However, it is difficult to establish the methodology for evaluating proliferation resistance since the results greatly depend on the assumption for the evaluation and the surrounding conditions. This study grouped factors of proliferation resistance into categories through reviewing past studies and studied the relationships between the factors. Then, this study tried to find vulnerable nuclear material (plutonium) in some FBR fuel cycles from the proliferation perspective, and calculated the time it takes to convert the materials from various nuclear fuel cycles into pure plutonium metal under some assumptions. The result showed that it would take a long time to convert the nuclear materials from the FBR fuel cycles without plutonium separation. While it is a preliminary attempt to evaluate a technical factor of proliferation resistance as the basis of the institutional proliferation resistance, the JNC hopes that it will contribute to future discussions in this area. (author)

Nuclear relevant installations licensing methodology in the Argentine Republic

International Nuclear Information System (INIS)

Paganini, C.E.

1986-01-01

A review of the requeriments of the Nuclear Installations Advisory Committee on Licensing (CALIN) from the nuclear security point of view, is presented. The methodology applied by the CALIN for the licensing in the Argentine Republic is included as well as codes, standards of applications and the interaction between the licensing Authority and the Responsible Entity during the whole process. Finally, the Atucha II nuclear power plant's licensing, in construction at present, is explained and the standard, of the licensing schedule, is presented graphically. (author) [es

Methodology and preliminary models for analyzing nuclear-safeguards decisions

International Nuclear Information System (INIS)

Judd, B.R.; Weissenberger, S.

1978-11-01

This report describes a general analytical tool designed with Lawrence Livermore Laboratory to assist the Nuclear Regulatory Commission in making nuclear safeguards decisions. The approach is based on decision analysis - a quantitative procedure for making decisions under uncertain conditions. The report: describes illustrative models that quantify the probability and consequences of diverted special nuclear material and the costs of safeguarding the material; demonstrates a methodology for using this information to set safeguards regulations (safeguards criteria); and summarizes insights gained in a very preliminary assessment of a hypothetical reprocessing plant

Methodologies for nuclear material accounting and control: challenges and expectations

International Nuclear Information System (INIS)

Ramakumar, K.L.

2007-01-01

Nuclear Material Accounting and Control (NUMAC) represents one of the most important and indispensable responsibilities of any nuclear installation. The emphasis is to ensure that the nuclear material being handled in the nuclear installation is properly accounted for with the expected accuracy and confidence levels. A number of analytical methods based on both destructive and non-destructive assay techniques are available at the disposal of the nuclear analytical scientists for this purpose and they have been enumerated extensively in literature. Instead of recounting the analytical methodologies available, an attempt has been made in this paper to highlight some of the challenges. (author)

Methodology for risk analysis of nuclear installations

International Nuclear Information System (INIS)

Vasconcelos, Vanderley de; Senne Junior, Murillo; Jordao, Elizabete

2002-01-01

Both the licensing standards for general uses in nuclear facilities and the specific ones require a risk assessment during their licensing processes. The risk assessment is carried out through the estimation of both probability of the occurrence of the accident, and their magnitudes. This is a complex task because the great deal of potential hazardous events that can occur in nuclear facilities difficult the statement of the accident scenarios. There are also many available techniques to identify the potential accidents, estimate their probabilities, and evaluate their magnitudes. In this paper is presented a new methodology that systematizes the risk assessment process, and orders the accomplishment of their several steps. (author)

Fire risk analysis for nuclear power plants: Methodological developments and applications

International Nuclear Information System (INIS)

Kazarians, M.; Apostolakis, G.; Siv, N.O.

1985-01-01

A methodology to quantify the risk from fires in nuclear power plants is described. This methodology combines engineering judgment, statistical evidence, fire phenomenology, and plant system analysis. It can be divided into two major parts: (1) fire scenario identification and quantification, and (2) analysis of the impact on plant safety. This article primarily concentrates on the first part. Statistical analysis of fire occurrence data is used to establish the likelihood of ignition. The temporal behaviors of the two competing phenomena, fire propagation and fire detection and suppression, are studied and their characteristic times are compared. Severity measures are used to further specialize the frequency of the fire scenario. The methodology is applied to a switchgear room of a nuclear power plant

An Integrated Safety Assessment Methodology for Generation IV Nuclear Systems

International Nuclear Information System (INIS)

Leahy, Timothy J.

2010-01-01

The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Early work of the RSWG focused on defining a safety philosophy founded on lessons learned from current and prior generations of nuclear technologies, and on identifying technology characteristics that may help achieve Generation IV safety goals. More recent RSWG work has focused on the definition of an integrated safety assessment methodology for evaluating the safety of Generation IV systems. The methodology, tentatively called ISAM, is an integrated 'toolkit' consisting of analytical techniques that are available and matched to appropriate stages of Generation IV system concept development. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time.

Methodologies for rapid evaluation of seismic demand levels in nuclear power plant structures

International Nuclear Information System (INIS)

Manrique, M.; Asfura, A.; Mukhim, G.

1990-01-01

A methodology for rapid assessment of both acceleration spectral peak and 'zero period acceleration' (ZPA) values for virtually any major structure in a nuclear power plant is presented. The methodology is based on spectral peak and ZPA amplification factors, developed from regression analyses of an analytical database. The developed amplification factors are applied to the plant's design ground spectrum to obtain amplified response parameters. A practical application of the methodology is presented. This paper also presents a methodology for calculating acceleration response spectrum curves at any number of desired damping ratios directly from a single known damping ratio spectrum. The methodology presented is particularly useful and directly applicable to older vintage nuclear power plant facilities (i.e. such as those affected by USI A-46). The methodology is based on principles of random vibration theory. The methodology has been implemented in a computer program (SPECGEN). SPECGEN results are compared with results obtained from time history analyses. (orig.)

Interaction between core analysis methodology and nuclear design: some PWR examples

International Nuclear Information System (INIS)

Rothleder, B.M.; Eich, W.J.

1982-01-01

The interaction between core analysis methodology and nuclear design is exemplified by PSEUDAX, a major improvement related to the Advanced Recycle methodology program (ARMP) computer code system, still undergoing development by the Electric Power Research Institute. The mechanism of this interaction is explored by relating several specific nulcear design changes to the demands placed by these changes on the ARMP system, and by examining the meeting of these demands, first within the standard ARMP methodology and then through augmentation of the standard methodology by development of PSEUDAX

Systems selection methodology for civil nuclear power applications

International Nuclear Information System (INIS)

Scarborough, J.

1988-01-01

A methodology for evaluation and selection of a preferred Advanced Small or Medium Power Reactor (SMPR) for commercial electric power generation is discussed, and an illustrative example is presented with five US Advanced SMPR power plants. The evaluation procedure was developed from a methodology for ranking small, advanced nuclear power plant designs under development by the US Department of Energy (DOE) and Department of Defense (DOD). The methodology involves establishing numerical probability distributions for each of fifteen evaluation criteria for each Advanced SMPR plant. A resultant single probability distribution with its associated numerical mean value is then developed for each Advanced SMPR plant by Monte Carlo sampling techniques in order that each plant may be ranked with an associated statement of certainty. The selection methodology is intended as a screening procedure for commercial offerings to preclude detailed technical and commercial assessments from being conducted for those offerings which do not meet the initial screening criteria

Systems selection methodology for civil nuclear power applications

International Nuclear Information System (INIS)

Scarborough, J.C.

1987-01-01

A methodology for evaluation and selection of a preferred Advanced Small or Medium Power Reactor (SMPR) for commercial electric power generation is discussed, and an illustrative example is presented with five U.S. Advanced SMPR power plants. The evaluation procedure was developed from a methodology for ranking small. advenced nuclear power plant designs under development by the U.S. Department of Energy (DOE) and Department of Defense (DOD). The methodology involves establishing numerical probability distributions for each of fifteen evaluation criteria for each Advanced SMPR plant. A resultant single probability distribution with its associated numerical mean value is then developed for each Advanced SMPR plant by Monte Carlo sampling techniques in order that each plant may be ranked with an associated statement of certainty. The selection methodology is intended as a screening procedure for commercial offerings to preclude detailed technical and commercial assessments from being conducted for those offerings which do not meet the initial screening criteria. (auhtor)

Systematic review of perceptive studies on nuclear risk; Revisao sistematica de estudos perceptivos sobre risco nuclear

Energy Technology Data Exchange (ETDEWEB)

Freitas, Mariana Gama de

2014-07-01

This present work contains the study of risk perception in different areas of interaction. For it was made an analysis using methodology previously recognized and tested: a systematic review in the search for better understanding of the perception of risk in the nuclear area. Through this study it was possible to understand the potential of the systematic review as a tool for information that encompass the perception of risk as a whole. Making it possible to trace parameters to find out why the world's people have an aversion to certain matters relating to nuclear energy. Considering that if you can understand what drives the people has disgust on nuclear area, it is probably possible to create alternatives to remedy this lack of information and knowledge about the area. Causing the population to realize the benefits that nuclear power brings to people. (author)

The development of a neuroscience-based methodology for the nuclear energy learning/teaching process

International Nuclear Information System (INIS)

Barabas, Roberta de C.; Sabundjian, Gaiane

2015-01-01

When compared to other energy sources such as fossil fuels, coal, oil, and gas, nuclear energy has perhaps the lowest impact on the environment. Moreover, nuclear energy has also benefited other fields such as medicine, pharmaceutical industry, and agriculture, among others. However, despite all benefits that result from the peaceful uses of nuclear energy, the theme is still addressed with prejudice. Education may be the starting point for public acceptance of nuclear energy as it provides pedagogical approaches, learning environments, and human resources, which are essential conditions for effective learning. So far nuclear energy educational researches have been conducted using only conventional assessment methods. The global educational scenario has demonstrated absence of neuroscience-based methods for the teaching of nuclear energy, and that may be an opportunity for developing new strategic teaching methods that will help demystifying the theme consequently improving public acceptance of this type of energy. This work aims to present the first step of a methodology in progress based on researches in neuroscience to be applied to Brazilian science teachers in order to contribute to an effective teaching/learning process. This research will use the Implicit Association Test (IAT) to verify implicit attitudes of science teachers concerning nuclear energy. Results will provide data for the next steps of the research. The literature has not reported a similar neuroscience-based methodology applied to the nuclear energy learning/teaching process; therefore, this has demonstrated to be an innovating methodology. The development of the methodology is in progress and the results will be presented in future works. (author)

The development of a neuroscience-based methodology for the nuclear energy learning/teaching process

Energy Technology Data Exchange (ETDEWEB)

Barabas, Roberta de C.; Sabundjian, Gaiane, E-mail: robertabarabas@usp.br, E-mail: gdjian@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

When compared to other energy sources such as fossil fuels, coal, oil, and gas, nuclear energy has perhaps the lowest impact on the environment. Moreover, nuclear energy has also benefited other fields such as medicine, pharmaceutical industry, and agriculture, among others. However, despite all benefits that result from the peaceful uses of nuclear energy, the theme is still addressed with prejudice. Education may be the starting point for public acceptance of nuclear energy as it provides pedagogical approaches, learning environments, and human resources, which are essential conditions for effective learning. So far nuclear energy educational researches have been conducted using only conventional assessment methods. The global educational scenario has demonstrated absence of neuroscience-based methods for the teaching of nuclear energy, and that may be an opportunity for developing new strategic teaching methods that will help demystifying the theme consequently improving public acceptance of this type of energy. This work aims to present the first step of a methodology in progress based on researches in neuroscience to be applied to Brazilian science teachers in order to contribute to an effective teaching/learning process. This research will use the Implicit Association Test (IAT) to verify implicit attitudes of science teachers concerning nuclear energy. Results will provide data for the next steps of the research. The literature has not reported a similar neuroscience-based methodology applied to the nuclear energy learning/teaching process; therefore, this has demonstrated to be an innovating methodology. The development of the methodology is in progress and the results will be presented in future works. (author)

Methodology and technology of decommissioning nuclear facilities

International Nuclear Information System (INIS)

1986-01-01

The decommissioning and decontamination of nuclear facilities is a topic of great interest to many Member States of the International Atomic Energy Agency (IAEA) because of the large number of older nuclear facilities which are or soon will be retired from service. In response to increased international interest in decommissioning and to the needs of Member States, the IAEA's activities in this area have increased during the past few years and will be enhanced considerably in the future. A long range programme using an integrated systems approach covering all the technical, regulatory and safety steps associated with the decommissioning of nuclear facilities is being developed. The database resulting from this work is required so that Member States can decommission their nuclear facilities in a safe time and cost effective manner and the IAEA can effectively respond to requests for assistance. The report is a review of the current state of the art of the methodology and technology of decommissioning nuclear facilities including remote systems technology. This is the first report in the IAEA's expanded programme and was of benefit in outlining future activities. Certain aspects of the work reviewed in this report, such as the recycling of radioactive materials from decommissioning, will be examined in depth in future reports. The information presented should be useful to those responsible for or interested in planning or implementing the decommissioning of nuclear facilities

Internal fire analysis screening methodology for the Salem Nuclear Generating Station

International Nuclear Information System (INIS)

Eide, S.; Bertucio, R.; Quilici, M.; Bearden, R.

1989-01-01

This paper reports on an internal fire analysis screening methodology that has been utilized for the Salem Nuclear Generating Station (SNGS) Probabilistic Risk Assessment (PRA). The methodology was first developed and applied in the Brunswick Steam Electric Plant (BSEP) PRA. The SNGS application includes several improvements and extensions to the original methodology. The SNGS approach differs significantly from traditional fire analysis methodologies by providing a much more detailed treatment of transient combustibles. This level of detail results in a model which is more usable for assisting in the management of fire risk at the plant

Methodology and preliminary models for analyzing nuclear safeguards decisions

International Nuclear Information System (INIS)

1978-11-01

This report describes a general analytical tool designed to assist the NRC in making nuclear safeguards decisions. The approach is based on decision analysis--a quantitative procedure for making decisions under uncertain conditions. The report: describes illustrative models that quantify the probability and consequences of diverted special nuclear material and the costs of safeguarding the material, demonstrates a methodology for using this information to set safeguards regulations (safeguards criteria), and summarizes insights gained in a very preliminary assessment of a hypothetical reprocessing plant

A study on the proliferation resistance evaluation methodology for nuclear energy system

International Nuclear Information System (INIS)

Kim, Min Su

2007-02-01

The framework of proliferation resistance evaluation methodology, based on attribute analysis and scenario analysis, for nuclear energy system is suggested in order to allow for the comprehensive assessment of proliferation resistance by addressing the intrinsic and extrinsic features of nuclear energy system. Proliferation resistance is viewed within the context of the success tree model of proliferator's diversion attempt and expressed by the value of top event probability of the success tree model. This study focused on the method that the value of top event is estimated. The methodology uses two different methods to quantify the likelihood of basic events constituting the top event. The likelihood of basic event success affected by intrinsic feature of nuclear energy system was assessed by using multi-attribute utility theory and likelihood of basic event related to the diversion detection measures was assessed by direct expert elicitation. The value of top event was calculated based on the intersection of probabilities of basic event success. Feasibility of the methodology was explored by applying it to selected reference nuclear energy systems. System-Integrated Modular Advanced Reactor (SMART) system and Light Water Reactor (LWR) were chosen as reference systems and the value proliferation resistance of SMART and LWR were evaluated. Characteristics of inherent features and hypothesized safeguards measures of both systems were identified and used as input data to evaluate proliferation resistance. The results and conclusions are applicable only within the context of subjectivity of this methodology

Methodology for evaluating port vulnerability to nuclear smuggling

International Nuclear Information System (INIS)

Ek, D.; Gronager, J.R.; Blankenship, J.A.; Martin, D.

2001-01-01

Full text: Background: Fueled by an increase in intercepted nuclear smuggling events, the threat of nuclear smuggling has received increased attention in recent years. This attention has resulted in a focused effort to improve the ability to deter or detect smuggling attempts through border crossings, including seaports, airports, and rail and road crossings. These efforts have primarily been focused on installing SNM detectors across vehicle and pedestrian gates entering these ports. However, the effectiveness of this application in deterring or detecting events has not been carefully evaluated. A recent effort was undertaken to evaluate in detail the susceptibility of an international seaport and airport to nuclear smuggling. The evaluation considered a range of adversary profiles to match these against existing and proposed port security measures and equipment. The evaluation was pursued using path analysis methodologies, which were adapted to the port environment. As a result of limited data concerning the effectiveness of patrol, search, and access control procedures at the port, an assessment methodology was developed to estimate these in a standardized fashion. The methodology considers a detailed list of tasks each type of adversary must successfully accomplish for any particular smuggling scenario and path through the port. Within these tasks, locations or times of potential detection are identified. From a look-up table, a detection level (Low, Medium, or High) is assigned to each detection potential based upon the type of detection possible and considering the possible access or authority of each adversary. The overall detection potential in determined as a sum of these individual detection potentials according to the equation: P t ={1-Σ(1-P n ). Where: P t is the total detection potential for an adversary path, and P n is the individual detection at a particular location or time. The evaluation revealed that the current process of installing portals at

Development of Risk Assessment Methodology for State's Nuclear Security Regime

Energy Technology Data Exchange (ETDEWEB)

Jang, Sung Soon; Seo, Hyung Min; Lee, Jung Ho; Kwak, Sung Woo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2011-05-15

Threats of nuclear terrorism are increasing after 9/11 terrorist attack. Treats include nuclear explosive device (NED) made by terrorist groups, radiological damage caused by a sabotage aiming nuclear facilities, and radiological dispersion device (RDD), which is also called 'dirty bomb'. In 9/11, Al Qaeda planed to cause radiological consequences by the crash of a nuclear power plant and the captured airplane. The evidence of a dirty bomb experiment was found in Afganistan by the UK intelligence agency. Thus, the international communities including the IAEA work substantial efforts. The leaders of 47 nations attended the 2010 nuclear security summit hosted by President Obama, while the next global nuclear summit will be held in Seoul, 2012. Most states established and are maintaining state's nuclear security regime because of the increasing threat and the international obligations. However, each state's nuclear security regime is different and depends on the state's environment. The methodology for the assessment of state's nuclear security regime is necessary to design and implement an efficient nuclear security regime, and to figure out weak points. The IAEA's INPRO project suggests a checklist method for State's nuclear security regime. The IAEA is now researching more quantitative methods cooperatively with several countries including Korea. In this abstract, methodologies to evaluate state's nuclear security regime by risk assessment are addressed

Estudo MONISA: características e aspectos metodológicos MONISA study: characteristics and methodological aspects

Directory of Open Access Journals (Sweden)

Thiago Ferreira de Sousa

2012-12-01

Full Text Available O objetivo é apresentar as características e os procedimentos metodológicos adotados no Estudo Monitoramento dos Indicadores de Saúde e Qualidade de Vida de Acadêmicos (MONISA. Trata-se de um estudo prospectivo, do tipo painel, com inquéritos bianuais em amostras representativas de estudantes de uma universidade pública do Estado da Bahia. Este estudo realizará cinco inquéritos, perfazendo 10 anos de monitoramento (2010 a 2018. A amostra é estratificada e proporcional aos cursos de graduação presenciais, período de estudo (noturno e diurno e ano de ingresso na universidade. Por fim, os estudantes universitários são selecionados em cada estrato, por meio da lista de matrícula em ordem alfabética. Para obtenção das informações é utilizado um questionário estruturado, com as seguintes seções: indicadores sociodemográficos; indicadores do estilo de vida e saúde; hábitos alimentares e controle do peso corporal; atividades físicas e opções de lazer; comportamentos preventivos; e, indicadores do ambiente e condições de aprendizagem. O pioneirismo do Estudo MONISA poderá auxiliar no esclarecimento de possíveis tendências relacionadas à saúde de estudantes universitários brasileiros e subsidiar informações para propor programas ou projetos de promoção da saúde e qualidade de vida em nível organizacional local.The objective is to present the characteristics and methodological procedures adopted in the MONISA Study (Surveillance of health and quality of life indicators of college students. This is a prospective, panel type study, with biannual surveys of representative samples of undergraduate students at a public university in the State of Bahia, Brazil. This study carried out five surveys, totaling 10 years of monitoring (2010-2018. The sample is stratified and proportional to the courses, study period (day and night and year of attending university. Finally, college students are selected at each stratum

Methodology for value/impact assessment of nuclear regulatory research programs

International Nuclear Information System (INIS)

Carlson, D.D.

1978-12-01

A methodology for conducting a value/impact assessment of research programs has been developed to provide the Nuclear Regulatory Commission (NRC) an improved capability for allocating resources for confirmatory research. This report presents a seven-step evaluation process and applies it to selected units of research. The methodology is intended to provide insight into the technical merits of the programs, one dimension of the complex problem of resource allocation for confirmatory research

Use of the project management methodology to establish physical protection system at nuclear facility

International Nuclear Information System (INIS)

Gramotkin, F.; Kuzmyak, I.; Kravtsov, V.

2015-01-01

The paper considers the possibility of using the project management methodology developed by the Project Management Institute (USA) in nuclear security in terms of modernization or development of physical protection system at nuclear facility. It was demonstrated that this methodology allows competent and flexible management of the projects on physical protection, ensuring effective control of their timely implementation in compliance with the planned budget and quality

Methodology implementation for multi objective optimisation for nuclear fleet evolution scenarios

International Nuclear Information System (INIS)

Freynet, David

2016-01-01

The issue of the evolution French nuclear fleet can be considered through the study of nuclear transition scenarios. These studies are of paramount importance as their results can greatly affect the decision making process, given that they take into account industrial concerns, investments, time, and nuclear system complexity. Such studies can be performed with the COSI code (developed at the CEA/DEN), which enables the calculation of matter inventories and fluxes across the fuel cycle (nuclear reactors and associated facilities), especially when coupled with the CESAR depletion code. The studies today performed with COSI require the definition of the various scenarios' input parameters, in order to fulfil different objectives such as minimising natural uranium consumption, waste production and so on. These parameters concern the quantities and the scheduling of spent fuel destined for reprocessing, and the number, the type and the commissioning dates of deployed reactors.This work aims to develop, validate and apply an optimisation methodology coupled with COSI, in order to determine optimal nuclear transition scenarios for a multi-objective platform. Firstly, this methodology is based on the acceleration of scenario evaluation, enabling the use of optimisation methods in a reasonable time-frame. With this goal in mind, artificial neural network irradiation surrogate models are created with the URANIE platform (developed at the CEA/DEN) and are implemented within COSI. The next step in this work is to use, adapt and compare different optimisation methods, such as URANIE's genetic algorithm and particle swarm methods, in order to define a methodology suited to this type of study. This methodology development is based on an incremental approach which progressively adds objectives, constraints and decision variables to the optimisation problem definition. The variables added, which are related to reactor deployment and spent fuel reprocessing strategies, are chosen

PRODUÇÃO E COMPARTILHAMENTO DO CONHECIMENTO NUCLEAR: UM ESTUDO DE CASO NO IEN/CNEN

Directory of Open Access Journals (Sweden)

Marcia Pires da Luz Bettencourt

2012-04-01

Full Text Available O estudo procurou identificar ações que possam contribuir para a produção e compartilhamento de conhecimentos e informações na Divisão de Radiofármacos do Instituto de Engenharia Nuclear da Comissão Nacional de Energia Nuclear (IEN/CNEN. A motivação para a pesquisa foi o risco, identificado em relatórios da área nuclear, de perda de conhecimento nessa área nos últimos anos. A gestão do conhecimento foi escolhida como ferramenta para o estudo do problema apontado, por possuir metodologias que visam estimular o processo de produção e compartilhamento de conhecimentos e informações, em empresas privadas e também em instituições públicas, como é o caso do IEN/CNEN. A gestão do conhecimento é uma disciplina relativamente nova, que mesmo não tendo nascido na Ciência da Informação, nela vem buscando sustentação teórica e legitimidade. A pesquisa identifica fatores que influenciam no compartilhamento de informação e conhecimento, tais como: redes sociais, comunidades de prática, ambientes facilitadores de colaboração, cultura organizacional, aprendizagem para formação de competências, e narrativas (storytelling. A revisão da literatura e analise dos dados obtidos, diversas práticas foram identificadas, e foram feitas algumas sugestões. Conclui-se que o estímulo institucional à colaboração e à troca de conhecimentos pode influenciar em resultados positivos em relação a um incremento na produção de novos conhecimentos.

The Nuclear Organization and Management Analysis Concept methodology: Four years later

International Nuclear Information System (INIS)

Haber, S.B.; Shurberg, D.A.; Barriere, M.T.; Hall, R.E.

1992-01-01

The Nuclear Organization and Management Analysis Concept was first presented at the IEEE Human Factors meeting in Monterey in 1988. In the four years since that paper, the concept and its associated methodology has been demonstrated at two commercial nuclear power plants (NPP) and one fossil power plant. In addition, applications of some of the methods have been utilized in other types of organizations, and products are being developed from the insights obtained using the concept for various organization and management activities. This paper will focus on the insights and results obtained from the two demonstration studies at the commercial NPPs. The results emphasize the utility of the methodology and the comparability of the results from the two organizations

A methodology for nuclear power plant operational events evaluation

International Nuclear Information System (INIS)

Araujo, Jeferson

2015-01-01

to identify trends that might pass unnoticed. There are several methodologies for evaluation of operational events, specifically, for the determination of the causes of the event, where the concepts of root cause, direct cause and causal factors, among others. However, the most recent methodology in use in Brazil, date of 2003. The subject is so important that there is national legislation dealing with the theme, also it need of update. The actual regulations establishes criteria for notification of the occurrence of events considered significant for safety and establishes criteria and deadlines for the issuance of the report. Is also discussed the relationship between occurrence of operational events and a potential application for the life extension of the nuclear power plants, considering the regulatory focus, theme quite present in the international field. The present study intends to present a modern, appropriate methodology for evaluation of operational events, focusing on regulatory aspects and verify its applicability to nuclear power plants. Will also be presented a study of the occurrence of events, focusing on the last five years of operation. Finally will be also presented to international trends in development on this area. (author)

A methodology for nuclear power plant operational events evaluation

Energy Technology Data Exchange (ETDEWEB)

Araujo, Jeferson, E-mail: jeferson@cnen.gov.br [Comissao Nacional de Energia Nuclear (CGRC/CNEN), Rio de janeiro, RJ (Brazil). Coordenacao Geral de Reatores e do Ciclo de Combustivel; Costa, Sergio Dias, E-mail: sergiodiascosta@hotmail.com [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2015-07-01

to identify trends that might pass unnoticed. There are several methodologies for evaluation of operational events, specifically, for the determination of the causes of the event, where the concepts of root cause, direct cause and causal factors, among others. However, the most recent methodology in use in Brazil, date of 2003. The subject is so important that there is national legislation dealing with the theme, also it need of update. The actual regulations establishes criteria for notification of the occurrence of events considered significant for safety and establishes criteria and deadlines for the issuance of the report. Is also discussed the relationship between occurrence of operational events and a potential application for the life extension of the nuclear power plants, considering the regulatory focus, theme quite present in the international field. The present study intends to present a modern, appropriate methodology for evaluation of operational events, focusing on regulatory aspects and verify its applicability to nuclear power plants. Will also be presented a study of the occurrence of events, focusing on the last five years of operation. Finally will be also presented to international trends in development on this area. (author)

Development of a methodology for dissemination and formation favourable of using nuclear energy

Energy Technology Data Exchange (ETDEWEB)

Lobo, Belinda Maria; Aquino, Afonso Rodrigues de, E-mail: belindalobo@usp.br, E-mail: araquino@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

Space Nuclear Technology (ENT), located in the IPEN is the basis for the study of a reporting methodology of Nuclear Energy Technology, for the public get some physical-chemical knowledge, benefits of using radioactivity and the activities carried out by the Institute Energy and Nuclear Research - National Commission of Nuclear Energy (IPEN / CNEN), for increased acceptance of its use. This article reports the survey in two schools, with groups of teachers from different areas of elementary and secondary education of the Sao Paulo state. The strategies used to establish communication by means of an environment of trust are: a questionnaire at the beginning and end of the presentation, one sensationalised reporting, Cesium -137 -Linha Direta, aired by Rede Globo TV, in 2007, theoretical foundation of physics and chemistry, picturesque figures and photos as the Nuclear Reactor IEA-R1. The contributions of this research will improve the methodology for future presentations. (author)

Development of a methodology for dissemination and formation favourable of using nuclear energy

International Nuclear Information System (INIS)

Lobo, Belinda Maria; Aquino, Afonso Rodrigues de

2015-01-01

Space Nuclear Technology (ENT), located in the IPEN is the basis for the study of a reporting methodology of Nuclear Energy Technology, for the public get some physical-chemical knowledge, benefits of using radioactivity and the activities carried out by the Institute Energy and Nuclear Research - National Commission of Nuclear Energy (IPEN / CNEN), for increased acceptance of its use. This article reports the survey in two schools, with groups of teachers from different areas of elementary and secondary education of the Sao Paulo state. The strategies used to establish communication by means of an environment of trust are: a questionnaire at the beginning and end of the presentation, one sensationalised reporting, Cesium -137 -Linha Direta, aired by Rede Globo TV, in 2007, theoretical foundation of physics and chemistry, picturesque figures and photos as the Nuclear Reactor IEA-R1. The contributions of this research will improve the methodology for future presentations. (author)

New quickest transient detection methodology. Nuclear engineering applications

International Nuclear Information System (INIS)

Wang, Xin; Jevremovic, Tatjana; Tsoukalas, Lefteri H.

2003-01-01

A new intelligent systems methodology for quickest online transient detection is presented. Based on information that includes, but is not limited to, statistical features, energy of frequency components and wavelet coefficients, the new methodology decides whether a transient has emerged. A fuzzy system makes the final decision, the membership functions of which are obtained by artificial neural networks and adjusted in an online manner. Comparisons are performed with conventional methods for transient detection using simulated and plant data. The proposed methodology could be useful in power plant operations, diagnostic and maintenance activities. It is also considered as a design tool for quick design modifications in a virtual design environment aimed at next generation University Research and Training Reactors (URTRs). (The virtual design environment is pursued as part of the Big-10 Consortium sponsored by the new Innovations in Nuclear Infrastructure and Education (INIE) program sponsored by the US Department of Energy.) (author)

Nuclear insurance risk assessment using risk-based methodology

International Nuclear Information System (INIS)

Wendland, W.G.

1992-01-01

This paper presents American Nuclear Insurers' (ANI's) and Mutual Atomic Energy Liability Underwriters' (MAELU's) process and experience for conducting nuclear insurance risk assessments using a risk-based methodology. The process is primarily qualitative and uses traditional insurance risk assessment methods and an approach developed under the auspices of the American Society of Mechanical Engineers (ASME) in which ANI/MAELU is an active sponsor. This process assists ANI's technical resources in identifying where to look for insurance risk in an industry in which insurance exposure tends to be dynamic and nonactuarial. The process is an evolving one that also seeks to minimize the impact on insureds while maintaining a mutually agreeable risk tolerance

Methodological basis for formation of uniterruptible education content for future specialists of atomic-nuclear complex

International Nuclear Information System (INIS)

Burtebayev, N.; Burtebayeva, J.T.; Basharuly, R.; Altynsarin, Y.

2009-01-01

Full text: For science-reliable determination of the content of uninterruptible education system, as a rule, the following levels of theoretical-methodological approach are used in complex: 1) science-wide methodological level based on the dialectical laws of knowledge theory; 2) science-wide methodological level based on the principles and the provisions of system analysis; 3) particular science methodological level based on the laws and the principles of any specific science [1]. Such holistic approach covering all levels of science methodology is required for determination of the content of uninterruptible education for future specialists of nuclear profile. Indeed, considering the problem related to the content of uninterruptible education from the point of the first science-wide methodological level we shall follow primary the requirements of dialectical 'Law of common, special and single unity', where firstly the universal values in science, culture and technology forming the united invariant of education content of the world education space is positioned as the 'common' component of uninterruptible education content; secondly, the theoretical-practical achievements gained in the countries of any region (for example Eurasian space) are positioned as the 'special' component of the content for the training of the specialists of nuclear profile; thirdly, the content elements determined in accordance with socio-economic order of the specific society introducing the national interests of the specific country (for example, Republic of Kazakhstan) are positioned as the 'single' component of the education content for the future specialists of atomic-nuclear complex. Inseparable unity of the above mentioned components of the education content which have been determined in accordance with the laws, principles and provisions of all three levels of science-methodological approach assures the high level competence and the functional mobility of nuclear profile specialist

The first international training course on basic nuclear forensic methodologies for practitioners

International Nuclear Information System (INIS)

Schwantes, Jon M.; Smith, David K.

2013-01-01

The IAEA, in cooperation with the United States National Nuclear Security Administration, developed and conducted the first international training course on basic nuclear forensic methodologies for practitioners in 2012. An overview of the major elements of this landmark workshop as well as successes and recommendations for future improvement are presented here. (author)

INPRO Methodology to evaluate the Mexico nuclear energy system; Metodologia INPRO para evaluar el sistema de energia nuclear de Mexico

Energy Technology Data Exchange (ETDEWEB)

Cruz S, R. R.; Martin del C, C., E-mail: crzslns.ricardoruben@gmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

2016-09-15

The International Atomic Energy Agency has developed the so-called International Project on Fuel Cycles and Innovative Nuclear Reactors (INPRO), in order to make nuclear energy available to meet the energy needs of the 21 century, in a sustainable way. One of the tasks of the project is the evaluation of the nuclear systems, to check whether they meet the objectives of the project and whether they are sustainable. This paper explains the rationale and general characteristics of the project in the evaluation of nuclear energy systems based on the concept of sustainable development. It describes the methodology developed to carry out this evaluation, divided into seven areas, such as economic, environmental, security, etc., which together make up the sustainable development of energy through nuclear systems. The economic area is analyzed and the evaluation criteria and parameters established by INPRO are discussed, in order to evaluate the Mexican nuclear energy system using Nest (software developed within the same project) as a tool to support the economic evaluation of nuclear systems. Based on the energy strategy proposed by the Energy Secretary of the Mexican Government which seeks to reduce the greenhouse gas emissions from the national electricity generation park, two types of reactor of currently available technology (A BWR and AP1000), were compared and these in turn with other alternative energy generation technologies, such as combined cycle, geothermal and wind plants. Also, the results of the application of the INPRO methodology are presented. Finally, the recommendations on actions that could lead the Mexican nuclear energy system towards sustainable development and conclusions on the application of the methodology to the Mexican case are mentioned. (Author)

Nuclear data evaluation methodology including estimates of covariances

Directory of Open Access Journals (Sweden)

Smith D.L.

2010-10-01

Full Text Available Evaluated nuclear data rather than raw experimental and theoretical information are employed in nuclear applications such as the design of nuclear energy systems. Therefore, the process by which such information is produced and ultimately used is of critical interest to the nuclear science community. This paper provides an overview of various contemporary methods employed to generate evaluated cross sections and related physical quantities such as particle emission angular distributions and energy spectra. The emphasis here is on data associated with neutron induced reaction processes, with consideration of the uncertainties in these data, and on the more recent evaluation methods, e.g., those that are based on stochastic (Monte Carlo techniques. There is no unique way to perform such evaluations, nor are nuclear data evaluators united in their opinions as to which methods are superior to the others in various circumstances. In some cases it is not critical which approaches are used as long as there is consistency and proper use is made of the available physical information. However, in other instances there are definite advantages to using particular methods as opposed to other options. Some of these distinctions are discussed in this paper and suggestions are offered regarding fruitful areas for future research in the development of evaluation methodology.

Comparison of economic evaluation methodology for the nuclear plant lifetime extension

International Nuclear Information System (INIS)

Song, T. H.; Jung, I. S.

2003-01-01

In connection with economic evaluation of NPP lifetime management, there are lots of methodologies such as present worth calculation, Levelized Unit Energy Cost (LUEC) calculation, and market benefit comparison methodology. In this paper, economic evaluation of NPP lifetime management was carried out by using these three methodologies, and the results of each was compared with the other methodologies. With these three methodologies, break even points of investment cost related to life extension of nuclear power plant were calculated. It was turned out to be as a analysis result that LUEC is more conservative than present worth calculation and that benefit comparison is more conservative than LUEC, which means that Market Benefit Comparison is the most conservative methodology, and which means base load demand of the future would be far more important than any other factors such as capacity factor, investment cost of life extension, and performance of replacing power plant

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

International Nuclear Information System (INIS)

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

1998-07-01

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

Application of NASA Kennedy Space Center system assurance analysis methodology to nuclear power plant systems designs

International Nuclear Information System (INIS)

Page, D.W.

1985-01-01

The Kennedy Space Center (KSC) entered into an agreement with the Nuclear Regulatory Commission (NRC) to conduct a study to demonstrate the feasibility and practicality of applying the KSC System Assurance Analysis (SAA) methodology to nuclear power plant systems designs. In joint meetings of KSC and Duke Power personnel, an agreement was made to select to CATAWBA systems, the Containment Spray System and the Residual Heat Removal System, for the analyses. Duke Power provided KSC with a full set a Final Safety Analysis Reports as well as schematics for the two systems. During Phase I of the study the reliability analyses of the SAA were performed. During Phase II the hazard analyses were performed. The final product of Phase II is a handbook for implementing the SAA methodology into nuclear power plant systems designs. The purpose of this paper is to describe the SAA methodology as it applies to nuclear power plant systems designs and to discuss the feasibility of its application. The conclusion is drawn that nuclear power plant systems and aerospace ground support systems are similar in complexity and design and share common safety and reliability goals. The SAA methodology is readily adaptable to nuclear power plant designs because of it's practical application of existing and well known safety and reliability analytical techniques tied to an effective management information system

Comparison of risk assessment methodologies for nuclear power and nuclear fuels processing plants

International Nuclear Information System (INIS)

Durant, W.S.; Walker, D.H.

1986-08-01

The utilization of nuclear fission for the generation of electric power or other purposes has as its by-product radioactive fission products. These radioactive fission products represent a potential hazard different in nature from that associated with other process operations or other methods of electrical power generation. As a result the electrical power stations and the facilities designed to process the irradiated fuel to recover the still useful fuel and the products of the irradiation are designed with multiple physical barriers to contain the radioactive fission products in the event that an accident were to occur. In recent years, a disciplined approach has evolved for developing detailed models of a facility and its processes. These models can be used to assess the response for the facility to upset or accident events. The approach is based on an ordered application of available data employing fault tree/event tree methodologies. Data and/or engineering judgment are applied in a probabilisitc framework so the approach has been called Probabilistic Risk Assessment (PRA). The approach has been applied to nuclear electric generating facilities and to nuclear fuel processing facilities to assess the potential for release of fission product and transuranium element radionuclides (the hazard) and the resulting risks. The application of the methodology to the electrical generating facilities and to the fuel processing facilities has evolved somewhat differently because of differences in the facilities, availability of failure rate data, and expected outputs. This paper summarizes the two approaches and the differences in them compares the risk results from the existing studies

Desafios dos Estudos Gays, Lésbicos e Transgêneros

Directory of Open Access Journals (Sweden)

Denilson Lopes

2008-09-01

Full Text Available Resumo: Este ensaio introduz algumas questões relativas aos estudos feministas, gays, lésbicos, transgênecos e teoria queer na busca de contribuições teórico-metodológicas na análise da cultura contemporânea. Palavras-chave: Estudos gays e lésbicos, estudos transgêneros, teoria queer, cultura. Abstrat: This essay introduces some issues related tofeminist studies, gay and lesbian studies, transgender studies and queer theory in the search of theoretical and methodological contributions in the analysis of contemporary culture. Key-words: Gay and Lesbian Studies, transgender studies, queer theory, culture

Methodology for flood risk analysis for nuclear power plants

International Nuclear Information System (INIS)

Wagner, D.P.; Casada, M.L.; Fussell, J.B.

1984-01-01

The methodology for flood risk analysis described here addresses the effects of a flood on nuclear power plant safety systems. Combining the results of this method with the probability of a flood allows the effects of flooding to be included in a probabilistic risk assessment. The five-step methodology includes accident sequence screening to focus the detailed analysis efforts on the accident sequences that are significantly affected by a flood event. The quantitative results include the flood's contribution to system failure probability, accident sequence occurrence frequency and consequence category occurrence frequency. The analysis can be added to existing risk assessments without a significant loss in efficiency. The results of two example applications show the usefulness of the methodology. Both examples rely on the Reactor Safety Study for the required risk assessment inputs and present changes in the Reactor Safety Study results as a function of flood probability

A methodology for evaluating ''new'' technologies in nuclear power plants

International Nuclear Information System (INIS)

Korsah, K.; Clark, R.L.; Holcomb, D.E.

1994-01-01

As obsolescence and spare parts issues drive nuclear power plants to upgrade with new technology (such as optical fiber communication systems), the ability of the new technology to withstand stressors present where it is installed needs to be determined. In particular, new standards may be required to address qualification criteria and their application to the nuclear power plants of tomorrow. This paper discusses the failure modes and age-related degradation mechanisms of fiber optic communication systems, and suggests a methodology for identifying when accelerated aging should be performed during qualification testing

Projecting labor demand and worker immigration at nuclear power plant construction sites: an evaluation of methodology

International Nuclear Information System (INIS)

Herzog, H.W. Jr; Schlottmann, A.M.; Schriver, W.R.

1981-12-01

The study evaluates methodology employed for the projection of labor demand at, and worker migration to, nuclear power plant construction sites. In addition, suggestions are offered as to how this projection methodology might be improved. The study focuses on projection methodologies which forecast either construction worker migration or labor requirements of alternative types of construction activity. Suggested methodological improvements relate both to institutional factors within the nuclear power plant construction industry, and to a better use of craft-specific data on construction worker demand/supply. In addition, the timeliness and availability of the regional occupational data required to support, or implement these suggestions are examined

Methodology for safety classification of PWR type nuclear power plants items

International Nuclear Information System (INIS)

Oliveira, Patricia Pagetti de

1995-01-01

This paper contains the criteria and methodology which define a classification system of structures, systems and components in safety classes according to their importance to nuclear safety. The use of this classification system will provide a set of basic safety requirements associated with each safety class specified. These requirements, when available and applicable, shall be utilized in the design, fabrication and installation of structures, systems and components of Pressurized Water Reactor Nuclear Power Plants. (author). 13 refs, 1 tab

Methodology for proliferation resistance and physical protection of Generation IV nuclear energy systems

International Nuclear Information System (INIS)

Bari, R.; Peterson, P.; Nishimura, R.; Roglans-Ribas, J.

2005-01-01

Enhanced proliferation resistance and physical protection (PR and PP) is one of the technology goals for advanced nuclear concepts. Under the auspices of the Generation IV International Forum an international experts group has been chartered to develop an evaluation methodology for PR and PP. This methodology will permit an objective PR and PP comparison between alternative nuclear systems and support design optimization to enhance robustness against proliferation, theft and sabotage. The assessment framework consists of identifying the threats to be considered, defining the PR and PP measures required to evaluate the resistance of a nuclear system to proliferation, theft or sabotage, and establishing quantitative methods to evaluate the proposed measures. The defined PR and PP measures are based on the design of the system (e.g., materials, processes, facilities), and institutional measures (e.g., safeguards, access control). The assessment methodology uses analysis of pathways' with respect to specific threats to determine the PR and PP measures. Analysis requires definition of the threats (i.e. objective, capability, strategy), decomposition of the system into its relevant elements (e.g., reactor core, fuel recycle facility, fuel storage), and identification of targets. (author)

Analysis of offsite dose calculation methodology for a nuclear power reactor

International Nuclear Information System (INIS)

Moser, D.M.

1995-01-01

This technical study reviews the methodology for calculating offsite dose estimates as described in the offsite dose calculation manual (ODCM) for Pennsylvania Power and Light - Susquehanna Steam Electric Station (SSES). An evaluation of the SSES ODCM dose assessment methodology indicates that it conforms with methodology accepted by the US Nuclear Regulatory Commission (NRC). Using 1993 SSES effluent data, dose estimates are calculated according to SSES ODCM methodology and compared to the dose estimates calculated according to SSES ODCM and the computer model used to produce the reported 1993 dose estimates. The 1993 SSES dose estimates are based on the axioms of Publication 2 of the International Commission of Radiological Protection (ICRP). SSES Dose estimates based on the axioms of ICRP Publication 26 and 30 reveal the total body estimates to be the most affected

Methodology for evaluation of alternative technologies applied to nuclear fuel reprocessing

International Nuclear Information System (INIS)

Selvaduray, G.S.; Goldstein, M.K.; Anderson, R.N.

1977-07-01

An analytic methodology has been developed to compare the performance of various nuclear fuel reprocessing techniques for advanced fuel cycle applications including low proliferation risk systems. The need to identify and to compare those processes, which have the versatility to handle the variety of fuel types expected to be in use in the next century, is becoming increasingly imperative. This methodology allows processes in any stage of development to be compared and to assess the effect of changing external conditions on the process

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

A framework and methodology for nuclear fuel cycle transparency

International Nuclear Information System (INIS)

McClellan, Yvonne; York, David L.; Inoue, Naoko; Love, Tracia L.; Rochau, Gary Eugene

2006-01-01

A key objective to the global deployment of nuclear technology is maintaining transparency among nation-states and international communities. By providing an environment in which to exchange scientific and technological information regarding nuclear technology, the safe and legitimate use of nuclear material and technology can be assured. Many nations are considering closed or multiple-application nuclear fuel cycles and are subsequently developing advanced reactors in an effort to obtain some degree of energy self-sufficiency. Proliferation resistance features that prevent theft or diversion of nuclear material and reduce the likelihood of diversion from the civilian nuclear power fuel cycle are critical for a global nuclear future. IAEA Safeguards have been effective in minimizing opportunities for diversion; however, recent changes in the global political climate suggest implementation of additional technology and methods to ensure the prompt detection of proliferation. For a variety of reasons, nuclear facilities are becoming increasingly automated and will require minimum manual operation. This trend provides an opportunity to utilize the abundance of process information for monitoring proliferation risk, especially in future facilities. A framework that monitors process information continuously can lead to greater transparency of nuclear fuel cycle activities and can demonstrate the ability to resist proliferation associated with these activities. Additionally, a framework designed to monitor processes will ensure the legitimate use of nuclear material. This report describes recent efforts to develop a methodology capable of assessing proliferation risk in support of overall plant transparency. The framework may be tested at the candidate site located in Japan: the Fuel Handling Training Model designed for the Monju Fast Reactor at the International Cooperation and Development Training Center of the Japan Atomic Energy Agency

Application of extended statistical combination of uncertainties methodology for digital nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

In, Wang Ki; Uh, Keun Sun; Chul, Kim Heui [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-02-01

A technically more direct statistical combinations of uncertainties methodology, extended SCU (XSCU), was applied to statistically combine the uncertainties associated with the DNBR alarm setpoint and the DNBR trip setpoint of digital nuclear power plants. The modified SCU (MSCU) methodology is currently used as the USNRC approved design methodology to perform the same function. In this report, the MSCU and XSCU methodologies were compared in terms of the total uncertainties and the net margins to the DNBR alarm and trip setpoints. The MSCU methodology resulted in the small total penalties due to a significantly negative bias which are quite large. However the XSCU methodology gave the virtually unbiased total uncertainties. The net margins to the DNBR alarm and trip setpoints by the MSCU methodology agree with those by the XSCU methodology within statistical variations. (Author) 12 refs., 17 figs., 5 tabs.

Methodology used in IRSN nuclear accident cost estimates in France

International Nuclear Information System (INIS)

2015-01-01

This report describes the methodology used by IRSN to estimate the cost of potential nuclear accidents in France. It concerns possible accidents involving pressurized water reactors leading to radioactive releases in the environment. These accidents have been grouped in two accident families called: severe accidents and major accidents. Two model scenarios have been selected to represent each of these families. The report discusses the general methodology of nuclear accident cost estimation. The crucial point is that all cost should be considered: if not, the cost is underestimated which can lead to negative consequences for the value attributed to safety and for crisis preparation. As a result, the overall cost comprises many components: the most well-known is offsite radiological costs, but there are many others. The proposed estimates have thus required using a diversity of methods which are described in this report. Figures are presented at the end of this report. Among other things, they show that purely radiological costs only represent a non-dominant part of foreseeable economic consequences. (authors)

Methodology for identifying boundaries of systems important to safety in CANDU nuclear power plants

International Nuclear Information System (INIS)

Therrien, S.; Komljenovic, D.; Therrien, P.; Ruest, C.; Prevost, P.; Vaillancourt, R.

2007-01-01

This paper presents a methodology developed to identify the boundaries of the systems important to safety (SIS) at the Gentilly-2 Nuclear Power Plant (NPP), Hydro-Quebec. The SIS boundaries identification considers nuclear safety only. Components that are not identified as important to safety are systematically identified as related to safety. A global assessment process such as WANO/INPO AP-913 'Equipment Reliability Process' will be needed to implement adequate changes in the management rules of those components. The paper depicts results in applying the methodology to the Shutdown Systems 1 and 2 (SDS 1, 2), and to the Emergency Core Cooling System (ECCS). This validation process enabled fine tuning the methodology, performing a better estimate of the effort required to evaluate a system, and identifying components important to safety of these systems. (author)

Improved best estimate plus uncertainty methodology, including advanced validation concepts, to license evolving nuclear reactors

International Nuclear Information System (INIS)

Unal, C.; Williams, B.; Hemez, F.; Atamturktur, S.H.; McClure, P.

2011-01-01

Research highlights: → The best estimate plus uncertainty methodology (BEPU) is one option in the licensing of nuclear reactors. → The challenges for extending the BEPU method for fuel qualification for an advanced reactor fuel are primarily driven by schedule, the need for data, and the sufficiency of the data. → In this paper we develop an extended BEPU methodology that can potentially be used to address these new challenges in the design and licensing of advanced nuclear reactors. → The main components of the proposed methodology are verification, validation, calibration, and uncertainty quantification. → The methodology includes a formalism to quantify an adequate level of validation (predictive maturity) with respect to existing data, so that required new testing can be minimized, saving cost by demonstrating that further testing will not enhance the quality of the predictive tools. - Abstract: Many evolving nuclear energy technologies use advanced predictive multiscale, multiphysics modeling and simulation (M and S) capabilities to reduce the cost and schedule of design and licensing. Historically, the role of experiments has been as a primary tool for the design and understanding of nuclear system behavior, while M and S played the subordinate role of supporting experiments. In the new era of multiscale, multiphysics computational-based technology development, this role has been reversed. The experiments will still be needed, but they will be performed at different scales to calibrate and validate the models leading to predictive simulations for design and licensing. Minimizing the required number of validation experiments produces cost and time savings. The use of multiscale, multiphysics models introduces challenges in validating these predictive tools - traditional methodologies will have to be modified to address these challenges. This paper gives the basic aspects of a methodology that can potentially be used to address these new challenges in

A methodology for analyzing the detection and suppression of fires in nuclear power plants

International Nuclear Information System (INIS)

Siu, N.; Apostolakis, G.

1986-01-01

The assessment of the fire risk in nuclear power plants requires the analysis of fire scenarios within specified rooms. A methodology that integrates the fire protection features of a given room into an existing fire risk analysis framework is developed. An important component of this methodology is a model for the time required to detect and suppress a fire in a given room, called the ''hazard time.'' This model accounts for the reliability of fire detection and suppression equipment, as well as for the characteristics rates of the detection and suppression processes. Because the available evidence for fire detection and suppression in nuclear power plants is sparse and often qualitative, a second component of this methodology is a set of methods needed to employ imprecise information in a statistical analysis. These methods can be applied to a wide variety of problems

INPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Environmental Impact of Stressors. INPRO Manual

International Nuclear Information System (INIS)

2016-01-01

This publication provides guidance on assessing of sustainability of a nuclear energy system (NES) in the area of environmental impact of stressors. The INPRO methodology is a comprehensive tool for the assessment of sustainability of an NES. Basic principles, user requirements and criteria have been defined in different areas of INPRO methodology. These include economics, infrastructure, waste management, proliferation resistance, environmental impact of stressors, environmental impact from depletion of resources, and safety of nuclear reactors and fuel cycle facilities. The ultimate goal of the application of the INPRO methodology is to check whether the assessed NES fulfils all the criteria, and hence the user requirements and basic principles, and therefore presents a system for a Member State that is sustainable in the long term

Methodology for characterizing potential adversaries of Nuclear Material Safeguards Systems

International Nuclear Information System (INIS)

Kirkwood, C.W.; Pollock, S.M.

1978-11-01

The results are described of a study by Woodward--Clyde Consultants to assist the University of California Lawrence Livermore Laboratory in the development of methods to analyze and evaluate Nuclear Material Safeguards (NMS) Systems. The study concentrated on developing a methodology to assist experts in describing, in quantitative form, their judgments about the characteristics of potential adversaries of NMS Systems

Methodology for characterizing potential adversaries of Nuclear Material Safeguards Systems

Energy Technology Data Exchange (ETDEWEB)

Kirkwood, C.W.; Pollock, S.M.

1978-11-01

The results are described of a study by Woodward--Clyde Consultants to assist the University of California Lawrence Livermore Laboratory in the development of methods to analyze and evaluate Nuclear Material Safeguards (NMS) Systems. The study concentrated on developing a methodology to assist experts in describing, in quantitative form, their judgments about the characteristics of potential adversaries of NMS Systems.

An intelligent design methodology for nuclear power systems

International Nuclear Information System (INIS)

Nassersharif, B.; Martin, R.P.; Portal, M.G.; Gaeta, M.J.

1989-01-01

The goal of this investigation is to research possible methodologies into automating the design of, specifically, nuclear power facilities; however, it is relevant to all thermal power systems. The strategy of this research has been to concentrate on individual areas of the thermal design process, investigate procedures performed, develop methodology to emulate that behavior, and prototype it in the form of a computer program. The design process has been generalized as follows: problem definition, design definition, component selection procedure, optimization and engineering analysis, testing and final design with the problem definition defining constraints that will be applied to the selection procedure as well as design definition. The result of this research is a prototype computer program applying an original procedure for the selection of the best set of real components that would be used in constructing a system with desired performance characteristics. The mathematical model used for the selection procedure is possibility theory

National Certification Methodology for the Nuclear Weapons Stockpile

International Nuclear Information System (INIS)

Goodwin, B T; Juzaitis, R J

2006-01-01

and December of 2001 and continued in 2002 have proven useful in developing the methodology, and future workshops should prove useful in further refining this framework. Each laboratory developed an approach to certification with some differences in detailed implementation. The general methodology introduces specific quantitative indicators for assessing confidence in our nuclear weapon stockpile. The quantitative indicators are based upon performance margins for key operating characteristics and components of the system, and these are compared to uncertainties in these factors. These criteria can be summarized in a quantitative metric (for each such characteristic) expressed as: (i.e., confidence in warhead performance depends upon CR significantly exceeding unity for all these characteristics). These Confidence Ratios are proposed as a basis for guiding technical and programmatic decisions on stockpile actions. This methodology already has been deployed in certifying weapons undergoing current life extension programs or component remanufacture. The overall approach is an adaptation of standard engineering practice and lends itself to rigorous, quantitative, and explicit criteria for judging the robustness of weapon system and component performance at a detailed level. There are, of course, a number of approaches for assessing these Confidence Ratios. The general certification methodology was publicly presented for the first time to a meeting of Strategic Command SAG in January 2002 and met with general approval. At that meeting, the Laboratories committed to further refine and develop the methodology through the implementation process. This paper reflects the refinement and additional development to date. There will be even further refinement at a joint laboratory workshop later in FY03. A common certification methodology enables us to engage in peer reviews and evaluate nuclear weapon systems on the basis of explicit and objective metrics. The clarity provided by

Assessment of two small-sized innovative nuclear reactors for electricity generation in Brazil using INPRO methodology

International Nuclear Information System (INIS)

Goncalves Filho, Orlando Joao Agostinho; Sefidvash, Farhang

2009-01-01

This paper presents the main results of the assessment study of two small-sized innovative reactors for electricity generation in Brazil using the methodology developed under the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), co-ordinated by the International Atomic Energy Agency (IAEA). INPRO was initiated in 2001 and has the main objective of helping to ensure that nuclear energy is available to contribute in a sustainable manner to the energy needs of the 21st century. Brazil joined the INPRO project since its beginning and in 2005 submitted a proposal for the assessment using INPRO methodology of two small-sized reactors (IRIS - International Reactor Innovative and Secure, and FBNR - Fixed Bed Nuclear Reactor) as potential components of an innovative nuclear energy system (INS) completed by a conventional open nuclear fuel cycle based on enriched uranium. The scope of this assessment study was restricted to the reactor component of the INS and to the methodology areas of economics and safety for IRIS, and proliferation resistance and safety for FBNR. The results indicate that both IRIS and FBNR innovative designs comply mostly with the basic principles of the areas assessed and have potential to comply with the remaining ones. (author)

Development of a new methodology for quantifying nuclear safety culture

International Nuclear Information System (INIS)

Han, Kiyoon; Jae, Moosung

2017-01-01

The present study developed a Safety Culture Impact Assessment Model (SCIAM) which consists of a safety culture assessment methodology and a safety culture impact quantification methodology. The SCIAM uses a safety culture impact index (SCII) to monitor the status of safety culture of NPPs periodically and it uses relative core damage frequency (RCDF) to present the impact of safety culture on the safety of NPPs. As a result of applying the SCIAM to the reference plant (Kori 3), the standard for the healthy safety culture of the reference plant is suggested. SCIAM might contribute to improve the safety of NPPs (Nuclear Power Plants) by monitoring the status of safety culture periodically and presenting the standard of healthy safety culture.

Development of a new methodology for quantifying nuclear safety culture

Energy Technology Data Exchange (ETDEWEB)

Han, Kiyoon; Jae, Moosung [Hanyang Univ., Seoul (Korea, Republic of). Dept. of Nuclear Engineering

2017-01-15

The present study developed a Safety Culture Impact Assessment Model (SCIAM) which consists of a safety culture assessment methodology and a safety culture impact quantification methodology. The SCIAM uses a safety culture impact index (SCII) to monitor the status of safety culture of NPPs periodically and it uses relative core damage frequency (RCDF) to present the impact of safety culture on the safety of NPPs. As a result of applying the SCIAM to the reference plant (Kori 3), the standard for the healthy safety culture of the reference plant is suggested. SCIAM might contribute to improve the safety of NPPs (Nuclear Power Plants) by monitoring the status of safety culture periodically and presenting the standard of healthy safety culture.

IAEA Nuclear Security Assessment Methodologies (NUSAM) Project for Regulated Facilities

International Nuclear Information System (INIS)

Jang, Sung Soon

2016-01-01

Nuclear Security Assessment Methodologies (NUSAM) is a coordinate research project. The objectives of the NUSAM project is to establish a risk informed, performance-based methodological framework in a systematic, structured, comprehensive and appropriately transparent manner; to provide an environment for the sharing and transfer of knowledge and experience; and to provide guidance on, and practical examples of good practices in assessing the security of nuclear and other radioactive materials, as well as associated facilities and activities. The author worked as an IAEA scientific secretary of the NUAM project from 2013 to 2015. IAEA launched this project in 2013 and performed many activities: meetings, document development, table-top exercises and computer simulations. Now the project is in the final stage and will be concluded in the late 2016. The project will produce documents on NUSAM assessment methods and case study documents on NPP, Irradiator Facility and Transport. South Korea as a main contributor to this project will get benefits from the NUSAM. In 2014, South Korea introduced force-on-force exercises, which could be used as the assessment of physical protection system by the methods of NUSAM

IAEA Nuclear Security Assessment Methodologies (NUSAM) Project for Regulated Facilities

Energy Technology Data Exchange (ETDEWEB)

Jang, Sung Soon [Korea Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

2016-05-15

Nuclear Security Assessment Methodologies (NUSAM) is a coordinate research project. The objectives of the NUSAM project is to establish a risk informed, performance-based methodological framework in a systematic, structured, comprehensive and appropriately transparent manner; to provide an environment for the sharing and transfer of knowledge and experience; and to provide guidance on, and practical examples of good practices in assessing the security of nuclear and other radioactive materials, as well as associated facilities and activities. The author worked as an IAEA scientific secretary of the NUAM project from 2013 to 2015. IAEA launched this project in 2013 and performed many activities: meetings, document development, table-top exercises and computer simulations. Now the project is in the final stage and will be concluded in the late 2016. The project will produce documents on NUSAM assessment methods and case study documents on NPP, Irradiator Facility and Transport. South Korea as a main contributor to this project will get benefits from the NUSAM. In 2014, South Korea introduced force-on-force exercises, which could be used as the assessment of physical protection system by the methods of NUSAM.

National assessment study in Armenia using innovative nuclear reactors and fuel cycles methodology for an innovative nuclear systems in a country with small grid

International Nuclear Information System (INIS)

Sargsyan, V.H.; Galstyan, A.A.; Gevorgyan, A.A.

2010-01-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was launched in November 2000 under the aegis of the IAEA. Phases 1A and IB (first Part) of the Project were dedicated to elaboration, testing and validation of the INPRO Methodology. At the Technical Meeting in Vienna (13-15 October 2004) Armenia has proposed an assessment using the INPRO Methodology for an Innovative Nuclear Energy System in a country with a small electrical grid. Such kind of study helps Armenia in analysis of Innovative Nuclear Energy System (INS), including fuel cycle options, as well as shows applicability of INPRO methodology for small countries, like Armenia. This study was based on the results given in [3] and [4], and also on the main objectives, declared by the Government of Armenia in the paper 'Energy Sector Development Strategies in the Context of Economic Development in Armenia'

Nuclear reactor conceptual design: methodology for cost-effective internalisation of nuclear safety

International Nuclear Information System (INIS)

Gimenez, M.; Grinblat, P.; Schlamp, M.

2002-01-01

A novel and promising methodology to perform nuclear reactor design is presented in this work. It achieves to balance efficiently safety and economics at the conceptual engineering stage. The key to this integral approach is to take into account safety aspects in a design optimisation process where the design variables are balanced in order to obtain a better figure of merit related with reactor economic performance. Design parameter effects on characteristic or critical safety variables, chosen from reactor behaviour during accidents and from its probabilistic safety assessment -safety performance indicators-, are synthesised on Safety Design Maps. These maps allow one to compare these indicators with limit values, which are determined by design criteria or regulations, and to transfer these restrictions to the design parameters. In this way, reactor dynamic response and other safety aspects are integrated in a global optimisation process, by means of additional rules to the neutronic, thermal-hydraulic and mechanical calculations. This methodology turns out to be promising to balance and optimise reactor and safety system design in an early engineering stage, in order to internalise cost-efficiently safety issues. It also allows one to evaluate the incremental costs of implementing higher safety levels. Furthermore, through this methodology, a simplified design can be obtained, compared to the resultant complexity when these concepts are introduced in a later engineering stage. (author)

Application of Master Curve Methodology for Structural Integrity Assessments of Nuclear Components

Energy Technology Data Exchange (ETDEWEB)

Sattari-Far, Iradj [Det Norske Veritas, Stockholm (Sweden); Wallin, Kim [VTT, Esbo (Finland)

2005-10-15

The objective was to perform an in-depth investigation of the Master Curve methodology and also based on this method develop a procedure for fracture assessments of nuclear components. The project has sufficiently illustrated the capabilities of the Master Curve methodology for fracture assessments of nuclear components. Within the scope of this work, the theoretical background of the methodology and its validation on small and large specimens has been studied and presented to a sufficiently large extent, as well as the correlations between the charpy-V data and the Master Curve T{sub 0} reference temperature in the evaluation of fracture toughness. The work gives a comprehensive report of the background theory and the different applications of the Master Curve methodology. The main results of the work have shown that the cleavage fracture toughness is characterized by a large amount of statistical scatter in the transition region, it is specimen size dependent and it should be treated statistically rather than deterministically. The Master Curve methodology is able to make use of statistical data in a consistent way. Furthermore, the Master Curve methodology provides a more precise prediction of the fracture toughness of embrittled materials in comparison with the ASME K{sub IC} reference curve, which often gives over-conservative results. The suggested procedure in this study, concerning the application of the Master Curve method in fracture assessments of ferritic steels in the transition region and the low shelf regions, is valid for the temperatures range T{sub 0}-50{<=}T{<=}T{sub 0}+50 deg C. If only approximate information is required, the Master Curve may well be extrapolated outside this temperature range. The suggested procedure has also been illustrated for some examples.

A cost-effective methodology to internalize nuclear safety in nuclear reactor conceptual design

International Nuclear Information System (INIS)

Gimenez, M.; Grinblat, P.; Schlamp, M.

2003-01-01

A new methodology to perform nuclear reactor design, balancing safety and economics at the conceptual engineering stage, is presented in this work. The goal of this integral methodology is to take into account safety aspects in an optimization design process where the design variables are balanced in order to obtain a better figure of merit related with reactor economic performance. Design parameter effects on characteristic or critical safety variables, chosen from reactor behavior during accidents (safety performance indicators), are synthesized on Design Maps. These maps allow one to compare the safety indicator with limits, which are determined by design criteria or regulations, and to transfer these restrictions to the design parameters. In this way, reactor dynamic response and other safety aspects are integrated in a global optimization process, by means of additional rules to the neutronic, thermal-hydraulic, and mechanical calculations. An application of the methodology, implemented in Integrated Reactor Evaluation Program 3 (IREP3) code, to optimize safety systems of CAREM prototype is presented. It consists in balancing the designs of the Emergency Injection System (EIS), the Residual Heat Removal System (RHRS), the primary circuit water inventory and the containment height, to cope with loss of coolant and loss of heat sink (LOHS) accidental sequences, taking into account cost and reactor performance. This methodology turns out to be promising to internalize cost-efficiently safety issues. It also allows one to evaluate the incremental costs of implementing higher safety levels

Application of NASA Kennedy Space Center System Assurance Analysis methodology to nuclear power plant systems designs

International Nuclear Information System (INIS)

Page, D.W.

1985-01-01

In May of 1982, the Kennedy Space Center (KSC) entered into an agreement with the NRC to conduct a study to demonstrate the feasibility and practicality of applying the KSC System Assurance Analysis (SAA) methodology to nuclear power plant systems designs. North Carolina's Duke Power Company expressed an interest in the study and proposed the nuclear power facility at CATAWBA for the basis of the study. In joint meetings of KSC and Duke Power personnel, an agreement was made to select two CATAWBA systems, the Containment Spray System and the Residual Heat Removal System, for the analyses. Duke Power provided KSC with a full set of Final Safety Analysis Reports (FSAR) as well as schematics for the two systems. During Phase I of the study the reliability analyses of the SAA were performed. During Phase II the hazard analyses were performed. The final product of Phase II is a handbook for implementing the SAA methodology into nuclear power plant systems designs. The purpose of this paper is to describe the SAA methodology as it applies to nuclear power plant systems designs and to discuss the feasibility of its application. (orig./HP)

Evaluation methodology of a manipulator actuator for the dismantling process during nuclear decommissioning

International Nuclear Information System (INIS)

Park, Jongwon; Kim, Chang-Hoi; Jeong, Kyung-min; Choi, Byung-Seon; Moon, Jeikwon

2016-01-01

Highlights: • A methodology to evaluate actuators of a dismantling manipulator. • Evaluation criteria for choosing the most suitable actuator type. • A mathematical evaluation model for evaluation. • The evaluation method is expected to be used for determining other manipulators. - Abstract: This paper presents a methodology to evaluate actuators of a manipulator for dismantling nuclear power plants. Actuators are the most dominant components because a dismantling manipulator relies heavily on the actuator type used. To select the most suitable actuator, evaluation criteria are presented in four categories based on the nuclear dismantling environment. A mathematical model is presented and evaluation results are calculated with weights and scores for each criterion. The proposed evaluation method is expected to be used for determining other aspects of the design of dismantling manipulators.

Methodology applied by IRSN for nuclear accident cost estimations in France

International Nuclear Information System (INIS)

2013-01-01

This report describes the methodology used by IRSN to estimate the cost of potential nuclear accidents in France. It concerns possible accidents involving pressurized water reactors leading to radioactive releases in the environment. These accidents have been grouped in two accident families called: severe accidents and major accidents. Two model scenarios have been selected to represent each of these families. The report discusses the general methodology of nuclear accident cost estimation. The crucial point is that all cost should be considered: if not, the cost is underestimated which can lead to negative consequences for the value attributed to safety and for crisis preparation. As a result, the overall cost comprises many components: the most well-known is offsite radiological costs, but there are many others. The proposed estimates have thus required using a diversity of methods which are described in this report. Figures are presented at the end of this report. Among other things, they show that purely radiological costs only represent a non-dominant part of foreseeable economic consequences

ENVIRONMENTAL ASSESSMENT METHODOLOGY FOR THE NUCLEAR FUEL CYCLE

Energy Technology Data Exchange (ETDEWEB)

Brenchley, D. L.; Soldat, J. K.; McNeese, J. A.; Watson, E. C.

1977-07-01

This report describes the methodology for determining where environmental control technology is required for the nuclear fuel cycle. The methodology addresses routine emission of chemical and radioactive effluents, and applies to mining, milling, conversion, enrichment, fuel fabrication, reactors (LWR and BWR) and fuel reprocessing. Chemical and radioactive effluents are evaluated independently. Radioactive effluents are evaluated on the basis of maximum exposed individual dose and population dose calculations for a 1-year emission period and a 50-year commitment. Sources of radionuclides for each facility are then listed according to their relative contribution to the total calculated dose. Effluent, ambient and toxicology standards are used to evaluate the effect of chemical effluents. First, each chemical and source configuration is determined. Sources are tagged if they exceed existirrg standards. The combined effect of all chemicals is assessed for each facility. If the additive effects are unacceptable, then additional control technology is recommended. Finally, sources and their chemicals at each facility are ranked according to their relative contribution to the ambient pollution level. This ranking identifies those sources most in need of environmental control.

Using HABIT to Establish the Chemicals Analysis Methodology for Maanshan Nuclear Power Plant

OpenAIRE

J. R. Wang; S. W. Chen; Y. Chiang; W. S. Hsu; J. H. Yang; Y. S. Tseng; C. Shih

2017-01-01

In this research, the HABIT analysis methodology was established for Maanshan nuclear power plant (NPP). The Final Safety Analysis Report (FSAR), reports, and other data were used in this study. To evaluate the control room habitability under the CO2 storage burst, the HABIT methodology was used to perform this analysis. The HABIT result was below the R.G. 1.78 failure criteria. This indicates that Maanshan NPP habitability can be maintained. Additionally, the sensitivity study of the paramet...

Spent Nuclear Fuel Transportation Risk Assessment Methodology for Homeland Security

International Nuclear Information System (INIS)

Teagarden, Grant A.; Canavan, Kenneth T.; Nickell, Robert E.

2006-01-01

In response to increased interest in risk-informed decision making regarding terrorism, EPRI was selected by U.S. DHS and ASME to develop and demonstrate a nuclear sector specific methodology for owner / operators to utilize in performing a Risk Analysis and Management for Critical Asset Protection (RAMCAP) assessment for the transportation of spent nuclear fuel (SNF). The objective is to characterize SNF transportation risk for risk management opportunities and to provide consistent information for DHS decision making. The method uses a characterization of risk as a function of Consequence, Vulnerability, and Threat. Worst reasonable case scenarios characterize risk for a benchmark set of threats and consequence types. A trial application was successfully performed and implementation is underway by one utility. (authors)

Validation of seismic soil structure interaction (SSI) methodology for a UK PWR nuclear power station

International Nuclear Information System (INIS)

Llambias, J.M.

1993-01-01

The seismic loading information for use in the seismic design of equipment and minor structures within a nuclear power plant is determined from a dynamic response analysis of the building in which they are located. This dynamic response analysis needs to capture the global response of both the building structure and adjacent soil and is commonly referred to as a soil structure interaction (SSI) analysis. NNC have developed a simple and cost effective methodology for the seismic SSI analysis of buildings in a PWR nuclear power station at a UK soft site. This paper outlines the NNC methodology and describes the approach adopted for its validation

Methodology of shielding calculation for nuclear reactors

International Nuclear Information System (INIS)

Maiorino, J.R.; Mendonca, A.G.; Otto, A.C.; Yamaguchi, Mitsuo

1982-01-01

A methodology of calculation that coupling a serie of computer codes in a net that make the possibility to calculate the radiation, neutron and gamma transport, is described, for deep penetration problems, typical of nuclear reactor shielding. This net of calculation begining with the generation of constant multigroups, for neutrons and gamma, by the AMPX system, coupled to ENDF/B-IV data library, the transport calculation of these radiations by ANISN, DOT 3.5 and Morse computer codes, up to the calculation of absorbed doses and/or equivalents buy SPACETRAN code. As examples of the calculation method, results from benchmark n 0 6 of Shielding Benchmark Problems - ORNL - RSIC - 25, namely Neutron and Secondary Gamma Ray fluence transmitted through a Slab of Borated Polyethylene, are presented. (Author) [pt

Introduction to the use of the INPRO methodology in a nuclear energy system assessment. A report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Nuclear Information System (INIS)

2010-01-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in 2001 on the basis of an IAEA General Conference resolution in 2000 (GC(44)/RES/21). INPRO activities have since that time been continuously endorsed by resolutions of the IAEA General Conference and by the General Assembly of the United Nations. The objectives of INPRO are to: Help ensure that nuclear energy is available to contribute, in a sustainable manner, to the goal of meeting energy needs in the 21st century; Bring together technology holders and users so that they can jointly consider the international and national actions required to ensure the sustainability of nuclear energy through innovations in technology and/or institutional arrangements. To fulfil these objectives, INPRO developed a set of basic principles, user requirements and criteria, along with an assessment method, which are the basis of the INPRO methodology for evaluation of the sustainability of innovative nuclear energy systems. To provide additional guidance in using the INPRO methodology, the nine volume INPRO Manual was developed; it consists of an overview volume and eight volumes covering the areas of economics, institutional measures (infrastructure), waste management, proliferation resistance, physical protection, environment (including the impact of stressors and the availability of resources), reactor safety, and the safety of nuclear fuel cycle facilities. To assist Member States in applying the INPRO methodology, the nuclear energy system assessment (NESA) support package is being developed. This includes a database (containing input data for assessment), provision of training courses in the INPRO methodology and examples of comprehensive assessments. This publication provides guidance on how a variety of potential users, including nuclear technology developers, experienced users and prospective first time nuclear technology users (newcomers) can apply the INPRO methodology for

Development of the methodology for application of revised source term to operating nuclear power plants in Korea

International Nuclear Information System (INIS)

Kang, M.S.; Kang, P.; Kang, C.S.; Moon, J.H.

2004-01-01

Considering the current trend in applying the revised source term proposed by NUREG-1465 to the nuclear power plants in the U.S., it is expected that the revised source term will be applied to the Korean operating nuclear power plants in the near future, even though the exact time can not be estimated. To meet the future technical demands, it is necessary to prepare the technical system including the related regulatory requirements in advance. In this research, therefore, it is intended to develop the methodology to apply the revised source term to operating nuclear power plants in Korea. Several principles were established to develop the application methodologies. First, it is not necessary to modify the existing regulations about source term (i.e., any back-fitting to operating nuclear plants is not necessary). Second, if the pertinent margin of safety is guaranteed, the revised source term suggested by NUREG-1465 may be useful to full application. Finally, a part of revised source term could be selected to application based on the technical feasibility. As the results of this research, several methodologies to apply the revised source term to the Korean operating nuclear power plants have been developed, which include: 1) the selective (or limited) application to use only some of all the characteristics of the revised source term, such as release timing of fission products and chemical form of radio-iodine and 2) the full application to use all the characteristics of the revised source term. The developed methodologies are actually applied to Ulchin 9 and 4 units and their application feasibilities are reviewed. The results of this research are used as either a manual in establishing the plan and the procedure for applying the revised source term to the domestic nuclear plant from the utility's viewpoint; or a technical basis of revising the related regulations from the regulatory body's viewpoint. The application of revised source term to operating nuclear

Recent developments in methodology for dynamic qualification of nuclear plant equipment

International Nuclear Information System (INIS)

Kana, D.D.; Pomerening, D.J.

1984-01-01

Dynamic qualification of nuclear plant electrical and mechanical equipment is performed basically under guidelines given in IEEE Standards 323 and 344, and a variety of NRC regulatory guides. Over the last fifteen years qualification methodology prescribed by these documents has changed significantly as interpretations, equipment capability, and imagination of the qualification engineers have progressed. This progress has been sparked by concurrent NRC and industry sponsored research programs that have identified anomalies and developed new methodologies for resolving them. Revisions of the standards have only resulted after a lengthy debate of all such new information and subsequent judgment of its validity. The purpose of this paper is to review a variety of procedural improvements and developments in qualification methodology that are under current consideration as revisions to the standards. Many of the improvements and developments have resulted from recent research programs. All are very likely to appear in one type of standard or another in the near future

Proposal of methodology of tsunami accident sequence analysis induced by earthquake using DQFM methodology

International Nuclear Information System (INIS)

Muta, Hitoshi; Muramatsu, Ken

2017-01-01

Since the Fukushima-Daiichi nuclear power station accident, the Japanese regulatory body has improved and upgraded the regulation of nuclear power plants, and continuous effort is required to enhance risk management in the mid- to long term. Earthquakes and tsunamis are considered as the most important risks, and the establishment of probabilistic risk assessment (PRA) methodologies for these events is a major issue of current PRA. The Nuclear Regulation Authority (NRA) addressed the PRA methodology for tsunamis induced by earthquakes, which is one of the methodologies that should be enhanced step by step for the improvement and maturity of PRA techniques. The AESJ standard for the procedure of seismic PRA for nuclear power plants in 2015 provides the basic concept of the methodology; however, details of the application to the actual plant PRA model have not been sufficiently provided. This study proposes a detailed PRA methodology for tsunamis induced by earthquakes using the DQFM methodology, which contributes to improving the safety of nuclear power plants. Furthermore, this study also states the issues which need more research. (author)

Estimating the potential impacts of a nuclear reactor accident: methodology and case studies

International Nuclear Information System (INIS)

Cartwright, J.V.; Beemiller, R.M.; Trott, E.A. Jr.; Younger, J.M.

1982-04-01

This monograph describes an industrial impact model that can be used to estimate the regional industry-specific impacts of disasters. Special attention is given to the impacts of possible nuclear reactor accidents. The monograph also presents three applications of the model. The impacts estimated in the case studies are based on (1) general information and reactor-specific data, supplied by the US Nuclear Regulatory Commission (NRC), (2) regional economic models derived from the Regional Input-Output Modeling System (RIMS II) developed at the Bureau of Economic Analysis (BEA), and (3) additional methodology developed especially for taking into account the unique characteristics of a nuclear reactor accident with respect to regional industrial activity

Radiochemical methodologies applied to analytical characterization of low and intermediate level wastes from nuclear power plants

International Nuclear Information System (INIS)

Monteiro, Roberto Pellacani G.; Júnior, Aluísio Souza R.; Kastner, Geraldo F.; Temba, Eliane S.C.; Oliveira, Thiago C. de; Amaral, Ângela M.; Franco, Milton B.

2017-01-01

The aim of this work is to present radiochemical methodologies developed at CDTN/CNEN in order to answer a program for isotopic inventory of radioactive wastes from Brazilian Nuclear Power Plants. In this program some radionuclides, 3 H, 14 C, 55 Fe, 59 Ni, 63 Ni, 90 Sr, 93 Zr, 94 Nb, 99 Tc, 129 I, 235 U, 238 U, 238 Pu, 239 + 240 Pu, 241 Pu, 242 Pu, 241 Am, 242 Cm e 243 + 244 Cm, were determined in Low Level Wastes (LLW) and Intermediate Level Wastes (ILW) and a protocol of analytical methodologies based on radiochemical separation steps and spectrometric and nuclear techniques was established. (author)

Research on Methodology to Prioritize Critical Digital Assets based on Nuclear Risk Assessment

Energy Technology Data Exchange (ETDEWEB)

Kim, Wonjik; Kwon, Kookheui; Kim, Hyundoo [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2016-10-15

Digital systems are used in nuclear facilities to monitor and control various types of field devices, as well as to obtain and store vital information. Therefore, it is getting important for nuclear facilities to protect digital systems from cyber-attack in terms of safety operation and public health since cyber compromise of these systems could lead to unacceptable radiological consequences. Based on KINAC/RS-015 which is a cyber security regulatory standard, regulatory activities for cyber security at nuclear facilities generally focus on critical digital assets (CDAs) which are safety, security, and emergency preparedness related digital assets. Critical digital assets are estimated over 60% among all digital assets in a nuclear power plant. Therefore, it was required to prioritize critical digital assets to improve efficiency of regulation and implementation. In this paper, the research status on methodology development to prioritize critical digital assets based on nuclear risk assessment will be introduced. In this paper, to derive digital asset directly affect accident, PRA results (ET, FT, and minimal cut set) are analyzed. According to result of analysis, digital systems related to CD are derived ESF-CCS (safety-related component control system) and Process-CCS (non-safety-related component control system) as well as Engineered Safety Features Actuation System (ESFAS). These digital assets can be identified Vital Digital Asset (VDA). Hereafter, to develop general methodology which was identified VDA related to accident among CDAs, (1) method using result of minimal cut set in PRA model will be studied and (2) method quantifying result of Digital I and C PRA which is performed to reflect all digital cabinet related to system in FT will be studied.

Research on Methodology to Prioritize Critical Digital Assets based on Nuclear Risk Assessment

International Nuclear Information System (INIS)

Kim, Wonjik; Kwon, Kookheui; Kim, Hyundoo

2016-01-01

Digital systems are used in nuclear facilities to monitor and control various types of field devices, as well as to obtain and store vital information. Therefore, it is getting important for nuclear facilities to protect digital systems from cyber-attack in terms of safety operation and public health since cyber compromise of these systems could lead to unacceptable radiological consequences. Based on KINAC/RS-015 which is a cyber security regulatory standard, regulatory activities for cyber security at nuclear facilities generally focus on critical digital assets (CDAs) which are safety, security, and emergency preparedness related digital assets. Critical digital assets are estimated over 60% among all digital assets in a nuclear power plant. Therefore, it was required to prioritize critical digital assets to improve efficiency of regulation and implementation. In this paper, the research status on methodology development to prioritize critical digital assets based on nuclear risk assessment will be introduced. In this paper, to derive digital asset directly affect accident, PRA results (ET, FT, and minimal cut set) are analyzed. According to result of analysis, digital systems related to CD are derived ESF-CCS (safety-related component control system) and Process-CCS (non-safety-related component control system) as well as Engineered Safety Features Actuation System (ESFAS). These digital assets can be identified Vital Digital Asset (VDA). Hereafter, to develop general methodology which was identified VDA related to accident among CDAs, (1) method using result of minimal cut set in PRA model will be studied and (2) method quantifying result of Digital I and C PRA which is performed to reflect all digital cabinet related to system in FT will be studied

Assessing environmental and health impact of the nuclear fuel cycle. Methodology and application to prospective actinides recycling options

International Nuclear Information System (INIS)

Garzenne, Claude; Grouiller, Jean-Paul; Le Boulch, Denis

2005-01-01

French Industrial Companies: EDF, AREVA (COGEMA and FRAMATOME-ANP), associated with ANDRA, the organization in charge of the waste management in France, and Public Research Institute CEA and IRSN, involved in the nuclear waste management, have developed in collaboration a methodology intended to assess the environmental and health impact of the nuclear fuel cycle. This methodology, based on fuel cycle simulation, Life Cycle Analysis, and Impact Studies of each fuel cycle facilities, has been applied to a set of nuclear scenarios covering a very contrasted range of waste management options, in order to characterize the effect of High Level Waste transmutation, and to estimate to what extent it could contribute to reduce their overall impact on health and environment. The main conclusion we could draw from this study is that it is not possible to discriminate, as far as health and environmental impacts are concerned, nuclear scenarios implementing very different levels of HLW transmutation, representative of the whole range of available options. The main limitation of this work is due to the hypothesis of normal behavior of all fuel cycle facilities: main future improvement of the methodology would be to take the accidental risk into account. (author)

Development of the GO-FLOW reliability analysis methodology for nuclear reactor system

International Nuclear Information System (INIS)

Matsuoka, Takeshi; Kobayashi, Michiyuki

1994-01-01

Probabilistic Safety Assessment (PSA) is important in the safety analysis of technological systems and processes, such as, nuclear plants, chemical and petroleum facilities, aerospace systems. Event trees and fault trees are the basic analytical tools that have been most frequently used for PSAs. Several system analysis methods can be used in addition to, or in support of, the event- and fault-tree analysis. The need for more advanced methods of system reliability analysis has grown with the increased complexity of engineered systems. The Ship Research Institute has been developing a new reliability analysis methodology, GO-FLOW, which is a success-oriented system analysis technique, and is capable of evaluating a large system with complex operational sequences. The research has been supported by the special research fund for Nuclear Technology, Science and Technology Agency, from 1989 to 1994. This paper describes the concept of the Probabilistic Safety Assessment (PSA), an overview of various system analysis techniques, an overview of the GO-FLOW methodology, the GO-FLOW analysis support system, procedure of treating a phased mission problem, a function of common cause failure analysis, a function of uncertainty analysis, a function of common cause failure analysis with uncertainty, and printing out system of the results of GO-FLOW analysis in the form of figure or table. Above functions are explained by analyzing sample systems, such as PWR AFWS, BWR ECCS. In the appendices, the structure of the GO-FLOW analysis programs and the meaning of the main variables defined in the GO-FLOW programs are described. The GO-FLOW methodology is a valuable and useful tool for system reliability analysis, and has a wide range of applications. With the development of the total system of the GO-FLOW, this methodology has became a powerful tool in a living PSA. (author) 54 refs

Review of experience with plutonium exposure assessment methodologies at the nuclear fuel reprocessing site of British Nuclear Fuels plc

International Nuclear Information System (INIS)

Strong, R.

1988-01-01

British Nuclear Fuels plc and its predecessors have provided a complete range of nuclear fuel services to utilities in the UK and elsewhere for more than 30 years. Over 30,000 ton of Magnox and Oxide fuel have been reprocessed at Sellafield. During this time substantial experience has accumulated of methodologies for the assessment of exposure to actinides, mainly isotopes of plutonium. For most of the period monitoring of personnel included assessment of systemic uptake deduced from plutonium-in-urine results. The purpose of the paper is to present some conclusions of contemporary work in this area

Methodology to evaluate the site standard seismic motion for a nuclear facility

International Nuclear Information System (INIS)

Soares, W.A.

1983-03-01

An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic priciples of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; avalable methodologies and recommended procedures to evaluate the site standard seismic motion. (E.G.) [pt

Methodology for determining acceptable residual radioactive contamination levels at decommissioned nuclear facilities/sites

International Nuclear Information System (INIS)

Watson, E.C.; Kennedy, W.E. Jr.; Hoenes, G.R.; Waite, D.A.

1979-01-01

The ultimate disposition of decommissioned nuclear facilities and their surrrounding sites depends upon the degree and type of residual contamination. Examination of existing guidelines and regulations has led to the conclusion that there is a need for a general method to derive residual radioactive contamination levels that are acceptable for public use of any decommissioned nuclear facility or site. This paper describes a methodology for determining acceptable residual radioactive contamination levels based on the concept of limiting the annual dose to members of the public. It is not the purpose of this paper to recommend or even propose dose limits for the exposure of the public to residual radioactive contamination left at decommissioned nuclear facilities or sites. Unrestricted release of facilities and/or land is based on the premise that the potential annual dose to any member of the public using this property from all possible exposure pathways will not exceed appropriate limits as may be defined by Federal regulatory agencies. For decommissioned land areas, consideration should be given to people living directly on previously contaminated areas, growing crops, grazing food animals and using well water. Mixtures of radionuclides in the residual contamination representative of fuel reprocessing plants, light water reactors and their respective sites are presented. These mixtures are then used to demonstrate the methodology. Example acceptable residual radioactive contamination levels, based on an assumed maximum annual dose of one millirem, are calculated for several selected times following shutdown of a facility. It is concluded that the methodology presented in this paper results in defensible acceptable residual contamination levels that are directly relatable to risk assessment with the proviso that an acceptable limit to the maximum annual dose will be established. (author)

Methodology to evaluate the site standard seismic motion to a nuclear facility

International Nuclear Information System (INIS)

Soares, W.A.

1983-01-01

For the seismic design of nuclear facilities, the input motion is normally defined by the predicted maximum ground horizontal acceleration and the free field ground response spectrum. This spectrum is computed on the basis of records of strong motion earthquakes. The pair maximum acceleration-response spectrum is called the site standard seismic motion. An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic principles of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; available methodologies and recommended procedures to evaluate the site standard seismic motion. (Author) [pt

Improved best estimate plus uncertainty methodology including advanced validation concepts to license evolving nuclear reactors

International Nuclear Information System (INIS)

Unal, Cetin; Williams, Brian; McClure, Patrick; Nelson, Ralph A.

2010-01-01

Many evolving nuclear energy programs plan to use advanced predictive multi-scale multi-physics simulation and modeling capabilities to reduce cost and time from design through licensing. Historically, the role of experiments was primary tool for design and understanding of nuclear system behavior while modeling and simulation played the subordinate role of supporting experiments. In the new era of multi-scale multi-physics computational based technology development, the experiments will still be needed but they will be performed at different scales to calibrate and validate models leading predictive simulations. Cost saving goals of programs will require us to minimize the required number of validation experiments. Utilization of more multi-scale multi-physics models introduces complexities in the validation of predictive tools. Traditional methodologies will have to be modified to address these arising issues. This paper lays out the basic aspects of a methodology that can be potentially used to address these new challenges in design and licensing of evolving nuclear technology programs. The main components of the proposed methodology are verification, validation, calibration, and uncertainty quantification. An enhanced calibration concept is introduced and is accomplished through data assimilation. The goal is to enable best-estimate prediction of system behaviors in both normal and safety related environments. To achieve this goal requires the additional steps of estimating the domain of validation and quantification of uncertainties that allow for extension of results to areas of the validation domain that are not directly tested with experiments, which might include extension of the modeling and simulation (M and S) capabilities for application to full-scale systems. The new methodology suggests a formalism to quantify an adequate level of validation (predictive maturity) with respect to required selective data so that required testing can be minimized for

Improved best estimate plus uncertainty methodology including advanced validation concepts to license evolving nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Unal, Cetin [Los Alamos National Laboratory; Williams, Brian [Los Alamos National Laboratory; Mc Clure, Patrick [Los Alamos National Laboratory; Nelson, Ralph A [IDAHO NATIONAL LAB

2010-01-01

Many evolving nuclear energy programs plan to use advanced predictive multi-scale multi-physics simulation and modeling capabilities to reduce cost and time from design through licensing. Historically, the role of experiments was primary tool for design and understanding of nuclear system behavior while modeling and simulation played the subordinate role of supporting experiments. In the new era of multi-scale multi-physics computational based technology development, the experiments will still be needed but they will be performed at different scales to calibrate and validate models leading predictive simulations. Cost saving goals of programs will require us to minimize the required number of validation experiments. Utilization of more multi-scale multi-physics models introduces complexities in the validation of predictive tools. Traditional methodologies will have to be modified to address these arising issues. This paper lays out the basic aspects of a methodology that can be potentially used to address these new challenges in design and licensing of evolving nuclear technology programs. The main components of the proposed methodology are verification, validation, calibration, and uncertainty quantification. An enhanced calibration concept is introduced and is accomplished through data assimilation. The goal is to enable best-estimate prediction of system behaviors in both normal and safety related environments. To achieve this goal requires the additional steps of estimating the domain of validation and quantification of uncertainties that allow for extension of results to areas of the validation domain that are not directly tested with experiments, which might include extension of the modeling and simulation (M&S) capabilities for application to full-scale systems. The new methodology suggests a formalism to quantify an adequate level of validation (predictive maturity) with respect to required selective data so that required testing can be minimized for cost

Abnormal condition and events analysis for instrumentation and control systems. Volume 1: Methodology for nuclear power plant digital upgrades. Final report

International Nuclear Information System (INIS)

McKemy, S.; Marcelli, M.; Boehmer, N.; Crandall, D.

1996-01-01

The ACES project was initiated to identify a cost-effective methodology for addressing abnormal conditions and events (ACES) in digital upgrades to nuclear power plant systems, as introduced by IEEE Standard 7-4.3.2-1993. Several methodologies and techniques currently in use in the defense, aerospace, and other communities for the assurance of digital safety systems were surveyed, and although several were shown to possess desirable qualities, non sufficiently met the needs of the nuclear power industry. This report describes a tailorable methodology for performing ACES analysis that is based on the more desirable aspects of the reviewed methodologies and techniques. The methodology is applicable to both safety- and non-safety-grade systems, addresses hardware, software, and system-level concerns, and can be applied in either a lifecycle or post-design timeframe. Employing this methodology for safety systems should facilitate the digital upgrade licensing process

Analytical methodology for optimization of waste management scenarios in nuclear installation decommissioning process - 16148

International Nuclear Information System (INIS)

Zachar, Matej; Necas, Vladimir; Daniska, Vladimir; Rehak, Ivan; Vasko, Marek

2009-01-01

The nuclear installation decommissioning process is characterized by production of large amount of various radioactive and non-radioactive waste that has to be managed, taking into account its physical, chemical, toxic and radiological properties. Waste management is considered to be one of the key issues within the frame of the decommissioning process. During the decommissioning planning period, the scenarios covering possible routes of materials release into the environment and radioactive waste disposal, should be discussed and evaluated. Unconditional and conditional release to the environment, long-term storage at the nuclear site, near surface or deep geological disposal and relevant material management techniques for achieving the final status should be taken into account in the analysed scenarios. At the level of the final decommissioning plan, it is desirable to have the waste management scenario optimized for local specific facility conditions taking into account a national decommissioning background. The analytical methodology for the evaluation of decommissioning waste management scenarios, presented in the paper, is based on the materials and radioactivity flow modelling, which starts from waste generation activities like pre-dismantling decontamination, selected methods of dismantling, waste treatment and conditioning, up to materials release or conditioned radioactive waste disposal. The necessary input data for scenarios, e.g. nuclear installation inventory database (physical and radiological data), waste processing technologies parameters or material release and waste disposal limits, have to be considered. The analytical methodology principles are implemented into the standardised decommissioning parameters calculation code OMEGA, developed in the DECOM company. In the paper the examples of the methodology implementation for the scenarios optimization are presented and discussed. (authors)

State regulation of nuclear sector: comparative study of Argentina and Brazil models; Regulacao estatal do setor nuclear: estudo comparativo dos modelos da Argentina e do Brasil

Energy Technology Data Exchange (ETDEWEB)

Monteiro Filho, Joselio Silveira

2004-08-01

This research presents a comparative assessment of the regulation models of the nuclear sector in Argentina - under the responsibility of the Autoridad Regulatoria Nuclear (ARN), and Brazil - under the responsibility of Comissao Nacional de Energia Nuclear (CNEN), trying to identify which model is more adequate aiming the safe use of nuclear energy. Due to the methodology adopted, the theoretical framework resulted in criteria of analysis that corresponds to the characteristics of the Brazilian regulatory agencies created for other economic sector during the State reform staring in the middle of the nineties. Later, these criteria of analysis were used as comparison patterns between the regulation models of the nuclear sectors of Argentina and Brazil. The comparative assessment showed that the regulatory structure of the nuclear sector in Argentina seems to be more adequate, concerning the safe use of nuclear energy, than the model adopted in Brazil by CNEN, because its incorporates the criteria of functional, institutional and financial independence, competence definitions, technical excellence and transparency, indispensable to the development of its functions with autonomy, ethics, exemption and agility. (author)

Application of a methodology to determine priorities for nuclear power plant safety issues

International Nuclear Information System (INIS)

Daling, P.M.

1988-01-01

The Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) is sponsoring a research program to determine priorities of nuclear power plant safety issues. A methodology has been developed at the Pacific Northwest Laboratory (PNL) to provide technical assistance in the development of risk and cost estimates for implementing resolutions to the safety issues. The information development methods are intended to provide the NRC with a consistent level of information for use in ranking the issues. The NRC uses this information, along with judgmental factors, to rank the issues for further consideration by the NRC staff. The primary purpose of the priority rankings are to assist in the allocation of resources to issues that have high potential for reducing public risk as well as to remove issues from further consideration that have little safety significance

Radiochemical methodologies applied to analytical characterization of low and intermediate level wastes from nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Monteiro, Roberto Pellacani G.; Júnior, Aluísio Souza R.; Kastner, Geraldo F.; Temba, Eliane S.C.; Oliveira, Thiago C. de; Amaral, Ângela M.; Franco, Milton B., E-mail: rpgm@cdtn.br, E-mail: reisas@cdtn.br, E-mail: gfk@cdtn.br, E-mail: esct@cdtn.br, E-mail: tco@cdtn.br, E-mail: ama@cdtn.br, E-mail: francom@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

The aim of this work is to present radiochemical methodologies developed at CDTN/CNEN in order to answer a program for isotopic inventory of radioactive wastes from Brazilian Nuclear Power Plants. In this program some radionuclides, {sup 3}H, {sup 14}C, {sup 55}Fe, {sup 59}Ni, {sup 63}Ni, {sup 90}Sr, {sup 93}Zr, {sup 94}Nb, {sup 99}Tc, {sup 129}I, {sup 235}U, {sup 238}U, {sup 238}Pu, {sup 239}+{sup 240}Pu, {sup 241}Pu, {sup 242}Pu, {sup 241}Am, {sup 242}Cm e {sup 243}+{sup 244}Cm, were determined in Low Level Wastes (LLW) and Intermediate Level Wastes (ILW) and a protocol of analytical methodologies based on radiochemical separation steps and spectrometric and nuclear techniques was established. (author)

Applications of a methodology for the analysis of learning trends in nuclear power plants

International Nuclear Information System (INIS)

Cho, Hang Youn; Choi, Sung Nam; Yun, Won Yong

1995-01-01

A methodology is applied to identify the learning trend related to the safety and availability of U.S. commercial nuclear power plants. The application is intended to aid in reducing likelihood of human errors. To assure that the methodology can be easily adapted to various types of classification schemes of operation data, a data bank classified by the Transient Analysis Classification and Evaluation(TRACE) scheme is selected for the methodology. The significance criteria for human-initiated events affecting the systems and for events caused by human deficiencies were used. Clustering analysis was used to identify the learning trend in multi-dimensional histograms. A computer code is developed based on the K-Means algorithm and applied to find the learning period in which error rates are monotonously decreasing with plant age

Methodological considerations in evaluating a proliferation resistance of innovative nuclear energy systems

International Nuclear Information System (INIS)

Kikuchi, Masahiro; Takaki, Naoyuki; Murajiri, Masahiro; Nakagome, Yoshihiro; Tokiwai, Moriyasu

2004-01-01

Over 25 years ago, INFCE studied the evaluation methodology of proliferation resistance. Recently, INPRO and GEN-IV coordinated by the IAEA and the USDOE respectively seek an appropriate innovative fuel cycle system for next generation that is furnished safer, sustainable, economical and reliable features. The evaluation methodology of the proliferation resistance is also assigned as an essential part of both studies. The IAEA established and has been strictly implementing the verification measures with accurate material accountancy system from the early of the 1970s in order to detect diversion of plutonium that is individually separated from irradiated nuclear material and recycled as MOX fuel. This paper firstly identifies the impedibility of intrinsic features of innovative fuel cycles and the safeguardability of selected nonproliferation measures as two individual essential parameters for evaluation of a proliferation resistance capability. As a next step, this paper also shows methodological considerations in evaluating the proliferation resistance levels as a multiple model of several clusters that are identified the ability of each parameter. (author)

Age-dependent risk-based methodology and its application to prioritization of nuclear power plant components and to maintenance for managing aging using PRAs

International Nuclear Information System (INIS)

Levy, I.S.; Vesely, W.E.

1990-01-01

This paper is based on a study to demonstrate several important ways that the age-dependent risk-based methodology developed by the Nuclear Plant Aging Research (NPAR) Program may be applied to resolving important issues related to the aging of nuclear power plant systems, structures, and components (SSCs). The study was sponsored by the NPAR Program of the Division of Engineering, Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission (NRC). Initiated on the basis of a Users Need Request, the age-dependent risk-based methodology has been under development by the NPAR Program for several years. In this methodology, the time-dependent change in a component's risk contribution is the product of two factors: (1) the risk importance of the component (e.g., the change in its risk contribution when it is assumed to be totally unavailable to perform its intended safety function) and (2) the change in its unavailability with time. This change in the component's unavailability with time is a function of the component's aging rate and plant inspection and maintenance practices. The methodology permits evaluations of the age-dependent risk contributions from both single- and multiple-components. Principal results and conclusions generated by the methodology demonstrations are discussed

Eliciting and communicating expert judgments: Methodology and application to nuclear safety

International Nuclear Information System (INIS)

Winterfeldt, D. von

1989-01-01

The most ambitious and certainly the most extensive formal expert judgment process was the elicitation of numerous events and uncertain quantities for safety issues in five nuclear power plants in the U.S. The general methodology for formal expert elicitations are described. An overview of the expert elicitation process of NUREG 1150 is provided and the elicitation of probabilities for the interfacing systems loss of coolant accident LOCA (ISL) in PWRs is given as an example of this elicitation process. Some lessons learned from this study are presented. (DG)

A methodology to simulate the cutting process for a nuclear dismantling simulation based on a digital manufacturing platform

International Nuclear Information System (INIS)

Hyun, Dongjun; Kim, Ikjune; Lee, Jonghwan; Kim, Geun-Ho; Jeong, Kwan-Seong; Choi, Byung Seon; Moon, Jeikwon

2017-01-01

Highlights: • Goal is to provide existing tech. with cutting function handling dismantling process. • Proposed tech. can handle various cutting situations in the dismantlement activities. • Proposed tech. can be implemented in existing graphical process simulation software. • Simulation results have demonstrated that the proposed technology achieves its goal. • Proposed tech. enlarges application of graphic simulation into dismantlement activity. - Abstract: This study proposes a methodology to simulate the cutting process in a digital manufacturing platform for the flexible planning of nuclear facility decommissioning. During the planning phase of decommissioning, visualization and verification using process simulation can be powerful tools for the flexible planning of the dismantling process of highly radioactive, large and complex nuclear facilities. However, existing research and commercial solutions are not sufficient for such a situation because complete segmented digital models for the dismantling objects such as the reactor vessel, internal assembly, and closure head must be prepared before the process simulation. The preparation work has significantly impeded the broad application of process simulation due to the complexity and workload. The methodology of process simulation proposed in this paper can flexibly handle various dismantling processes including repetitive object cuttings over heavy and complex structures using a digital manufacturing platform. The proposed methodology, which is applied to dismantling scenarios of a Korean nuclear power plant in this paper, is expected to reduce the complexity and workload of nuclear dismantling simulations.

Neutron detection of the Triga Mark III reactor, using nuclear track methodology

Energy Technology Data Exchange (ETDEWEB)

Espinosa, G., E-mail: espinosa@fisica.unam.mx; Golzarri, J. I. [Instituto de Física, Universidad Nacional Autónoma de México Circuito de la Investigación Científica, Ciudad Universitaria. México, DF (Mexico); Raya-Arredondo, R.; Cruz-Galindo, S. [Instituto Nacional de Investigaciones Nucleares (Mexico); Sajo-Bohus, L. [Universidad Simón Bolivar, Laboratorio de Física Nuclear, Caracas (Venezuela, Bolivarian Republic of)

2015-07-23

Nuclear Track Methodology (NTM), based on the neutron-proton interaction is one often employed alternative for neutron detection. In this paper we apply NTM to determine the Triga Mark III reactor operating power and neutron flux. The facility nuclear core, loaded with 85 Highly Enriched Uranium as fuel with control rods in a demineralized water pool, provide a neutron flux around 2 × 10{sup 12} n cm{sup −2} s{sup −1}, at the irradiation channel TO-2. The neutron field is measured at this channel, using Landauer{sup ®} PADC as neutron detection material, covered by 3 mm Plexiglas{sup ®} as converter. After exposure, plastic detectors were chemically etched to make observable the formed latent tracks induced by proton recoils. The track density was determined by a custom made Digital Image Analysis System. The resulting average nuclear track density shows a direct proportionality response for reactor power in the range 0.1-7 kW. We indicate several advantages of the technique including the possibility to calibrate the neutron flux density measured at low reactor power.

Safety Assessment for Decommissioning of Nuclear Facilities - From Methodology to the Use of Results in Decision Making

International Nuclear Information System (INIS)

Batandjieva, B.; Ferch, R.; Joubert, A.; Kaulard, J.; Manson, P.; Percival, K.; Thierfeldt, St.

2008-01-01

The safety assessment of operational facilities in the nuclear industry is well understood and methodologies have been developed and refined over several decades. Similarly safety assessment methodologies for near surface disposal facilities have been harmonized internationally during the last few years. There is however relatively less widespread and documented experience of safety assessment for decommissioning among Member States of the International Atomic Energy Agency (IAEA) and consequently there is less commonalty of approaches internationally. The importance of safety during decommissioning was further emphasized at the first review meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, and the Berlin Conference 'Safe Decommissioning for Nuclear Activities' (14-18 October 2002). As a consequence during its June 2004 meeting the IAEA Board of Governors approved an Action Plan on Decommissioning of nuclear Facilities that requested the Secretariat to 'establish a forum for the sharing and exchange of national information and experience on the application of safety assessment in the context of decommissioning and provide a means to convey this information to other interested parties, also drawing on the work of other international organizations in this area'. In response the IAEA launched the International Project Evaluation and Demonstration of Safety during Decommissioning of Nuclear Facilities (DeSa) in November 2004 with the following objectives: - To develop a harmonized approach to safety assessment and define the elements of safety assessment for decommissioning; - To investigate the practical applicability of the methodology and performance of safety assessments for the decommissioning of various types of facilities through a selected number of test cases; - To investigate approaches for review of safety assessments for decommissioning activities and the development of a regulatory

Development of a standard methodology for optimizing remote visual display for nuclear-maintenance tasks

International Nuclear Information System (INIS)

Clarke, M.M.; Garin, J.; Preston-Anderson, A.

1981-01-01

The aim of the present study is to develop a methodology for optimizing remote viewing systems for a fuel recycle facility (HEF) being designed at Oak Ridge National Laboratory (ORNL). An important feature of this design involves the Remotex concept: advanced servo-controlled master/slave manipulators, with remote television viewing, will totally replace direct human contact with the radioactive environment. Therefore, the design of optimal viewing conditions is a critical component of the overall man/machine system. A methodology has been developed for optimizing remote visual displays for nuclear maintenance tasks. The usefulness of this approach has been demonstrated by preliminary specification of optimal closed circuit TV systems for such tasks

Lessons Learned from Nuclear Energy System Assessments (NESA) Using the INPRO Methodology. A Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Nuclear Information System (INIS)

2009-11-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in 2001 on the basis of a resolution of the IAEA General Conference in 2000 (GC(44)/RES/21). INPRO activities have since been continuously endorsed by resolutions of IAEA General Conferences and by the General Assembly of the United Nations. The objectives of INPRO are to: Help ensure that nuclear energy is available to contribute, in a sustainable manner, to meeting the energy needs of the 21st century; Bring together technology holders and users so that they can consider jointly the international and national actions required for achieving desired innovations in nuclear reactors and fuel cycles. INPRO is proceeding in steps. In its first step, referred to as Phase 1, 2001 to 2006, INPRO developed a set of basic principles, user requirements and criteria together with an assessment method, which taken together, comprise the INPRO methodology for the evaluation of innovative nuclear energy systems. To provide additional guidance in using the INPRO methodology an INPRO Manual was developed; it is comprised of an overview volume and eight additional volumes covering the areas of economics, infrastructure, waste management, proliferation resistance, physical protection, environment, safety of reactors, and safety of the nuclear fuel cycle facilities. Based on a decision of the 9 INPRO steering committee in July 2006, INPRO has entered into Phase 2. This phase has three main directions of activity: methodology improvement, infrastructure/institutional aspects and collaborative projects. As of March 2009, INPRO had 28 members: Argentina, Armenia, Belarus, Belgium, Brazil, Bulgaria, Canada, Chile, China, Czech Republic, France, Germany, India, Indonesia, Japan, Republic of Korea, Morocco, Netherlands, Pakistan, the Russian Federation, Slovakia, South Africa, Spain, Switzerland, Turkey, Ukraine, United States of America and the European Commission. This IAEA-TECDOC is part of

Transposition of the SQUG methodology to the Belgian NPP(nuclear power station)

International Nuclear Information System (INIS)

Detroux, P.; Aelbrecht, D.; Naisse, J.C.; Greer, J.L.

1991-01-01

The units of a Belgian Nuclear PowerStation had to be seismically reassessed after ten years of operation because the seismic requirements were upgraded from 0.1g to 0.17g free field ground acceleration. Seismic requalification of the active equipment was a critical problem as the current classical methods were too conservative and their application would have lead to unacceptable replacement or reinforcement of a lot of equipment. The approach based on the use of past experience of seismic behavior of non nuclear equipment was chosen; this methodology was developed by the Seismic Qualification Utility Group (SQUG); a group of U.S. utilities and had to be transposed to the Belgian N.P.P. This transposition is described in this paper. It affects different aspects of the methodology. First, the impact of specific requests of the Safety Authorities on the elaboration of the Safe Shutdown Equipment List (SSEL) shall be examined. Then it is explained why the tedious work of specific relay screening was avoided by taking advantage of initial design features for both Instrumentation and Control (I and C) and Electrical power distribution system; the impact on the Electrical SSEL is also described. Afterwards, it is presented how it was possible to conduct a specific existing seismic qualification at 0.1 g free field ground acceleration. Finally, the resolution of specific important problems that arose from the application of the SQUG methodology, is presented such as the definition of the grade level and the conservatism of the classical Amplified Floor Spectra (criterion 1), the calculation of the nozzle loads on mechanical equipment connected to long unbraced piping and the transfer of these loads to the anchorage. (author)

Application of project management methodology in design management of nuclear safety related structure

International Nuclear Information System (INIS)

Chen Mao

2004-01-01

This paper focuses on the application of project management methodology in the design management of Nuclear Safety Related Structure (NSRS), considering the design management features of its civil construction. Based on the experiences from the management of several projects, the project management triangle is proposed to be used in the management, to well treat the position of design interface in the project management. Some other management methods are also proposed

A Methodology for Safety Culture Impact Assessment

Energy Technology Data Exchange (ETDEWEB)

Han, Kiyoon; Jae, Moosung [Hanyang Univ., Seoul (Korea, Republic of)

2014-05-15

The purpose of this study is to develop methodology for assessing safety culture impact on nuclear power plants. A new methodology for assessing safety culture impact index has been developed and applied for the reference nuclear power plants. The developed SCII model might contribute to comparing the level of safety culture among nuclear power plants as well as to improving the safety of nuclear power plants. Safety culture is defined to be fundamental attitudes and behaviors of the plant staff which demonstrate that nuclear safety is the most important consideration in all activities conducted in nuclear power operation. Through several accidents of nuclear power plant including the Fukusima Daiichi in 2011 and Chernovyl accidents in 1986, the safety of nuclear power plant is emerging into a matter of interest. From the accident review report, it can be easily found out that safety culture is important and one of dominant contributors to accidents. However, the impact methodology for assessing safety culture has not been established analytically yet. It is difficult to develop the methodology for assessing safety culture impact quantitatively.

A Methodology for Safety Culture Impact Assessment

International Nuclear Information System (INIS)

Han, Kiyoon; Jae, Moosung

2014-01-01

The purpose of this study is to develop methodology for assessing safety culture impact on nuclear power plants. A new methodology for assessing safety culture impact index has been developed and applied for the reference nuclear power plants. The developed SCII model might contribute to comparing the level of safety culture among nuclear power plants as well as to improving the safety of nuclear power plants. Safety culture is defined to be fundamental attitudes and behaviors of the plant staff which demonstrate that nuclear safety is the most important consideration in all activities conducted in nuclear power operation. Through several accidents of nuclear power plant including the Fukusima Daiichi in 2011 and Chernovyl accidents in 1986, the safety of nuclear power plant is emerging into a matter of interest. From the accident review report, it can be easily found out that safety culture is important and one of dominant contributors to accidents. However, the impact methodology for assessing safety culture has not been established analytically yet. It is difficult to develop the methodology for assessing safety culture impact quantitatively

Development of a methodology for safety classification on a non-reactor nuclear facility illustrated using an specific example

International Nuclear Information System (INIS)

Scheuermann, F.; Lehradt, O.; Traichel, A.

2015-01-01

To realize the safety of personnel and environment systems and components of nuclear facilities are classified according to their potential danger into safety classes. Based on this classification different demands on the manufacturing quality result. The objective of this work is to present the standardized method developed by NUKEM Technologies Engineering Services for the categorization into the safety classes restricted to Non-reactor nuclear facilities (NRNF). Exemplary the methodology is used on the complex Russian normative system (four safety classes). For NRNF only the lower two safety classes are relevant. The classification into the lowest safety class 4 is accordingly if the maximum resulting dose following from clean-up actions in case of incidents/accidents remains below 20 mSv and the volume activity restrictions of set in NRB-99/2009 are met. The methodology is illustrated using an example. In short the methodology consists of: - Determination of the working time to remove consequences of incidents, - Calculation of the dose resulting from direct radiation and due to inhalation during these works. The application of this methodology avoids over-conservative approaches. As a result some previously higher classified equipment can be classified into the lower safety class.

Methodology for estimating reprocessing costs for nuclear fuels

International Nuclear Information System (INIS)

Carter, W.L.; Rainey, R.H.

1980-02-01

A technological and economic evaluation of reprocessing requirements for alternate fuel cycles requires a common assessment method and a common basis to which various cycles can be related. A methodology is described for the assessment of alternate fuel cycles utilizing a side-by-side comparison of functional flow diagrams of major areas of the reprocessing plant with corresponding diagrams of the well-developed Purex process as installed in the Barnwell Nuclear Fuel Plant (BNFP). The BNFP treats 1500 metric tons of uranium per year (MTU/yr). Complexity and capacity factors are determined for adjusting the estimated facility and equipment costs of BNFP to determine the corresponding costs for the alternate fuel cycle. Costs of capacities other than the reference 1500 MT of heavy metal per year are estimated by the use of scaling factors. Unit costs of reprocessed fuel are calculated using a discounted cash flow analysis for three economic bases to show the effect of low-risk, typical, and high-risk financing methods

Development of a methodology for the evaluation of radiation protection performance and management in nuclear power plants

International Nuclear Information System (INIS)

Schieber, Caroline; Bataille, Celine; Cordier, Gerard; Delabre, Herve; Jeannin, Bernard

2008-01-01

This paper describes a specific methodology adopted by Electricite de France to perform the evaluation of radiation protection performance and management within its 19 nuclear power plants. The results obtained in 2007 are summed up. (author)

Cerebral methodology based computing to estimate real phenomena from large-scale nuclear simulation

International Nuclear Information System (INIS)

Suzuki, Yoshio

2011-01-01

Our final goal is to estimate real phenomena from large-scale nuclear simulations by using computing processes. Large-scale simulations mean that they include scale variety and physical complexity so that corresponding experiments and/or theories do not exist. In nuclear field, it is indispensable to estimate real phenomena from simulations in order to improve the safety and security of nuclear power plants. Here, the analysis of uncertainty included in simulations is needed to reveal sensitivity of uncertainty due to randomness, to reduce the uncertainty due to lack of knowledge and to lead a degree of certainty by verification and validation (V and V) and uncertainty quantification (UQ) processes. To realize this, we propose 'Cerebral Methodology based Computing (CMC)' as computing processes with deductive and inductive approaches by referring human reasoning processes. Our idea is to execute deductive and inductive simulations contrasted with deductive and inductive approaches. We have established its prototype system and applied it to a thermal displacement analysis of a nuclear power plant. The result shows that our idea is effective to reduce the uncertainty and to get the degree of certainty. (author)

Development and application of a decision methodology for the planning of nuclear research and development in Saudi Arabia

International Nuclear Information System (INIS)

Abulfaraj, W.H.

1983-01-01

The thesis adapts two formal decision methodologies for the planning and development of a Nuclear Research Center for the Kingdom of Saudi Arabia. The methodologies are useful for the selection of alternative nuclear energy strategies. Multiattribute utility theory (MUT) and fuzzy set theory (FST) are selected to accommodate for decision makers' preferences and quick decision. MUT is employed to evaluate four appropriate research center facilities to determine the optimal choice therefrom in order to meet the needs of the proposed center. FST is used to handle site selection decision for the center. Procurement and siting decisions in Saudi Arabia for equipment are based on the demonstrated performance of operating units. Certain procedures discussed in detail in the dissertation reflect this modus operandi. 106 refs

Bow tie methodology: a tool to enhance the visibility and understanding of nuclear safety cases

International Nuclear Information System (INIS)

Vannerem, Marc

2013-01-01

There is much common ground between the nuclear industry and other major hazard industries such as those subject to the Seveso II regulations, e.g. oil, gas and chemicals. They are all subject to legal requirements to identify and control hazards, and to demonstrate that all necessary measures have been taken to minimise risks posed by the site with regard to people and the environment. This places a requirement on the Operators of major hazard installations, whether nuclear or conventional, to understand and identify the hazards of their operations, the initiating events, the consequences, the prevention and mitigation measures. However, in the UK, nuclear and 'Seveso' type facilities seem to adopt a different approach to the presentation of their safety cases. Given the magnitude of the hazards, safety cases developed for nuclear fuel cycle facilities are rigorous, detailed and complex, which can have the effect of reducing the visibility of the key hazards and corresponding protective measures. In contrast, on installations in the oil and gas and chemical industries, a real attempt has been made over recent years to improve the visibility and accessibility of the safety case to all operating personnel, through the use of visual aids / diagrams. In particular, many Operators are choosing to use 'bow tie methodology', in which very simple overview diagrams are produced to illustrate, in a form understandable by all: - what the key hazards are; - the initiating events; - the consequences of an incident; - the barriers or 'Layers of Protection' which prevent an initiating event from developing into an incident; - the barriers or 'Layers of Defence' which mitigate the consequences of an incident, i.e. which prevent the incident from escalating into major consequences. The bow tie method is one of a number of methodologies that can be used to make safety cases more accessible. It is used in this paper to illustrate ways to

Low activation material design methodology for reduction of radio-active wastes of nuclear power plant

International Nuclear Information System (INIS)

Hasegawa, A.; Satou, M.; Nogami, S.; Kakinuma, N.; Kinno, M.; Hayashi, K.

2007-01-01

Most of the concrete shielding walls and pipes around a reactor pressure vessel of a light water reactor become low level radioactive waste at decommission phase because they contain radioactive nuclides by thermal-neutron irradiation during its operation. The radioactivity of some low level radioactive wastes is close to the clearance level. It is very desirable in terms of life cycle cost reduction that the radioactivity of those low level radioactive wastes is decreased below clearance level. In case of light water reactors, however, methodology of low activation design of a nuclear plant has not been established yet because the reactor is a large-scale facility and has various structural materials. The Objectives of this work are to develop low activation material design methodology and material fabrication for reduction of radio-active wastes of nuclear power plant such as reinforced concrete. To realize fabrication of reduced radioactive concrete, it is necessary to develop (1) the database of the chemical composition of raw materials to select low activation materials, (2) the tool for calculation of the neutron flux and the spectrum distribution of nuclear plants to evaluate radioactivity of reactor components, (3) optimization of material process conditions to produce the low activation cement and the low activation steels. Results of the data base development, calculation tools and trial production of low activation cements will be presented. (authors)

Development of performance assessment methodology for nuclear waste isolation in geologic media

International Nuclear Information System (INIS)

Bonano, E.J.; Chu, M.S.Y.; Cranwell, R.M.; Davis, P.A.

1986-01-01

The analysis of the processes involved in the burial of nuclear wastes can be performed only with reliable mathematical models and computer codes as opposed to conducting experiments because the time scales associated are on the order of tens of thousands of years. These analyses are concerned primarily with the migration of radioactive contaminants from the repository to the environment accessible to humans. Modeling of this phenomenon depends on a large number of other phenomena taking place in the geologic porous and/or fractured medium. These are ground-water flow, physicochemical interactions of the contaminants with the rock, heat transfer, and mass transport. Once the radionuclides have reached the accessible environment, the pathways to humans and health effects are estimated. A performance assessment methodology for a potential high-level waste repository emplaced in a basalt formation has been developed for the US Nuclear Regulatory Commission

Methodology for the assessment of innovative nuclear reactors and fuel cycles. Report of Phase 1B (first part) of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Nuclear Information System (INIS)

2004-12-01

an innovative nuclear energy system (INS) to meet the overall target of sustainable energy supply. As well, the initial development of the INPRO method for the assessment of nuclear energy systems was carried out. The Basic Principles, User Requirements, and Criteria and the INPRO method of assessment, taken together, comprise the INPRO methodology. The INPRO methodology provides the possibility to take into account local, regional and global boundary conditions of IAEA Member States, including those of both developing and developed countries. Phase 1A was completed in June of 2003 with the publication of IAEA-TECDOC-1362, Guidance for the Evaluation of Innovative Nuclear Reactors and Fuel Cycles, which documented the results of the Phase 1A work. The next step of INPRO was immediately launched. In this step, referred to as Phase 1B (first part), INPRO arranged for some 14 case studies to be performed, by national teams or by individual experts from seven countries, to test and provide feedback on the applicability, consistency and completeness of the INPRO methodology. This report documents changes to the basic principles, user requirements, criteria and the method of assessment that resulted from the second step of INPRO (referred to as Phase 1B (first part)), which started in June 2003 and ended in December 2004. During this step, Member States and individual experts performed 14 case studies with the objective of testing and validating the INPRO methodology. Based on the feedback from these case studies and numerous consultancies mostly held at the IAEA, the INPRO methodology has been significantly updated and revised, as documented in this report. The ongoing and future activities of INPRO will lead to further modifications to the INPRO methodology, based on the feedback received from Member States in light of their experience in applying the methodology. Thus, additional reports will be issued, as appropriate, to update the INPRO methodology

A probabilistic seismic risk assessment procedure for nuclear power plants: (I) Methodology

Science.gov (United States)

Huang, Y.-N.; Whittaker, A.S.; Luco, N.

2011-01-01

A new procedure for probabilistic seismic risk assessment of nuclear power plants (NPPs) is proposed. This procedure modifies the current procedures using tools developed recently for performance-based earthquake engineering of buildings. The proposed procedure uses (a) response-based fragility curves to represent the capacity of structural and nonstructural components of NPPs, (b) nonlinear response-history analysis to characterize the demands on those components, and (c) Monte Carlo simulations to determine the damage state of the components. The use of response-rather than ground-motion-based fragility curves enables the curves to be independent of seismic hazard and closely related to component capacity. The use of Monte Carlo procedure enables the correlation in the responses of components to be directly included in the risk assessment. An example of the methodology is presented in a companion paper to demonstrate its use and provide the technical basis for aspects of the methodology. ?? 2011 Published by Elsevier B.V.

Statement at TM/workshop on evaluation methodology for national nuclear infrastructure development, 10 December 2008, Vienna, Austria

International Nuclear Information System (INIS)

Sokolov, Y.

2008-01-01

In his statement at the Technical Meeting Workshop on Evaluation Methodology for National Nuclear Infrastructure Development Mr. Yuri Sokolov, IAEA Deputy Director General, Head of the Department of Nuclear Energy, thanked the co-sponsors of the workshop, namely Canada, China, France, India, Japan, the Republic of Korea, the Russian Federation and the United States for their continued support and the Nuclear Power Engineering Section for their dedication and hard work to implement this workshop. The evaluation methodology that is the main subject of this workshop is a component of building infrastructure for the implementation of cost-effective, safe and secure nuclear power programme. It aims to provide a tool for effective planning. The IAEA evaluation approach can be used either by a Member State wishing to review its own progress (self-assessment) or as a basis for an external review through which a Member State wishes to reassure others that its nuclear programme is effective. The IAEA can, upon a request from the Member State, provide Integrated Nuclear Infrastructure Review missions, INIR, conducted by international experts. These INIR missions provide a means for countries to work with the IAEA in an open and transparent way to ensure they are taking a comprehensive and integrated approach to nuclear power as promoted in the Milestones document. National self-assessments supported by INIR missions will help Member States to identify gaps and areas that need increased attention, and will help the Agency to focus the assistance on the Member States needs. Another theme of the workshop is the role of the Nuclear Energy Programme Implementing Organization (NEPIO), in studying the nuclear power option and coordinating planning among various stakeholders. During the workshop publications in preparation will be presented including one on responsibilities and capabilities of owner-operator organizations and one on workforce planning. Presentations from the

LOFT uncertainty-analysis methodology

International Nuclear Information System (INIS)

Lassahn, G.D.

1983-01-01

The methodology used for uncertainty analyses of measurements in the Loss-of-Fluid Test (LOFT) nuclear-reactor-safety research program is described and compared with other methodologies established for performing uncertainty analyses

LOFT uncertainty-analysis methodology

International Nuclear Information System (INIS)

Lassahn, G.D.

1983-01-01

The methodology used for uncertainty analyses of measurements in the Loss-of-Fluid Test (LOFT) nuclear reactor safety research program is described and compared with other methodologies established for performing uncertainty analyses

The effects of overtime work and task complexity on the performance of nuclear plant operators: A proposed methodology

International Nuclear Information System (INIS)

Banks, W.W.; Potash, L.

1985-01-01

This document presents a very general methodology for determining the effect of overtime work and task complexity on operator performance in response to simulated out-of-limit nuclear plant conditions. The independent variables consist of three levels of overtime work and three levels of task complexity. Multiple dependent performance measures are proposed for use and discussion. Overtime work is operationally defined in terms of the number of hours worked by nuclear plant operators beyond the traditional 8 hours per shift. Task complexity is operationalized in terms of the number of operator tasks required to remedy a given plant anomalous condition and bring the plant back to a ''within limits'' or ''normal'' steady-state condition. The proposed methodology would employ a 2 factor repeated measures design along with the analysis of variance (linear) model

The methodology of root cause analysis for equipment failure and its application at Guangdong nuclear power stations

International Nuclear Information System (INIS)

Gao Ligang; Lu Qunxian

2004-01-01

The methodology of Equipment Failure Root Cause Analysis (RCA) is described, as a systematic analysis methodology, it includes 9 steps. Its process is explained by some real examples, and the 6 precautions applying RCA is pointed out. The paper also summarizes the experience of RCA application at Daya Bay Nuclear Power Station, and the 7 key factors for RCA success is emphasized, that mainly concerns organization, objective, analyst, analysis technique, external technical supporting system, corrective actions developing and monitoring system for corrective actions. (authors)

Methodology for implementation of a national metrology net of radionuclides used in nuclear medicine

International Nuclear Information System (INIS)

Santos, Joyra Amaral dos

2004-01-01

The National Laboratory for Ionizing Radiation Metrology, of the Institute of Radiation Protection and Dosimetry, of the National Commission on Nuclear Energy (IRD/CNEN), comes leading a comparison program for activity measurements of radiopharmaceuticals administered to patients in the Nuclear Medicine Services (NMS) with the purpose to promote the quality control. This work presents a quality assurance program for the performance of such measurements, evaluated in the comparison runs between hospitals and LNMRI, under the statistic point of view and the compliment of regulatory authority norms. The performance of the radionuclides 67 Ga, 123 I, 131 I, 99m Tc and 210 Tl were evaluated and 201 TI have been standardized by absolute methods. Besides, it was established the traceability of the radioactivity standards used in nuclear medicine and a methodology for implementation of a national metrology net of radionuclides. The comparison results prove that the implementation of a radionuclide metrology net is viable, important and feasible. (author)

Study of the nuclear structure of {sup 155}Eu; Estudo da estrutura nuclear do {sup 155}Eu

Energy Technology Data Exchange (ETDEWEB)

Genezini, Frederico Antonio

2004-07-01

The {sup 155}Eu nuclide was investigated by the directional angular correlation technique following the {beta} decay of {sup 155}Sm. The angular correlation measurements were carried out using a setup with 4 Ge detectors and a multi parametric data acquisition system. To perform the data analysis a new methodology was developed . The multipole mixing ratios of twenty sixty {gamma}- transitions were determined. Seven of them agreed with the results of earlier angular correlation studies and nineteen obtained for the first time confirmed the multipolarity suggested in earlier electron capture studies. Besides, the spin of the level at 1106.83 keV as well as the parity of the level at 1301.41 keV have also been suggested. The nuclear structure of {sup 155}Eu was discussed successfully in terms of the single particle model using a deformed Woods-Saxon potential plus residual pairing interaction permitting the description of the rotational quasi-proton band heads. (author)

Development of performance assessment methodology for nuclear waste isolation in geologic media

Science.gov (United States)

Bonano, E. J.; Chu, M. S. Y.; Cranwell, R. M.; Davis, P. A.

The burial of nuclear wastes in deep geologic formations as a means for their disposal is an issue of significant technical and social impact. The analysis of the processes involved can be performed only with reliable mathematical models and computer codes as opposed to conducting experiments because the time scales associated are on the order of tens of thousands of years. These analyses are concerned primarily with the migration of radioactive contaminants from the repository to the environment accessible to humans. Modeling of this phenomenon depends on a large number of other phenomena taking place in the geologic porous and/or fractured medium. These are ground-water flow, physicochemical interactions of the contaminants with the rock, heat transfer, and mass transport. Once the radionuclides have reached the accessible environment, the pathways to humans and health effects are estimated. A performance assessment methodology for a potential high-level waste repository emplaced in a basalt formation has been developed for the U.S. Nuclear Regulatory Commission.

Pulse superimposition calculational methodology for estimating the subcriticality level of nuclear fuel assemblies

International Nuclear Information System (INIS)

Talamo, Alberto; Gohar, Y.; Rabiti, C.; Aliberti, G.; Kondev, F.; Smith, D.; Zhong, Z.; Kiyavitskaya, H.; Bournos, V.; Fokov, Y.; Routkovskaya, C.; Serafimovich, I.

2009-01-01

One of the most reliable experimental methods for measuring the subcriticality level of a nuclear fuel assembly is the Sjoestrand method applied to the reaction rate generated from a pulsed neutron source. This study developed a new analytical methodology simulating the Sjoestrand method, which allows comparing the experimental and analytical reaction rates and the obtained subcriticality levels. In this methodology, the reaction rate is calculated due to a single neutron pulse using MCNP/MCNPX computer code or any other neutron transport code that explicitly simulates the delayed fission neutrons. The calculation simulates a single neutron pulse over a long time period until the delayed neutron contribution to the reaction rate is vanished. The obtained reaction rate is then superimposed to itself, with respect to the time, to simulate the repeated pulse operation until the asymptotic level of the reaction rate, set by the delayed neutrons, is achieved. The superimposition of the pulse to itself was calculated by a simple C computer program. A parallel version of the C program is used due to the large amount of data being processed, e.g. by the Message Passing Interface (MPI). The analytical results of this new calculation methodology have shown an excellent agreement with the experimental data available from the YALINA-Booster facility of Belarus. This methodology can be used to calculate Bell and Glasstone spatial correction factor.

Pulse superimposition calculational methodology for estimating the subcriticality level of nuclear fuel assemblies

Energy Technology Data Exchange (ETDEWEB)

Talamo, Alberto [Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)], E-mail: atalamo@anl.gov; Gohar, Y. [Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States); Rabiti, C. [Idaho National Laboratory, P.O. Box 2528, Idaho Falls, ID 83403 (United States); Aliberti, G.; Kondev, F.; Smith, D.; Zhong, Z. [Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States); Kiyavitskaya, H.; Bournos, V.; Fokov, Y.; Routkovskaya, C.; Serafimovich, I. [Joint Institute for Power and Nuclear Research-Sosny, National Academy of Sciences (Belarus)

2009-07-21

One of the most reliable experimental methods for measuring the subcriticality level of a nuclear fuel assembly is the Sjoestrand method applied to the reaction rate generated from a pulsed neutron source. This study developed a new analytical methodology simulating the Sjoestrand method, which allows comparing the experimental and analytical reaction rates and the obtained subcriticality levels. In this methodology, the reaction rate is calculated due to a single neutron pulse using MCNP/MCNPX computer code or any other neutron transport code that explicitly simulates the delayed fission neutrons. The calculation simulates a single neutron pulse over a long time period until the delayed neutron contribution to the reaction rate is vanished. The obtained reaction rate is then superimposed to itself, with respect to the time, to simulate the repeated pulse operation until the asymptotic level of the reaction rate, set by the delayed neutrons, is achieved. The superimposition of the pulse to itself was calculated by a simple C computer program. A parallel version of the C program is used due to the large amount of data being processed, e.g. by the Message Passing Interface (MPI). The analytical results of this new calculation methodology have shown an excellent agreement with the experimental data available from the YALINA-Booster facility of Belarus. This methodology can be used to calculate Bell and Glasstone spatial correction factor.

Recent developments in atomic/nuclear methodologies used for the study of cultural heritage objects

International Nuclear Information System (INIS)

Appoloni, Carlos Roberto

2012-01-01

Full text: Archaeometry is an area established in the international community since the 60s, with extensive use of atomic- nuclear methods in the characterization of art, archaeological and cultural heritage objects in general. In Brazil, however, until the early '90s, employing methods of physics, only the area of archaeological dating was implemented. It was only after this period that Brazilian groups became involved in the characterization of archaeological and art objects with these methodologies. The Laboratory of Applied Nuclear Physics, State University of Londrina (LFNA/UEL) introduced, pioneered in 1994, Archaeometry and related issues among its priority lines of research, after a member of LFNA has been involved in 1992 with the possibilities of tomography in archaeometry, as well as the analysis of ancient bronzes by EDXRF. Since then, LFNA has been working with PXRF and Portable Raman in several museums in Brazil, in field studies of cave paintings and in the laboratory with material sent by archaeologists, as well as carrying out collaborative work with new groups that followed in this area. From 2003/2004 LAMFI/DFN/IFUSP and LIN/COPPE/UFRJ began to engage in the area, respectively with methodologies using ion beams and PXRF, then over time incorporating other techniques, followed later by other groups. Due to the growing number of laboratories and institutions / archaeologists / conservators interested in these applications, in may 2012 was created a network of available laboratories, based at http://www.dfn.if.usp.br/lapac. It will be presented a panel of recent developments and applications of these methodologies by national groups, as well as a sampling of what has been done by leading groups abroad. (author)

Recent developments in atomic/nuclear methodologies used for the study of cultural heritage objects

International Nuclear Information System (INIS)

Appoloni, Carlos Roberto

2013-01-01

Archaeometry is an area established in the international community since the 60s, with extensive use of atomic-nuclear methods in the characterization of art, archaeological and cultural heritage objects in general. In Brazil, however, until the early '90s, employing methods of physics, only the area of archaeological dating was implemented. It was only after this period that Brazilian groups became involved in the characterization of archaeological and art objects with these methodologies. The Laboratory of Applied Nuclear Physics, State University of Londrina (LFNA/UEL) introduced, pioneered in 1994, Archaeometry and related issues among its priority lines of research, after a member of LFNA has been involved in 1992 with the possibilities of tomography in archaeometry, as well as the analysis of ancient bronzes by EDXRF. Since then, LFNA has been working with PXRF and Portable Raman in several museums in Brazil, in field studies of cave paintings and in the laboratory with material sent by archaeologists, as well as carrying out collaborative work with new groups that followed in this area. From 2003/2004 LAMFI/DFN/IFUSP and LIN/COPPE/UFRJ began to engage in the area, respectively with methodologies using ion beams and PXRF, then over time incorporating other techniques, followed later by other groups. Due to the growing number of laboratories and institutions/archaeologists/conservators interested in these applications, in may 2012 was created a network of available laboratories, based at http://www.dfn.if.usp.br/lapac. It will be presented a panel of recent developments and applications of these methodologies by national groups, as well as a sampling of what has been done by leading groups abroad.

Proceedings of the specialist research meeting on scientific and engineering researches of unstable nuclei and on their nuclear methodology (3)

International Nuclear Information System (INIS)

Kawade, K.; Taniguchi, A.; Yamada, S.

1998-01-01

New research fields with the use of radioactive ion beams are now rapidly developing by virtue of recent progress in radioactive beam accelerators. The scientific and engineering researches on unstable nuclei far from stability are getting particular interests aiming at the full use of their radiation. In the circumstance many laboratories report utilizations and researches of the RI beam, the Tohoku University's renewal plan of the cyclotron and the short-lived nuclear beam facility at KEK have started. To discuss these new subjects on the scientific and engineering researches of unstable nuclei and on their nuclear methodology, the third specialist meeting was held at the KUR on February 16 and 17, 1998. Several noticeable and wide scope works on the method of RI-beam generation and on the new development of nuclear methodology have been reported, such as fundamental researches with laser, new isotope searchings and researches of nuclear structures with ISOL, in-beam nuclear spectroscopies through the deep-inelastic collision. In this meeting, especially, fundamental support-researches are reported, which are precise measurements of absolute disintegration rates, a gamma peak analysis method, evaluations of fundamental nuclear data, measurements of beta detector response functions for reducing Q values and precise measurement of high energy gamma intensities up to 11 MeV. The 14 papers are indexed individually. (J.P.N.)

Assessing organizational culture in complex sociotechnical systems. Methodological evidence from studies in nuclear power plant maintenance organizations

International Nuclear Information System (INIS)

Reiman, T.

2007-03-01

Failures in industrial organizations dealing with hazardous technologies can have widespread consequences for the safety of the workers and the general population. Psychology can have a major role in contributing to the safe and reliable operation of these technologies. Most current models of safety management in complex sociotechnical systems such as nuclear power plant maintenance are either non-contextual or based on an overly-rational image of an organization. Thus, they fail to grasp either the actual requirements of the work or the socially-constructed nature of the work in question. The general aim of the present study is to develop and test a methodology for contextual assessment of organizational culture in complex sociotechnical systems. This is done by demonstrating the findings that the application of the emerging methodology produces in the domain of maintenance of a nuclear power plant (NPP). The concepts of organizational culture and organizational core task (OCT) are operationalized and tested in the case studies

Assessing organizational culture in complex sociotechnical systems. Methodological evidence from studies in nuclear power plant maintenance organizations

Energy Technology Data Exchange (ETDEWEB)

Reiman, T.

2007-03-15

Failures in industrial organizations dealing with hazardous technologies can have widespread consequences for the safety of the workers and the general population. Psychology can have a major role in contributing to the safe and reliable operation of these technologies. Most current models of safety management in complex sociotechnical systems such as nuclear power plant maintenance are either non-contextual or based on an overly-rational image of an organization. Thus, they fail to grasp either the actual requirements of the work or the socially-constructed nature of the work in question. The general aim of the present study is to develop and test a methodology for contextual assessment of organizational culture in complex sociotechnical systems. This is done by demonstrating the findings that the application of the emerging methodology produces in the domain of maintenance of a nuclear power plant (NPP). The concepts of organizational culture and organizational core task (OCT) are operationalized and tested in the case studies

A methodology to assist in contingency planning for protection of nuclear power plants against land vehicle bombs

International Nuclear Information System (INIS)

James, J.W.; Goldman, L.A.; Lobner, P.R.; Finn, S.P.; Koch, T.H.; Veatch, J.D.

1989-04-01

This report provides a methodology which could be used by operators of licensed nuclear power reactors to address issues related to contingency planning for a land vehicle bomb, should such a threat arise. The methodology presented in this report provides a structured framework for understanding factors to be considered in contingency planning for a land vehicle bomb including: (1) system options available to maintain a safe condition, (2) associated components and equipment, (3) preferred system options for establishing and maintaining a safe shutdown condition, and (4) contingency measures to preserve the preferred system options. Example applications of the methodology for a Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) are provided along with an example of contingency plan changes necessary for implementation of this methodology, a discussion of some contingency measures that can be used to limit land vehicle access, and a bibliography. 2 refs., 11 figs., 6 tabs

Seismic methodology in determining basis earthquake for nuclear installation

International Nuclear Information System (INIS)

Ameli Zamani, Sh.

2008-01-01

Design basis earthquake ground motions for nuclear installations should be determined to assure the design purpose of reactor safety: that reactors should be built and operated to pose no undue risk to public health and safety from earthquake and other hazards. Regarding the influence of seismic hazard to a site, large numbers of earthquake ground motions can be predicted considering possible variability among the source, path, and site parameters. However, seismic safety design using all predicted ground motions is practically impossible. In the determination of design basis earthquake ground motions it is therefore important to represent the influences of the large numbers of earthquake ground motions derived from the seismic ground motion prediction methods for the surrounding seismic sources. Viewing the relations between current design basis earthquake ground motion determination and modem earthquake ground motion estimation, a development of risk-informed design basis earthquake ground motion methodology is discussed for insight into the on going modernization of the Examination Guide for Seismic Design on NPP

Methodological proposal for identification and evaluation of environmental aspects and impacts of nuclear facilities of IPEN, Sao Paulo, SP, Brazil: a case study applied to the Nuclear Fuel Center; Proposta metodologica para a identificacao e avaliacao de aspectos e impactos ambientais em instalacoes nucleares do IPEN: estudo de caso aplicado ao Centro do Combustivel Nuclear

Energy Technology Data Exchange (ETDEWEB)

Mattos, Luis Antonio Terribile de

2013-07-01

This work presents an application of Failure Mode Effect Analysis (FMEA) to the process of identification of environmental aspects and impacts as a part of implementation and maintenance of an Environmental Management System (EMS) in accordance with the NBR ISO 14001 standard. Also, it can contribute, as a complement, to the evaluation and improvement of safety of the installation focused. The study was applied to the Nuclear Fuel Center (CCN) of Nuclear and Energy Research Institute (IPEN), situated at the Campus of University of Sao Paulo, Brazil. The CCN facility has the objective of promoting scientific research and of producing nuclear fuel elements for the IEA-R1 Research Reactor. To identify the environmental aspects of the facility activities, products, and services, a systematic data collection was carried out by means of personal interviews, documents, reports and operation data records consulting. Furthermore, the processes and their interactions, failure modes, besides their causes and effects to the environment, were identified. As a result of a careful evaluation of these causes it was possible to identify and to classify the major potential environmental impacts, in order to set up and put in practice an Environmental Management System for the installation under study. The results have demonstrated the validity of the FMEA application to nuclear facility processes, identifying environmental aspects and impacts, whose controls are critical to achieve compliance with the environmental requirements of the Integrated Management System of IPEN. It was demonstrated that the methodology used in this work is a powerful management tool for resolving issues related to the conformity with applicable regulatory and legal requirements of the Brazilian Nuclear Energy Commission (CNEN) and the Brazilian Institute of Environment (IBAMA). (author)

Methodology and conclusions of activation calculations of WWER-440 type nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Babcsány, Boglárka, E-mail: boglarka.babcsany@reak.bme.hu; Czifrus, Szabolcs; Fehér, Sándor

2015-04-01

Highlights: • Activation calculation of two WWER-440 type nuclear power plants. • Detailed description of the applied activation calculation methodology. • Graphical results for total activity and waste index categorization. • General conclusions for activation applicable in the case of PWR reactors. - Abstract: Activation calculations for two nuclear power plants of WWER-440 type have been performed by the authors in order to assist the decommissioning planning by assessing the radioactive inventory present at the time of and at different times after the final shutdown. According to related international literature and studies performed earlier by the authors, considering the activity more than 99% of this inventory is concentrated in the materials directly surrounding the reactor core, where the predominant evolution of radionuclides is generated by neutron induced nuclear reactions. In order to obtain the highest possible accuracy in modelling, three-dimensional Monte Carlo neutron transport calculations were performed. Besides the methods and models applied to these analyses, the paper also summarizes the results that can be generally applied to such nuclear power plant types. At the time of shutdown, the total activity of the stainless steel components is about 6 × 10{sup 16} Bq and 1.3 × 10{sup 17} Bq for the two NPPs considered. The biological shielding concrete constitutes approximately 7 × 10{sup 13} Bq and 1.1 × 10{sup 14} Bq.

New Methodology For Use in Rotating Field Nuclear MagneticResonance

Energy Technology Data Exchange (ETDEWEB)

Jachmann, Rebecca C. [Univ. of California, Berkeley, CA (United States)

2007-01-01

High-resolution NMR spectra of samples with anisotropicbroadening are simplified to their isotropic spectra by fast rotation ofthe sample at the magic angle 54.7 circ. This dissertation concerns thedevelopment of novel Nuclear Magnetic Resonance (NMR) methodologies basedwhich would rotate the magnetic field instead of the sample, rotatingfield NMR. It provides an over of the NMR concepts, procedures, andexperiments needed to understand the methodologies that will be used forrotating field NMR. A simple two-dimensional shimming method based onharmonic corrector rings which can provide arbitrary multiple ordershimming corrections were developed for rotating field systems, but couldbe used in shimming other systems as well. Those results demonstrate, forexample, that quadrupolar order shimming improves the linewidth by up toan order of magnitude. An additional order of magnitude reduction is inprinciple achievable by utilizing this shimming method for z-gradientcorrection and higher order xy gradients. A specialized pulse sequencefor the rotating field NMR experiment is under development. The pulsesequence allows for spinning away from the magic angle and spinningslower than the anisotropic broadening. This pulse sequence is acombination of the projected magic angle spinning (p-MAS) and magic angleturning (MAT) pulse sequences. This will be useful to rotating field NMRbecause there are limits on how fast a field can be spun and spin at themagic angle is difficult. One of the goals of this project is forrotating field NMR to be used on biological systems. The p-MAS pulsesequence was successfully tested on bovine tissue samples which suggeststhat it will be a viable methodology to use in a rotating field set up. Aside experiment on steering magnetic particle by MRI gradients was alsocarried out. Some movement was seen in these experiment, but for totalcontrol over steering further experiments would need to bedone.

New Methodology For Use in Rotating Field Nuclear MagneticResonance

Energy Technology Data Exchange (ETDEWEB)

Jachmann, Rebecca C. [Univ. of California, Berkeley, CA (United States)

2007-05-18

High-resolution NMR spectra of samples with anisotropicbroadening are simplified to their isotropic spectra by fast rotation ofthe sample at the magic angle 54.7 circ. This dissertation concerns thedevelopment of novel Nuclear Magnetic Resonance (NMR) methodologies basedwhich would rotate the magnetic field instead of the sample, rotatingfield NMR. It provides an over of the NMR concepts, procedures, andexperiments needed to understand the methodologies that will be used forrotating field NMR. A simple two-dimensional shimming method based onharmonic corrector rings which can provide arbitrary multiple ordershimming corrections were developed for rotating field systems, but couldbe used in shimming other systems as well. Those results demonstrate, forexample, that quadrupolar order shimming improves the linewidth by up toan order of magnitude. An additional order of magnitude reduction is inprinciple achievable by utilizing this shimming method for z-gradientcorrection and higher order xy gradients. A specialized pulse sequencefor the rotating field NMR experiment is under development. The pulsesequence allows for spinning away from the magic angle and spinningslower than the anisotropic broadening. This pulse sequence is acombination of the projected magic angle spinning (p-MAS) and magic angleturning (MAT) pulse sequences. This will be useful to rotating field NMRbecause there are limits on how fast a field can be spun and spin at themagic angle is difficult. One of the goals of this project is forrotating field NMR to be used on biological systems. The p-MAS pulsesequence was successfully tested on bovine tissue samples which suggeststhat it will be a viable methodology to use in a rotating field set up. Aside experiment on steering magnetic particle by MRI gradients was alsocarried out. Some movement was seen in these experiment, but for totalcontrol over steering further experiments would need to bedone.

Approaches for the Assessment of the Innovative Nuclear System of Ukraine on the Base of INPRO Methodology

International Nuclear Information System (INIS)

Afanas'ev, A.A.; Vlasenko, N.I.

2007-01-01

Approaches for the preliminary and comparative assessment of Innovative Nuclear System (INS) of Ukraine using INPRO methodology (IAEA TECDOC-1434) suggested for the period up to 2030, which must answer the comprehensive purpose of sustainable development, contribute to strengthening of the non-proliferation principles and solving an energy problems supply on national and regional levels are presented in the paper. Using assessment results of the INS based on evolutionary designs will allow Ukraine to build informative, methodological and technical basis for choice of the INS based on innovative design which could be offered for deployment in Ukraine after 1030

A Study for Appropriateness of National Nuclear Policy by using Economic Analysis Methodology after Fukushima accident

International Nuclear Information System (INIS)

Shim, Jong Myoung; Roh, Myung Sub

2013-01-01

The aim of this paper is to clarify the appropriateness of national nuclear policy in BPE of Korea from an economic perspective. To do this, this paper only focus on the economic analysis methodology without any considering other conditions such as political, cultural, or historical things. In a number of countries, especially Korea, nuclear energy policy is keeping the status quo after Fukushima accident. However the nation's nuclear policy may vary depending on the choice of people. Thus, to make the right decisions, it is important to deliver accurate information and knowledge about nuclear energy to the people. As proven in this paper, the levelized cost of nuclear power is the most inexpensive among the base load units. As the reliance on nuclear power is getting stronger through the economic logic, the nuclear safety and environmental elements will be strengthened. Based on this, national nuclear policy should be promoted. In the aftermath of the Fukushima accident recognized as the world's worst nuclear disaster since the Chernobyl, there are some changes in the nuclear energy policy of various countries. Germany, for example, called a halt to operate Nuclear Power Plant (NPP) which accounts for about 7.5% of the national power generation capacity of 6.3GW. In developing countries such as China and India they conducted the safety check of the nuclear power plants again before preceding their nuclear business. Korea government announced 'The 6th Basic Plan for Long-term Electricity Supply and Demand (BPE)', considering the safety and general public acceptance of the nuclear power plants. According to BPE, they postponed a plan for additional NPP construction, except for constructions that had been already reflected in the 5th BPE. All told, the responses for nuclear energy policy of countries are different depending on their own circumstances

A Study for Appropriateness of National Nuclear Policy by using Economic Analysis Methodology after Fukushima accident

Energy Technology Data Exchange (ETDEWEB)

Shim, Jong Myoung; Roh, Myung Sub [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2013-10-15

The aim of this paper is to clarify the appropriateness of national nuclear policy in BPE of Korea from an economic perspective. To do this, this paper only focus on the economic analysis methodology without any considering other conditions such as political, cultural, or historical things. In a number of countries, especially Korea, nuclear energy policy is keeping the status quo after Fukushima accident. However the nation's nuclear policy may vary depending on the choice of people. Thus, to make the right decisions, it is important to deliver accurate information and knowledge about nuclear energy to the people. As proven in this paper, the levelized cost of nuclear power is the most inexpensive among the base load units. As the reliance on nuclear power is getting stronger through the economic logic, the nuclear safety and environmental elements will be strengthened. Based on this, national nuclear policy should be promoted. In the aftermath of the Fukushima accident recognized as the world's worst nuclear disaster since the Chernobyl, there are some changes in the nuclear energy policy of various countries. Germany, for example, called a halt to operate Nuclear Power Plant (NPP) which accounts for about 7.5% of the national power generation capacity of 6.3GW. In developing countries such as China and India they conducted the safety check of the nuclear power plants again before preceding their nuclear business. Korea government announced 'The 6th Basic Plan for Long-term Electricity Supply and Demand (BPE)', considering the safety and general public acceptance of the nuclear power plants. According to BPE, they postponed a plan for additional NPP construction, except for constructions that had been already reflected in the 5th BPE. All told, the responses for nuclear energy policy of countries are different depending on their own circumstances.

A methodology for on-line fatigue life monitoring of Indian nuclear power plant components

International Nuclear Information System (INIS)

Mukhopadhyay, N.K.; Dutta, B.K.; Kushawaha, H.S.

1992-01-01

Fatigue is one of the most important aging effects of nuclear power plant components. Information about accumulation of fatigue helps in assessing structural degradation of the components. This assists in-service inspection and maintenance and may also support future life extension program of a plant. In the present report a methodology is being proposed for monitoring on line fatigue life of nuclear power plant components using available plant instrumentations. Major factors affecting fatigue life of a nuclear power plant components are the fluctuations of temperature, pressure and flow rate. Green's function technique is used in on line fatigue monitoring as computation time is much less than finite element method. A code has been developed which computes temperature and stress Green's functions in 2-D and axisymmetric structure by finite element method due to unit change in various fluid parameters. A post processor has also been developed which computes the temperature and stress responses using corresponding Green's functions and actual fluctuation in fluid parameters. In this post processor, the multiple site problem is solved by superimposing single site Green's function technique. It is also shown that Green's function technique is best suited for on line fatigue life monitoring of nuclear power plant components. (author). 6 refs., 43 figs

A methodology for performing virtual measurements in a nuclear reactor system

International Nuclear Information System (INIS)

Ikonomopoulos, A.; Uhrig, R.E.; Tsoukalas, L.H.

1992-01-01

A novel methodology is presented for monitoring nonphysically measurable variables in an experimental nuclear reactor. It is based on the employment of artificial neural networks to generate fuzzy values. Neural networks map spatiotemporal information (in the form of time series) to algebraically defined membership functions. The entire process can be thought of as a virtual measurement. Through such virtual measurements the values of nondirectly monitored parameters with operational significance, e.g., transient-type, valve-position, or performance, can be determined. Generating membership functions is a crucial step in the development and practical utilization of fuzzy reasoning, a computational approach that offers the advantage of describing the state of the system in a condensed, linguistic form, convenient for monitoring, diagnostics, and control algorithms

Development of a standard methodology for optimizing remote visual display for nuclear maintenance tasks

Science.gov (United States)

Clarke, M. M.; Garin, J.; Prestonanderson, A.

A fuel recycle facility being designed at Oak Ridge National Laboratory involves the Remotex concept: advanced servo-controlled master/slave manipulators, with remote television viewing, will totally replace direct human contact with the radioactive environment. The design of optimal viewing conditions is a critical component of the overall man/machine system. A methodology was developed for optimizing remote visual displays for nuclear maintenance tasks. The usefulness of this approach was demonstrated by preliminary specification of optimal closed circuit TV systems for such tasks.

A Methodology for Evaluating Quantitative Nuclear Safety Culture Impact

Energy Technology Data Exchange (ETDEWEB)

Han, Kiyoon; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of)

2015-05-15

Through several accidents of NPPs including the Fukushima Daiichi in 2011 and Chernobyl accidents in 1986, nuclear safety culture has been emphasized in reactor safety world-widely. In Korea, KHNP evaluates the safety culture of NPP itself. KHNP developed the principles of the safety culture in consideration of the international standards. A questionnaire and interview questions are also developed based on these principles and it is used for evaluating the safety culture. However, existing methodology to evaluate the safety culture has some disadvantages. First, it is difficult to maintain the consistency of the assessment. Second, the period of safety culture assessment is too long (every two years) so it has limitations in preventing accidents occurred by a lack of safety culture. Third, it is not possible to measure the change in the risk of NPPs by weak safety culture since it is not clearly explains the effect of safety culture on the safety of NPPs. In this study, Safety Culture Impact Assessment Model (SCIAM) is developed overcoming these disadvantages. In this study, SCIAM which overcoming disadvantages of exiting safety culture assessment method is developed. SCIAM uses SCII to monitor the statues of the safety culture periodically and also uses RCDF to quantify the safety culture impact on NPP's safety. It is significant that SCIAM represents the standard of the healthy nuclear safety culture, while the exiting safety culture assessment presented only vulnerability of the safety culture of organization. SCIAM might contribute to monitoring the level of safety culture periodically and, to improving the safety of NPP.

A Methodology for Evaluating Quantitative Nuclear Safety Culture Impact

International Nuclear Information System (INIS)

Han, Kiyoon; Jae, Moosung

2015-01-01

Through several accidents of NPPs including the Fukushima Daiichi in 2011 and Chernobyl accidents in 1986, nuclear safety culture has been emphasized in reactor safety world-widely. In Korea, KHNP evaluates the safety culture of NPP itself. KHNP developed the principles of the safety culture in consideration of the international standards. A questionnaire and interview questions are also developed based on these principles and it is used for evaluating the safety culture. However, existing methodology to evaluate the safety culture has some disadvantages. First, it is difficult to maintain the consistency of the assessment. Second, the period of safety culture assessment is too long (every two years) so it has limitations in preventing accidents occurred by a lack of safety culture. Third, it is not possible to measure the change in the risk of NPPs by weak safety culture since it is not clearly explains the effect of safety culture on the safety of NPPs. In this study, Safety Culture Impact Assessment Model (SCIAM) is developed overcoming these disadvantages. In this study, SCIAM which overcoming disadvantages of exiting safety culture assessment method is developed. SCIAM uses SCII to monitor the statues of the safety culture periodically and also uses RCDF to quantify the safety culture impact on NPP's safety. It is significant that SCIAM represents the standard of the healthy nuclear safety culture, while the exiting safety culture assessment presented only vulnerability of the safety culture of organization. SCIAM might contribute to monitoring the level of safety culture periodically and, to improving the safety of NPP

Framework of Comprehensive Proliferation Resistance Evaluation Methodology

International Nuclear Information System (INIS)

Kim, Min Su; Jo, Seong Youn; Kim, Min Soo; Kim, Jae San; Lee, Hyun Kyung

2007-01-01

Civilian nuclear programs can be used as a pretext to acquire technologies, materials, equipment for military weapon programs. Consequently, international society has a strong incentive to develop a nuclear system more proliferation resistant to assure that the civilian nuclear energy system is an unattractive and least desirable route for diversion of weapon usable material. The First step developing a more proliferation resistant nuclear energy system is to develop a systematic and standardized evaluation methodology to ensure that any future nuclear energy system satisfies the proliferation resistance goals. Many attempts to develop systematic evaluation methodology have been proposed and many systems for assessing proliferation resistance have been previously studied. However, a comprehensive proliferation resistance evaluation can not be achieved by simply applying one method since complicated proliferation resistance characteristics, including inherent features and extrinsic features, should be completely evaluated. Therefore, it is necessary to develop one incorporated evaluation methodology to make up for weak points of each evaluation method. The objective of this study is to provide a framework of comprehensive proliferation resistance evaluation methodology by incorporating two generally used evaluation methods, attribute and scenario analysis

A multivariate statistical methodology for detection of degradation and failure trends using nuclear power plant operational data

International Nuclear Information System (INIS)

Samanta, P.K.; Teichmann, T.

1990-01-01

In this paper, a multivariate statistical method is presented and demonstrated as a means for analyzing nuclear power plant transients (or events) and safety system performance for detection of malfunctions and degradations within the course of the event based on operational data. The study provides the methodology and illustrative examples based on data gathered from simulation of nuclear power plant transients (due to lack of easily accessible operational data). Such an approach, once fully developed, can be used to detect failure trends and patterns and so can lead to prevention of conditions with serious safety implications

National Inventories and Management Strategies for Spent Nuclear Fuel and Radioactive Waste. Methodology for Common Presentation of Data

International Nuclear Information System (INIS)

Volckaert, Geert; George, Mathews; Kugel, Karin; Garamszeghy, Miklos; Leclaire, Arnaud; Dionisi, Mario; Deryabin, Sergey; Lebedev, Vladimir; ); Lemmens, A.; Cairns, B.; Neri, E.G.

2016-01-01

Radioactive waste inventory data are an important element in the development of a national radioactive waste management programme since these data affect the design and selection of the ultimate disposal methods. Inventory data are generally presented as an amount of radioactive waste under various waste classes, according to the waste classification scheme developed and adopted by the country or national programme in question. Various waste classification schemes have thus evolved in most countries, and these schemes classify radioactive waste according to its origin, to criteria related to the protection of workers or to the physical, chemical and radiological properties of the waste and the planned disposal method(s). The diversity in classification schemes across countries has restricted the possibility of comparing waste inventories and led to difficulties in interpreting waste management practices, both nationally and internationally. To help improve this situation, the Nuclear Energy Agency proposed to develop a methodology that would ensure consistency of national radioactive waste inventory data when presenting them in a common scheme. This report provides such a methodology and presenting scheme for spent nuclear fuel and for waste arising from reprocessing. The extension of the methodology and presenting scheme to other types of radioactive waste and corresponding management strategies is envisaged in a second phase. (authors)

Clearance of surface-contaminated objects from the controlled area of a nuclear facility. Application of the SUDOQU methodology

Energy Technology Data Exchange (ETDEWEB)

Russo, F.; Mommaert, C. [Bel V, Brussels (Belgium); Dillen, T. van [National Institute for Public Health and the Environment (RIVM), Bilthoven (Netherlands)

2018-01-15

The lack of clearly defined surface-clearance levels in the Belgian regulation led Bel V to start a collaboration with the Dutch National Institute for Public Health and the Environment (RIVM) to evaluate the applicability of the SUDOQU methodology for the derivation of nuclide-specific surface-clearance criteria for objects released from nuclear facilities. SUDOQU is a methodology for the dose assessment of exposure to a surface-contaminated object, with the innovative assumption of a time-dependent surface activity whose evolution is influenced by removal and deposition mechanisms. In this work, calculations were performed to evaluate the annual effective dose resulting from the use of a typical office item, e.g. a bookcase. Preliminary results allow understanding the interdependencies between the model's underlying mechanisms, and show a strong sensitivity to the main input parameters. The results were benchmarked against those from a model described in Radiation Protection 101, to investigate the impact of the model's main assumptions. Results of the two models were in good agreement. The SUDOQU methodology appears to be a flexible and powerful tool, suitable for the proposed application. Therefore, the project will be extended to more generic study cases, to eventually develop surface-clearance levels applicable to objects leaving nuclear facilities.

Activities planning of Nuclear Data Center - 1980

International Nuclear Information System (INIS)

Nair, R.P.K.

1980-01-01

The main process systems of nuclear data files and the actual nuclear data processing implantation in the Instituto de Estudos Avancados, are presented. The research activities of Nuclear Data Center during 1980 in relation to the implantation of file process systems for multigroup cross sections, and the calculations of integral reactor parameters, are described. (M.C.K.) [pt

A methodological framework applied to the choice of the best method in replacement of nuclear systems

International Nuclear Information System (INIS)

Vianna Filho, Alfredo Marques

2009-01-01

The economic equipment replacement problem is a central question in Nuclear Engineering. On the one hand, new equipment are more attractive given their best performance, better reliability, lower maintenance cost etc. New equipment, however, require a higher initial investment. On the other hand, old equipment represent the other way around, with lower performance, lower reliability and specially higher maintenance costs, but in contrast having lower financial and insurance costs. The weighting of all these costs can be made with deterministic and probabilistic methods applied to the study of equipment replacement. Two types of distinct problems will be examined, substitution imposed by the wearing and substitution imposed by the failures. In order to solve the problem of nuclear system substitution imposed by wearing, deterministic methods are discussed. In order to solve the problem of nuclear system substitution imposed by failures, probabilistic methods are discussed. The aim of this paper is to present a methodological framework to the choice of the most useful method applied in the problem of nuclear system substitution.(author)

Assessment of Proliferation Resistance of Closed Nuclear Fuel Cycle System with Sodium Cooled Fast Reactors Using INPRO Evaluation Methodology

International Nuclear Information System (INIS)

Kim, Young In; Hahn, Do Hee; Won, Byung Chool; Lee, Dong Uk

2007-11-01

Using the INPRO methodology, the proliferation resistance of an innovative nuclear energy system(INS) defined as a closed nuclear fuel cycle system consisting of KALIMER and pyroprocessing, has been assessed. Considering a very early development stage of the INS concept, the PR assessment is carried out based on intrinsic features, if required information and data are not available. The PR assessment of KALIMER and JSFR using the INPRO methodology affirmed that an adequate proliferation resistance has been achieved in both INSs CNFC-SFR, considering the assessor's progress and maturity of design development. KALIMER and JSFR are developed or being developed conforming to the targets and criteria defined for developing Gen IV nuclear reactor system. Based on these assessment results, proliferation resistance and physical protection(PR and PP) of KALIMER and JSFR are evaluated from the viewpoint of requirements for future nuclear fuel cycle system. The envisioned INSs CNFC-SFR rely on active plutonium management based on a closed fuel cycle, in which a fissile material is recycled in an integrated fuel cycle facility within proper safeguards. There is no isolated plutonium in the closed fuel cycle. The material remains continuously in a sequence of highly radioactive matrices within inaccessible facilities. The proliferation resistance assessment should be an ongoing analysis that keeps up with the progress and maturity of the design of Gen IV SFR

Assessment of Proliferation Resistance of Closed Nuclear Fuel Cycle System with Sodium Cooled Fast Reactors Using INPRO Evaluation Methodology

Energy Technology Data Exchange (ETDEWEB)

Kim, Young In; Hahn, Do Hee; Won, Byung Chool; Lee, Dong Uk

2007-11-15

Using the INPRO methodology, the proliferation resistance of an innovative nuclear energy system(INS) defined as a closed nuclear fuel cycle system consisting of KALIMER and pyroprocessing, has been assessed. Considering a very early development stage of the INS concept, the PR assessment is carried out based on intrinsic features, if required information and data are not available. The PR assessment of KALIMER and JSFR using the INPRO methodology affirmed that an adequate proliferation resistance has been achieved in both INSs CNFC-SFR, considering the assessor's progress and maturity of design development. KALIMER and JSFR are developed or being developed conforming to the targets and criteria defined for developing Gen IV nuclear reactor system. Based on these assessment results, proliferation resistance and physical protection(PR and PP) of KALIMER and JSFR are evaluated from the viewpoint of requirements for future nuclear fuel cycle system. The envisioned INSs CNFC-SFR rely on active plutonium management based on a closed fuel cycle, in which a fissile material is recycled in an integrated fuel cycle facility within proper safeguards. There is no isolated plutonium in the closed fuel cycle. The material remains continuously in a sequence of highly radioactive matrices within inaccessible facilities. The proliferation resistance assessment should be an ongoing analysis that keeps up with the progress and maturity of the design of Gen IV SFR.

Demonstration of a performance assessment methodology for nuclear waste isolation in basalt formations

International Nuclear Information System (INIS)

Bonano, E.J.; Davis, P.A.

1988-01-01

This paper summarizes the results of the demonstration of a performance assessment methodology developed by Sandia National Laboratories, Albuquerque for the US Nuclear Regulatory Commission for use in the analysis of high-level radioactive waste disposal in deep basalts. Seven scenarios that could affect the performance of a repository in basalts were analyzed. One of these scenarios, normal ground-water flow, was called the base-case scenario. This was used to demonstrate the modeling capabilities in the methodology necessary to assess compliance with the ground-water travel time criterion. The scenario analysis consisted of both scenario screening and consequence modeling. Preliminary analyses of scenarios considering heat released from the waste and the alteration of the hydraulic properties of the rock mass due to loads created by a glacier suggested that these effects would not be significant. The analysis of other scenarios indicated that those changing the flow field in the vicinity of the repository would have an impact on radionuclide discharges, while changes far from the repository may not be significant. The analysis of the base-case scenario was used to show the importance of matrix diffusion as a radionuclide retardation mechanism in fractured media. The demonstration of the methodology also included an overall sensitivity analysis to identify important parameters and/or processes. 15 refs., 13 figs., 2 tabs

Risk-based methodology for USNRC inspections

International Nuclear Information System (INIS)

Wong, S.M.; Holahan, G.M.; Chung, J.W.; Johnson, M.R.

1995-01-01

This paper describes the development and trial applications of a risk-based methodology to enhance the inspection processes for US nuclear power plants. Objectives of risk-based methods to complement prescriptive engineering approaches in US Nuclear Regulatory Commission (USNRC) inspection programs are presented. Insights from time-dependent risk profiles of plant configurational from Individual Plant Evaluation (IPE) studies were integrated to develop a framework for optimizing inspection efforts in NRC regulatory initiatives. Lessons learned from NRC pilot applications of the risk-based methodology for evaluation of the effectiveness of operational risk management programs at US nuclear power plant sites are also discussed

Probabilistic methodology for turbine missile risk analysis

International Nuclear Information System (INIS)

Twisdale, L.A.; Dunn, W.L.; Frank, R.A.

1984-01-01

A methodology has been developed for estimation of the probabilities of turbine-generated missile damage to nuclear power plant structures and systems. Mathematical models of the missile generation, transport, and impact events have been developed and sequenced to form an integrated turbine missile simulation methodology. Probabilistic Monte Carlo techniques are used to estimate the plant impact and damage probabilities. The methodology has been coded in the TURMIS computer code to facilitate numerical analysis and plant-specific turbine missile probability assessments. Sensitivity analyses have been performed on both the individual models and the integrated methodology, and probabilities have been estimated for a hypothetical nuclear power plant case study. (orig.)

Physical protection evaluation methodology program development and application

International Nuclear Information System (INIS)

Seo, Janghoon; Yoo, Hosik

2015-01-01

It is essential to develop a reliable physical protection evaluation methodology for applying physical protection concept to the design stage. The methodology can be used to assess weak points and improve performance not only for the design stage but also for nuclear facilities in operation. Analyzing physical protection property of nuclear facilities is not a trivial work since there are many interconnected factors affecting overall performance. Therefore several international projects have been organized to develop a systematic physical protection evaluation methodology. INPRO (The International Project on Innovative Nuclear Reactors and Fuel Cycles) and GIF PRPP (Generation IV International Forum Proliferation Resistance and Physical Protection) methodology are among the most well-known evaluation methodologies. INPRO adopts a checklist type of questionnaire and has a strong point in analyzing overall characteristic of facilities in a qualitative way. COMPRE program has been developed to help general users apply COMPRE methodology to nuclear facilities. In this work, COMPRE program development and a case study of the hypothetical nuclear facility are presented. The development of COMPRE program and a case study for hypothetic facility is presented in this work. The case study shows that COMPRE PP methodology can be a useful tool to assess the overall physical protection performance of nuclear facilities. To obtain meaningful results from COMPRE PP methodology, detailed information and comprehensive analysis are required. Especially, it is not trivial to calculate reliable values for PPSE (Physical Protection System Effectiveness) and C (Consequence), while it is relatively straightforward to evaluate LI (Legislative and Institutional framework), MC (Material Control) and HR (Human Resources). To obtain a reliable PPSE value, comprehensive information about physical protection system, vital area analysis and realistic threat scenario assessment are required. Like

Physical protection evaluation methodology program development and application

Energy Technology Data Exchange (ETDEWEB)

Seo, Janghoon; Yoo, Hosik [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

2015-10-15

It is essential to develop a reliable physical protection evaluation methodology for applying physical protection concept to the design stage. The methodology can be used to assess weak points and improve performance not only for the design stage but also for nuclear facilities in operation. Analyzing physical protection property of nuclear facilities is not a trivial work since there are many interconnected factors affecting overall performance. Therefore several international projects have been organized to develop a systematic physical protection evaluation methodology. INPRO (The International Project on Innovative Nuclear Reactors and Fuel Cycles) and GIF PRPP (Generation IV International Forum Proliferation Resistance and Physical Protection) methodology are among the most well-known evaluation methodologies. INPRO adopts a checklist type of questionnaire and has a strong point in analyzing overall characteristic of facilities in a qualitative way. COMPRE program has been developed to help general users apply COMPRE methodology to nuclear facilities. In this work, COMPRE program development and a case study of the hypothetical nuclear facility are presented. The development of COMPRE program and a case study for hypothetic facility is presented in this work. The case study shows that COMPRE PP methodology can be a useful tool to assess the overall physical protection performance of nuclear facilities. To obtain meaningful results from COMPRE PP methodology, detailed information and comprehensive analysis are required. Especially, it is not trivial to calculate reliable values for PPSE (Physical Protection System Effectiveness) and C (Consequence), while it is relatively straightforward to evaluate LI (Legislative and Institutional framework), MC (Material Control) and HR (Human Resources). To obtain a reliable PPSE value, comprehensive information about physical protection system, vital area analysis and realistic threat scenario assessment are required. Like

Metodologia de Shigeo Shingo (SMED: análise crítica e estudo de caso Shingo ´s methodology (SMED: critical evaluation and case study

Directory of Open Access Journals (Sweden)

Miguel Sugai

2007-01-01

Full Text Available A metodologia de Shigeo Shingo (SMED - single minute exchange of die foi publicada pela primeira vez no Ocidente em 1985, e é referência principal quando se trata de redução dos tempos de setup de máquinas. A metodologia enfatiza a separação e a transferência de elementos do setup interno para o setup externo. As diversas aplicações industriais e os artigos existentes indicam a relevância do tema e da metodologia. Este artigo propõe-se a analisar criticamente o SMED revelando as lacunas da metodologia. Particularmente, discutem-se os problemas associados aos períodos de desaceleração e aceleração relacionados às atividades de setup, verificando-se que a separação e a conversão de tarefas não são suficientes. Para tanto, apresenta-se um estudo de caso em uma linha de produção.Shingo ´s SMED (single minute exchange of die methodology was first published in the West in 1985 and is today widely used by companies to reduce changeover times. The methodology, which emphasizes the separation and conversion of internal setup to external setup, is likewise favourably viewed within academia. This article analyzes SMED, indicates some gaps in the methodology and proposes how potential shortcomings might be overcome. In particular it discusses problems associated with both the run-down and run-up phases of a changeover, and describes how an over-reliance on techniques to separate and convert changeover tasks can be misplaced.

Nuclear Dynamics Consequence Analysis (NDCA) for the Disposal of Spent Nuclear Fuel in an Underground Geologic Repository--Volume 2: Methodology and Results

International Nuclear Information System (INIS)

Taylor, L.L.; Wilson, J.R.; Sanchez, L.C.; Aguilar, R.; Trellue, H.R.; Cochrane, K.; Rath, J.S.

1998-01-01

The US Department of Energy Office of Environmental Management's (DOE/EM's) National Spent Nuclear Fuel Program (NSNFP), through a collaboration between Sandia National Laboratories (SNL) and Idaho National Engineering and Environmental Laboratory (INEEL), is conducting a systematic Nuclear Dynamics Consequence Analysis (NDCA) of the disposal of SNFs in an underground geologic repository sited in unsaturated tuff. This analysis is intended to provide interim guidance to the DOE for the management of the SNF while they prepare for final compliance evaluation. This report presents results from a Nuclear Dynamics Consequence Analysis (NDCA) that examined the potential consequences and risks of criticality during the long-term disposal of spent nuclear fuel owned by DOE-EM. This analysis investigated the potential of post-closure criticality, the consequences of a criticality excursion, and the probability frequency for post-closure criticality. The results of the NDCA are intended to provide the DOE-EM with a technical basis for measuring risk which can be used for screening arguments to eliminate post-closure criticality FEPs (features, events and processes) from consideration in the compliance assessment because of either low probability or low consequences. This report is composed of an executive summary (Volume 1), the methodology and results of the NDCA (Volume 2), and the applicable appendices (Volume 3)

Nuclear Dynamics Consequence Analysis (NDCA) for the Disposal of Spent Nuclear Fuel in an Underground Geologic Repository--Volume 2: Methodology and Results

Energy Technology Data Exchange (ETDEWEB)

Taylor, L.L.; Wilson, J.R.; Sanchez, L.C.; Aguilar, R.; Trellue, H.R.; Cochrane, K.; Rath, J.S.

1998-10-01

The US Department of Energy Office of Environmental Management's (DOE/EM's) National Spent Nuclear Fuel Program (NSNFP), through a collaboration between Sandia National Laboratories (SNL) and Idaho National Engineering and Environmental Laboratory (INEEL), is conducting a systematic Nuclear Dynamics Consequence Analysis (NDCA) of the disposal of SNFs in an underground geologic repository sited in unsaturated tuff. This analysis is intended to provide interim guidance to the DOE for the management of the SNF while they prepare for final compliance evaluation. This report presents results from a Nuclear Dynamics Consequence Analysis (NDCA) that examined the potential consequences and risks of criticality during the long-term disposal of spent nuclear fuel owned by DOE-EM. This analysis investigated the potential of post-closure criticality, the consequences of a criticality excursion, and the probability frequency for post-closure criticality. The results of the NDCA are intended to provide the DOE-EM with a technical basis for measuring risk which can be used for screening arguments to eliminate post-closure criticality FEPs (features, events and processes) from consideration in the compliance assessment because of either low probability or low consequences. This report is composed of an executive summary (Volume 1), the methodology and results of the NDCA (Volume 2), and the applicable appendices (Volume 3).

A study on methodologies for assessing safety critical network's risk impact on Nuclear Power Plant

International Nuclear Information System (INIS)

Lim, T. J.; Lee, H. J.; Park, S. K.; Seo, S. J.

2006-08-01

The objectives of this project is to investigate and study existing reliability analysis techniques for communication networks in order to develop reliability analysis models for Nuclear Power Plant's safety-critical networks. It is necessary to make a comprehensive survey of current methodologies for communication network reliability. Major outputs of the first year study are design characteristics of safety-critical communication networks, efficient algorithms for quantifying reliability of communication networks, and preliminary models for assessing reliability of safety-critical communication networks

Development and application of a methodology for the analysis of significant human related event trends in nuclear power plants

International Nuclear Information System (INIS)

Cho, H.Y.

1981-01-01

A methodology is developed to identify and flag significant trends related to the safety and availability of U.S. commercial nuclear power plants. The development is intended to aid in reducing likelihood of human errors. To assure that the methodology can be easily adapted to various types of classification schemes of operation data, a data bank classified by the Transient Analysis Classification and Evaluation (TRACE) scheme is selected for the methodology. The significance criteria for human-initiated events affecting the systems and for events caused by human deficiencies were developed. Clustering analysis was used to verify the learning trend in multidimensional histograms. A computer code is developed based on the K-Means algorithm and applied to find the learning period in which error rates are monotonously decreasing with plant age. The Freeman-Tukey (F-T) deviates are used to select generic problems identified by a large positive value (here approximately over 2.0) for the deviate. The identified generic problems are: decision errors which are highly associated with reactor startup operations in the learning period of PWR plants (PWRs), response errors which are highly associated with Secondary Non-Nuclear Systems (SNS) in PWRs, and significant errors affecting systems and which are caused by response action are highly associated with startup reactor mode in BWRS

Evaluation of proliferation resistance using the INPRO methodology

International Nuclear Information System (INIS)

Yang, Myung Seung; Park, Joo Hwan; Ko, Won Il; Song, Kee Chan; Choi, Kun Mo; Kim, Jin Kyoung

2007-01-01

The IAEA launched the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) and developed the INPRO Methodology to provide guidelines and to assess the characteristics of a future innovative nuclear energy system in areas such as safety, economics, waste management, and proliferation resistance. The proliferation resistance area of the INPRO Methodology is reviewed here, and modifications for further improvements are proposed. The evaluation metrics including the evaluation parameters, evaluation scales and acceptance limits are developed for a practical application of the methodology to assess the proliferation resistance. The proliferation resistant characteristics of the DUPIC fuel cycle are assessed by applying the modified INPRO Methodology based on the developed evaluation metrics and acceptance criteria. The evaluation procedure and the metrics can be utilized as a reference for an evaluation of the proliferation resistance of a future innovative nuclear energy system

A discussion about simplified methodologies for failure assessment of nuclear reactor components

International Nuclear Information System (INIS)

Cruz, J.R.B.; Andrade, A.H.P. de; Landes, J.D.

1996-01-01

Failure of nuclear reactor components like pressure vessels and piping must be avoided for all phases of reactor operation. Especially severe loading conditions come from postulated accident scenarios during which the integrity of the component is required. The use of Fracture Mechanics concepts to investigate the mechanical behavior of flawed structures in the non-linear regime is a complex subject due to the fact that the crack driving force (expressed in terms of J or CTOD) is not /only a function of the cracked geometry, but depends also on the plastic flow properties of the material. Since the numerical solutions by the finite element method are expensive and time consuming, the existence of simplified engineering procedures is of great relevance. These allow a ready identification of the main parameters affecting the crack driving force, and permit a fast and simple evaluation of the structural integrity of the cracked component. This paper presents an overview of the major simplified ductile fracture methodologies that have been proposed in the literature trying to point out their similarities, strong points and negative aspects. Once the best characteristics of each method are identified, they could then be combined to develop a single methodology, one that would be both easy to use and capable of making accurate failure predictions

Knowledge-based operation guidance system for nuclear power plants based on generic task methodology

International Nuclear Information System (INIS)

Yamada, Naoyuki; Chandrasekaran, B.; Bhatnager, R.

1989-01-01

A knowledge-based system for operation guidance of nuclear power plants is proposed. The Dynamic Procedure Management System (DPMS) is designed and developed to assist human operators interactively by selecting and modifying predefined operation procedures in a dynamic situation. Unlike most operation guidance systems, DPMS has been built based on Generic Task Methodology, which makes the overall framework of the system perspicuous and also lets domain knowledge be represented in a natural way. This paper describes the organization of the system, the definition of each task, and the form and organization of knowledge, followed by an application example. (author)

Development of Proliferation Resistance Assessment Methodology Based on International Standards

International Nuclear Information System (INIS)

Lee, Yong Deok; Lee, Jung Won; Lee, Kwang Seok

2009-03-01

Proliferation resistance is one of the requirement to be met in GEN IV and INPRO for next generation nuclear energy system. Internationally, the evaluation methodology on PR had been already initiated from 1980, but the systematic development was started at 2000s. In Korea, for the export of nuclear energy system and the increase of international credibility and transparence of domestic nuclear system and fuel cycle development, the independent development of PR evaluation methodology was started in 2007 as a nuclear long term R and D project and the development is being performed for the model of PR evaluation methodology. In 1st year, comparative study of GEN-IV/INPRO, PR indicator development, quantification of indicator and evaluation model development, analysis of technology system and international technology development trend had been performed. In 2nd year, feasibility study of indicator, allowable limit of indicator, review of technical requirement of indicator were done. The results of PR evaluation must be applied in the beginning of conceptual design of nuclear system. Through the technology development of PR evaluation methodology, the methodology will be applied in the regulatory requirement for authorization and permission to be developed

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

Energy Technology Data Exchange (ETDEWEB)

Bozzolan, Jean-Claude

2006-07-01

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

Nuclear EMP: ingredients of an EMP protection engineering methodology

International Nuclear Information System (INIS)

Latorre, V.R.; Spogen, L.R. Jr.

1977-02-01

A fundamental methodology of electromagnetic pulse (EMP) protection engineering is described. Operations performed within the framework of this methodology are discussed. These operations, along with problem constraints and data, constitute the essential ingredients needed to implement the overall engineering methodology. Basic definitions and descriptions of these essential ingredients are provided. The issues discussed represent the first step in developing a methodology for protecting systems against EMP effects

Development of risk-informed assessment (RIA) design methodology

International Nuclear Information System (INIS)

Ji, S. K.; Park, S. J.; Park, B. R.; Kim, M. R.; Choi, C. J.

2001-01-01

It has been assessed that the capital cost for future nuclear power plants needs to be reduced on the order of 35% to 40% for Advanced Light Water Reactors such as KNGR and System 80+. Such reduction in the capital cost will require a fundamental re-evaluation of the industry standards and regulatory basis under which nuclear plants are designed and licensed. The objective of this study is to develop the risk-informed assessment (RIA) design methodology for future nuclear power plants. In order to meet this objective, the design simplification method is developed and RIA design methodology exercised for conceptual system. For the methodology verification, simplified conceptual ECCS and feedwater system are developed, then LOCA sensitivity analyses and agressive secondary cooldown analyses for these systems are performed. In addition, the probability safety assessment (PSA) model for LOCA is developed and the validation of RIA design methodology is demonstrated

Methodology for the nuclear design validation of an Alternate Emergency Management Centre (CAGE

Directory of Open Access Journals (Sweden)

Hueso César

2017-01-01

Full Text Available The methodology is devised by coupling different codes. The study of weather conditions as part of the data of the site will determine the relative concentrations of radionuclides in the air using ARCON96. The activity in the air is characterized depending on the source and release sequence specified in NUREG-1465 by RADTRAD code, which provides results of the inner cloud source term contribution. Known activities and energy spectra are inferred using ORIGEN-S, which are used as input for the models of the outer cloud, filters and containment generated with MCNP5. The sum of the different contributions must meet the conditions of habitability specified by the CSN (Spanish Nuclear Regulatory Body (TEDE <50 mSv and equivalent dose to the thyroid <500 mSv within 30 days following the accident doses so that the dose is optimized by varying parameters including CAGE location, flow filtering need for recirculation, thicknesses and compositions of the walls, etc. The results for the most penalizing area meet the established criteria, and therefore the CAGE building design based on the methodology presented is radiologically validated.

Methodology for the nuclear design validation of an Alternate Emergency Management Centre (CAGE

Directory of Open Access Journals (Sweden)

Hueso César

2017-01-01

Full Text Available The methodology is devised by coupling different codes. The study of weather conditions as part of the data of the site will determine the relative concentrations of radionuclides in the air using ARCON96. The activity in the air is characterized depending on the source and release sequence specified in NUREG-1465 by RADTRAD code, which provides results of the inner cloud source term contribution. Known activities, energy spectra are inferred using ORIGEN-S, which are used as input for the models of the outer cloud, filters and containment generated with MCNP5. The sum of the different contributions must meet the conditions of habitability specified by the CSN (Spanish Nuclear Regulatory Body (TEDE <50 mSv and equivalent dose to the thyroid <500 mSv within 30 days following the accident doses so that the dose is optimized by varying parameters such as CAGE location, flow filtering need for recirculation, thicknesses and compositions of the walls, etc. The results for the most penalizing area meet the established criteria, and therefore the CAGE building design based on the methodology presented is radiologically validated.

Study on scenario evaluation methodology for decommissioning nuclear facilities using fuzzy logic

International Nuclear Information System (INIS)

Matsuhashi, Kazuya; Yanagihara, Satoshi

2015-01-01

Since there are many scenarios of the process from start to completion of a decommissioning project, it is important to study scenarios of decommissioning by evaluating such properties as safety, cost, and technology. An optimum scenario with the highest feasibility in accordance with the facility and environmental conditions should be selected on the basis of the results of the study. For analyzing a scenario of decommissioning, we prepared structured work packages by using the work breakdown structures (WBS) method together with qualitative evaluation of the technologies being applied to work packages located at the bottom (the third level) of the WBS. A calculation model was constructed to evaluate the feasibility of a scenario where fuzzy logic is applied to derive a score of technology performance and TOPSIS is applied for getting a feasibility grade of the scenario from technical performance scoring. As a case study, the model was applied to the debris removal scenario of Fukushima Daiichi Nuclear Power Plant to confirm its applicability. Two scenarios, underwater and in-air debris removal cases, were characterized by extracting the work packages with the lowest feasibility and by obtaining total average scores of the scenarios. It is confirmed that the methodology developed is useful for the scenario evaluation of decommissioning nuclear facilities. (author)

Development of performance assessment methodology for nuclear waste isolation in geologic media

International Nuclear Information System (INIS)

Bonano, E.J.; Chu, M.S.Y.; Cranwell, R.M.; Davis, P.A.

1985-01-01

The burial of nuclear wastes in deep geologic formations as a means for their disposal is an issue of significant technical and social impact. The analysis of the processes involved can be performed only with reliable mathematical models and computer codes as opposed to conducting experiments because the time scales associated are on the order of tens of thousands of years. These analyses are concerned primarily with the migration of radioactive contaminants from the repository to the environment accessible to humans. Modeling of this phenomenon depends on a large number of other phenomena taking place in the geologic porous and/or fractured medium. These are gound-water flow, physicochemical interactions of the contaminants with the rock, heat transfer, and mass transport. Once the radionuclides have reached the accessible environment, the pathways to humans and health effects are estimated. A performance assessment methodology for a potential high-level waste repository emplaced in a basalt formation has been developed for the US Nuclear Regulatory Commission. The approach followed consists of a description of the overall system (waste, facility, and site), scenario selection and screening, consequence modeling (source term, ground-water flow, radionuclide transport, biosphere transport, and health effects), and uncertainty and sensitivity analysis

Methodology for the nuclear design validation of an Alternate Emergency Management Centre (CAGE)

Science.gov (United States)

Hueso, César; Fabbri, Marco; de la Fuente, Cristina; Janés, Albert; Massuet, Joan; Zamora, Imanol; Gasca, Cristina; Hernández, Héctor; Vega, J. Ángel

2017-09-01

The methodology is devised by coupling different codes. The study of weather conditions as part of the data of the site will determine the relative concentrations of radionuclides in the air using ARCON96. The activity in the air is characterized depending on the source and release sequence specified in NUREG-1465 by RADTRAD code, which provides results of the inner cloud source term contribution. Known activities, energy spectra are inferred using ORIGEN-S, which are used as input for the models of the outer cloud, filters and containment generated with MCNP5. The sum of the different contributions must meet the conditions of habitability specified by the CSN (Spanish Nuclear Regulatory Body) (TEDE validated.

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)

Tornado missile simulation and design methodology. Volume 1: simulation methodology, design applications, and TORMIS computer code. Final report

International Nuclear Information System (INIS)

Twisdale, L.A.; Dunn, W.L.

1981-08-01

A probabilistic methodology has been developed to predict the probabilities of tornado-propelled missiles impacting and damaging nuclear power plant structures. Mathematical models of each event in the tornado missile hazard have been developed and sequenced to form an integrated, time-history simulation methodology. The models are data based where feasible. The data include documented records of tornado occurrence, field observations of missile transport, results of wind tunnel experiments, and missile impact tests. Probabilistic Monte Carlo techniques are used to estimate the risk probabilities. The methodology has been encoded in the TORMIS computer code to facilitate numerical analysis and plant-specific tornado missile probability assessments. Sensitivity analyses have been performed on both the individual models and the integrated methodology, and risk has been assessed for a hypothetical nuclear power plant design case study

Estimating the cost of delaying a nuclear power plant: methodology and application

International Nuclear Information System (INIS)

Hill, L.J.; Tepel, R.C.; Van Dyke, J.W.

1985-01-01

This paper presents an analysis of an actual 24-month nuclear power plant licensing delay under alternate assumptions about regulatory practice, sources of replacement power, and the cost of the plant. The analysis focuses on both the delay period and periods subsequent to the delay. The methodology utilized to simulate the impacts involved the recursive interaction of a generation-costing program to estimate fuel-replacement costs and a financial regulatory model to concomitantly determine the impact on the utility, its ratepayers, and security issues. The results indicate that a licensing delay has an adverse impact on the utility's internal generation of funds and financial indicators used to evaluate financial soundness. The direction of impact on electricity rates is contingent on the source of fuel used for replacement power. 5 references, 5 tables

Sandia National Laboratories performance assessment methodology for long-term environmental programs : the history of nuclear waste management.

Energy Technology Data Exchange (ETDEWEB)

Marietta, Melvin Gary; Anderson, D. Richard; Bonano, Evaristo J.; Meacham, Paul Gregory (Raytheon Ktech, Albuquerque, NM)

2011-11-01

Sandia National Laboratories (SNL) is the world leader in the development of the detailed science underpinning the application of a probabilistic risk assessment methodology, referred to in this report as performance assessment (PA), for (1) understanding and forecasting the long-term behavior of a radioactive waste disposal system, (2) estimating the ability of the disposal system and its various components to isolate the waste, (3) developing regulations, (4) implementing programs to estimate the safety that the system can afford to individuals and to the environment, and (5) demonstrating compliance with the attendant regulatory requirements. This report documents the evolution of the SNL PA methodology from inception in the mid-1970s, summarizing major SNL PA applications including: the Subseabed Disposal Project PAs for high-level radioactive waste; the Waste Isolation Pilot Plant PAs for disposal of defense transuranic waste; the Yucca Mountain Project total system PAs for deep geologic disposal of spent nuclear fuel and high-level radioactive waste; PAs for the Greater Confinement Borehole Disposal boreholes at the Nevada National Security Site; and PA evaluations for disposal of high-level wastes and Department of Energy spent nuclear fuels stored at Idaho National Laboratory. In addition, the report summarizes smaller PA programs for long-term cover systems implemented for the Monticello, Utah, mill-tailings repository; a PA for the SNL Mixed Waste Landfill in support of environmental restoration; PA support for radioactive waste management efforts in Egypt, Iraq, and Taiwan; and, most recently, PAs for analysis of alternative high-level radioactive waste disposal strategies including repositories deep borehole disposal and geologic repositories in shale and granite. Finally, this report summarizes the extension of the PA methodology for radioactive waste disposal toward development of an enhanced PA system for carbon sequestration and storage systems

Methodology for conducting baseline environmental studies, applied to the environments of two nuclear sites; Metodologia para la realizacion de estudios de estado basico ambiental, aplicada a los entornos de dos emplazamientos nucleares

Energy Technology Data Exchange (ETDEWEB)

Fernandez Baco, L.; Yague Alvarez, F.

2012-07-01

The methodology described can understand and document the characteristics of form geo referenced environmental baseline condition of the surroundings of nuclear power plants, covering the needs in this regard made by the legislation of environmental responsibility.

On the major ductile fracture methodologies for failure assessment of nuclear reactor components

International Nuclear Information System (INIS)

Cruz, Julio R.B.; Andrade, Arnaldo H.P. de; Landes, John D.

1996-01-01

In structures like nuclear reactor components there is a special concern with the loads that may occur under postulated accident conditions. These loads can cause the stresses to go well beyond the linear elastic limits, requiring the use of ductile fracture mechanics methods to the prediction of the structure behavior. Since the use of numerical methods to apply EPFM concepts is expensive and time consuming, the existence of analytical engineering procedures are of great relevance. The lack of precision in detail, as compared with numerical nonlinear analyses, is compensated by the possibility of quick failure assessments. This is a determinant factor in situations where a systematic evaluation of a large range of geometries and loading conditions is necessary, like in thr application of the Leak-Before-Break (LBB) concept on nuclear piping. This paper outlines four ductile fracture analytical methods, pointing out positive and negative aspects of each one. The objective is to take advantage of this critical review to conceive a new methodology, one that would gather strong points of the major existent methods and would try to eliminate some of their drawbacks. (author)

76 FR 81998 - Methodology for Low Power/Shutdown Fire PRA

Science.gov (United States)

2011-12-29

... NUCLEAR REGULATORY COMMISSION [NRC-2011-0295] Methodology for Low Power/Shutdown Fire PRA AGENCY..., ``Methodology for Low Power/Shutdown Fire PRA--Draft Report for Comment.'' DATES: Submit comments by March 01... risk assessment (PRA) method for quantitatively analyzing fire risk in commercial nuclear power plants...

Comparative analysis of proliferation resistance assessment methodologies

International Nuclear Information System (INIS)

Takaki, Naoyuki; Kikuchi, Masahiro; Inoue, Naoko; Osabe, Takeshi

2005-01-01

Comparative analysis of the methodologies was performed based on the discussions in the international workshop on 'Assessment Methodology of Proliferation Resistance for Future Nuclear Energy Systems' held in Tokyo, on March 2005. Through the workshop and succeeding considerations, it is clarified that the proliferation resistance assessment methodologies are affected by the broader nuclear options being pursued and also by the political situations of the state. Even the definition of proliferation resistance, despite the commonality of fundamental issues, derives from perceived threat and implementation circumstances inherent to the larger programs. Deep recognitions of the 'difference' among communities would help us to make further essential and progressed discussion with harmonization. (author)

Methodology for the knowledge preservation in the CSN Proyecto RECO

Energy Technology Data Exchange (ETDEWEB)

Montero, M.A.; Gil, E.; Merino, C.; Gonzalez, N.

2016-07-01

This paper summarizes the RECOR Project carried out by the Spanish Nuclear Regulatory Authority (CSN) to develop a methodology to preserve nuclear knowledge, specifically adapted to the CSN regulatory functions. The project covers the development, implantation and verification of the methodology and the development necessary procedures and tools to align it with the CSN Integrated Management System. The Project is complemented with a number of sessions to motivate the CSN management with the methodology and training the staff in the use and Implementation of the methodology. (Author)

Bayesian methodology for generic seismic fragility evaluation of components in nuclear power plants

International Nuclear Information System (INIS)

Yamaguchi, Akira; Campbell, R.D.; Ravindra, M.K.

1991-01-01

Bayesian methodology for updating the seismic fragility of components in nuclear power plants is presented. The generic fragility data which have been evaluated based on the past SPSAs are combined with the seismic experience data. Although the seismic experience is limited to the acceleration range below the median capacity of the components, it has been found that the evidence is effective to update the fragility tail. In other words, the uncertainty of the fragility is reduced although the median capacity itself is not modified to a great extent. The annual frequency of failure is also reduced as a result of the updating of the fragility tail. The PDF of the seismic capacity is handled in discrete form, which enables the use of arbitrary type of prior distribution. Accordingly, the Log-N prior can be used which is consistent with the widely used fragility model. For evaluating posterior fragility parameters (A m and B U ), two methods have been proposed. Furthermore, it has been found that the importance of evidence used in the Bayesian methodology can be quantified by the entropy of the evidence. Only the events with high entropy need to be considered in the Bayesian updating of the fragility. The currently available seismic experience database for typical components can be utilized to develop the fragility tail which is contributive to the seismically-induced failure frequency. The combined use of generic fragility and seismic experience data, with the aid of Bayesian methodology, provides refined generic fragility curves which are useful for SPSA studies. (author)

Hipnose e dor: proposta de metodologia clínica e qualitativa de estudo Hypnosis and pain: proposal of a clinical and qualitative research methodology

Directory of Open Access Journals (Sweden)

Maurício da Silva Neubern

2009-08-01

Full Text Available O presente trabalho visa apresentar uma proposta metodológica clínica e qualitativa para o estudo da relação entre hipnose e dor. Inicialmente, critica-se a pretensão de atribuir legitimidade científica exclusivamente para propostas estatísticas sobre o tema. Em seguida, são destacados alguns pressupostos da metodologia clínica e qualitativa, como a construção da realidade e das informações, as dimensões estética e técnica da relação terapêutica e a concepção da dor enquanto processo subjetivo. Uma vinheta clínica é utilizada de forma ilustrativa de modo a destacar as etapas e processos da pesquisa, como o uso dos registros e os processos interpretativos. Conclui-se o artigo ressaltando que a pertinência dessa metodologia se dá, basicamente, por abordar a dimensão subjetiva da relação entre dor e hipnose e por conceber o contexto como um conjunto de processos que não devem ser isolados, mas integrados à pesquisa.The purpose of this work is to present a proposal of clinical and qualitative methodology for the study of the relationship between hypnosis and pain. Initially, the pretension of attributing scientific legitimacy exclusively to statistical approaches on the theme is criticized. Then, some premises of the clinical and qualitative methodology are underlined, such as the construction of reality and information, esthetic and technical dimensions of therapeutic relationship and conception of pain as a subjective process. An illustrative clinical vignette is used so as to highlight the steps and processes of the research, such as the use of records and interpretative processes. The article is concluded emphasizing that the pertinence of this methodology is, basically, on its approach of relationship subjective dimension between pain and hypnosis and in its conceiving of the context as a set of processes that should not be isolated, but integrated into the research.

Proliferation resistance and physical protection working group: methodology and applications

International Nuclear Information System (INIS)

Bari, Robert A.; Whitlock, Jeremy J.; Therios, Ike U.; Peterson, P.F.

2012-01-01

We summarize the technical progress and accomplishments on the evaluation methodology for proliferation resistance and physical protection (PR and PP) of Generation IV nuclear energy systems. We intend the results of the evaluations performed with the methodology for three types of users: system designers, program policy makers, and external stakeholders. The PR and PP Working Group developed the methodology through a series of demonstration and case studies. Over the past few years various national and international groups have applied the methodology to nuclear energy system designs as well as to developing approaches to advanced safeguards.

PROLIFERATION RESISTANCE AND PHYSICAL PROTECTION WORKING GROUP: METHODOLOGY AND APPLICATIONS

Energy Technology Data Exchange (ETDEWEB)

Bari R. A.; Whitlock, J.; Therios, I.U.; Peterson, P.F.

2012-11-14

We summarize the technical progress and accomplishments on the evaluation methodology for proliferation resistance and physical protection (PR and PP) of Generation IV nuclear energy systems. We intend the results of the evaluations performed with the methodology for three types of users: system designers, program policy makers, and external stakeholders. The PR and PP Working Group developed the methodology through a series of demonstration and case studies. Over the past few years various national and international groups have applied the methodology to nuclear energy system designs as well as to developing approaches to advanced safeguards.

Updated methodology for nuclear magnetic resonance characterization of shales

Science.gov (United States)

Washburn, Kathryn E.; Birdwell, Justin E.

2013-08-01

Unconventional petroleum resources, particularly in shales, are expected to play an increasingly important role in the world's energy portfolio in the coming years. Nuclear magnetic resonance (NMR), particularly at low-field, provides important information in the evaluation of shale resources. Most of the low-field NMR analyses performed on shale samples rely heavily on standard T1 and T2 measurements. We present a new approach using solid echoes in the measurement of T1 and T1-T2 correlations that addresses some of the challenges encountered when making NMR measurements on shale samples compared to conventional reservoir rocks. Combining these techniques with standard T1 and T2 measurements provides a more complete assessment of the hydrogen-bearing constituents (e.g., bitumen, kerogen, clay-bound water) in shale samples. These methods are applied to immature and pyrolyzed oil shale samples to examine the solid and highly viscous organic phases present during the petroleum generation process. The solid echo measurements produce additional signal in the oil shale samples compared to the standard methodologies, indicating the presence of components undergoing homonuclear dipolar coupling. The results presented here include the first low-field NMR measurements performed on kerogen as well as detailed NMR analysis of highly viscous thermally generated bitumen present in pyrolyzed oil shale.

Joint application of AI techniques, PRA and disturbance analysis methodology to problems in the maintenance and design of nuclear power plants

International Nuclear Information System (INIS)

Okrent, D.

1989-01-01

This final report summarizes the accomplishments of a two year research project entitled ''Joint Application of Artificial Intelligence Techniques, Probabilistic Risk Analysis, and Disturbance Analysis Methodology to Problems in the Maintenance and Design of Nuclear Power Plants. The objective of this project is to develop and apply appropriate combinations of techniques from artificial intelligence, (AI), reliability and risk analysis and disturbance analysis to well-defined programmatic problems of nuclear power plants. Reactor operations issues were added to those of design and maintenance as the project progressed

Joint application of AI techniques, PRA and disturbance analysis methodology to problems in the maintenance and design of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Okrent, D.

1989-03-01

This final report summarizes the accomplishments of a two year research project entitled Joint Application of Artificial Intelligence Techniques, Probabilistic Risk Analysis, and Disturbance Analysis Methodology to Problems in the Maintenance and Design of Nuclear Power Plants. The objective of this project is to develop and apply appropriate combinations of techniques from artificial intelligence, (AI), reliability and risk analysis and disturbance analysis to well-defined programmatic problems of nuclear power plants. Reactor operations issues were added to those of design and maintenance as the project progressed.

A preliminary study on the application of system dynamics methodology to organizational safety in nuclear power plants: Learning from past models

Energy Technology Data Exchange (ETDEWEB)

Do, Giang [Sol Bridge International School of Business, Daejeon (Korea, Republic of); Kim, Sakil; Lee, Yong Hee; Lee, Yong Hee [KAERI, Daejeon (Korea, Republic of)

2012-10-15

Besides technical design, organizational and human factor are of increasing interest in literature on nuclear safety. Among the methodologies employed to study these factors, System Dynamics (SD) is considered to be suitable for addressing the complexity and dynamicity of the organizational system in nuclear power plants (NPPs). In the following sections, the method will be described and its several prior applications to studying organizational safety will be introduced. An SD model with emphasis on the role of organizational learning in organizational safety will be presented.

MIRD methodology

International Nuclear Information System (INIS)

Rojo, Ana M.; Gomez Parada, Ines

2004-01-01

The MIRD (Medical Internal Radiation Dose) system was established by the Society of Nuclear Medicine of USA in 1960 to assist the medical community in the estimation of the dose in organs and tissues due to the incorporation of radioactive materials. Since then, 'MIRD Dose Estimate Report' (from the 1 to 12) and 'Pamphlets', of great utility for the dose calculations, were published. The MIRD system was planned essentially for the calculation of doses received by the patients during nuclear medicine diagnostic procedures. The MIRD methodology for the absorbed doses calculations in different tissues is explained

Status of Methodology Development for the Evaluation of Proliferation Resistance

International Nuclear Information System (INIS)

Lee, Yong Deok; Ko, Won Il; Lee, Jung Won

2010-01-01

Concerning the increasing energy demand and green house effect, nuclear energy is now the most feasible option. Therefore, recently, oil countries even have a plan to build the nuclear power plant for energy production. If nuclear systems are to make a major and sustainable contribution to the worlds energy supply, future nuclear energy systems must meet specific requirements. One of the requirements is to satisfy the proliferation resistance condition in an entire nuclear system. Therefore, from the beginning of future nuclear energy system development, it is important to consider a proliferation resistance to prevent the diversion of nuclear materials. The misuse of a nuclear system must be considered as well. Moreover, in the import and export of nuclear system, the evaluation of the proliferation resistance on the nuclear system becomes a key factor The INPRO (International Project on Innovative Nuclear Reactors and Fuel Cycles) program initiated by the IAEA proposed proliferation resistance (PR) as a key component of a future innovative nuclear system (INS) with a sustainability, economics, safety of nuclear installation and waste management. The technical goal for Generation IV (Gen IV) nuclear energy systems (NESs) highlights a Proliferation Resistance and Physical Protection (PR and PP), sustainability, safety, reliability and economics as well. Based on INPRO and Gen IV study, the methodology development for the evaluation of proliferation resistance has been carried out in KAERI. Finally, the systematic procedure for methodology was setup and the indicators for the procedure were decided. The methodology involves the evaluation from total nuclear system to individual process. Therefore, in this study, the detailed procedure for the evaluation of proliferation resistance and the newly proposed additional indicators are described and several conditions are proposed to increase the proliferation resistance in the future nuclear system. The assessment of PR

Principle and methodology of nuclear power plant site selection. Application to radiocobalt cycle in the Rhone river

International Nuclear Information System (INIS)

Georges, J.

1987-01-01

In a first bibliographic part, after some generalities on radioactivity and nuclear power, general principles of radiation protection and national and international regulations are presented. The methodology of the radioecological study involved in site selection is developed. In a second more experimental part, the processing of radiocobalt gamma radioactivity measurement in water, fishes, plants and Rhone river sediments demonstrates the influence of age and geographical situation of the nuclear power stations located along the river. A laboratory experiment of cobalt 60 transfer from chironomes larvae to carp is carried out. Comparison with the results of other laboratory experiments makes it possible to propose an experimental model of cobalt transfer within a fresh water ecosystem; radioactivity levels calculated for various compartments seem to be consistent with the Rhone river levels [fr

Disposal criticality analysis methodology's principal isotope burnup credit

International Nuclear Information System (INIS)

Doering, T.W.; Thomas, D.A.

2001-01-01

This paper presents the burnup credit aspects of the United States Department of Energy Yucca Mountain Project's methodology for performing criticality analyses for commercial light-water-reactor fuel. The disposal burnup credit methodology uses a 'principal isotope' model, which takes credit for the reduced reactivity associated with the build-up of the primary principal actinides and fission products in irradiated fuel. Burnup credit is important to the disposal criticality analysis methodology and to the design of commercial fuel waste packages. The burnup credit methodology developed for disposal of irradiated commercial nuclear fuel can also be applied to storage and transportation of irradiated commercial nuclear fuel. For all applications a series of loading curves are developed using a best estimate methodology and depending on the application, an additional administrative safety margin may be applied. The burnup credit methodology better represents the 'true' reactivity of the irradiated fuel configuration, and hence the real safety margin, than do evaluations using the 'fresh fuel' assumption. (author)

Applicability of the Directed Graph Methodology

Energy Technology Data Exchange (ETDEWEB)

Huszti, Jozsef [Institute of Isotope of the Hungarian Academy of Sciences, Budapest (Hungary); Nemeth, Andras [ESRI Hungary, Budapest (Hungary); Vincze, Arpad [Hungarian Atomic Energy Authority, Budapest (Hungary)

2012-06-15

Possible methods to construct, visualize and analyse the 'map' of the State's nuclear infrastructure based on different directed graph approaches are proposed. The transportation and the flow network models are described in detail. The use of the possible evaluation methodologies and the use of available software tools to construct and maintain the nuclear 'map' using pre-defined standard building blocks (nuclear facilities) are introduced and discussed.

Comparison of methodologies for assessing the risks from nuclear weapons and from nuclear reactors

International Nuclear Information System (INIS)

Benjamin, A.S.

1996-01-01

There are important differences between the safety principles for nuclear weapons and for nuclear reactors. For example, a principal concern for nuclear weapons is to prevent electrical energy from reaching the nuclear package during accidents produced by crashes, fires, and other hazards, whereas the foremost concern for nuclear reactors is to maintain coolant around the core in the event of certain system failures. Not surprisingly, new methods have had to be developed to assess the risk from nuclear weapons. These include fault tree transformations that accommodate time dependencies, thermal and structural analysis techniques that are fast and unconditionally stable, and parameter sampling methods that incorporate intelligent searching. This paper provides an overview of the new methods for nuclear weapons and compares them with existing methods for nuclear reactors. It also presents a new intelligent searching process for identifying potential nuclear detonation vulnerabilities. The new searching technique runs very rapidly on a workstation and shows promise for providing an accurate assessment of potential vulnerabilities with far fewer physical response calculations than would be required using a standard Monte Carlo sampling procedure

Methodology for advanced control rooms assessment of nuclear reactors: case study using Laboratory of Human System Interface (LABIHS)

International Nuclear Information System (INIS)

Carvalho, Eduardo Ferro; Verboonen, Monique; Carvalho, Bruno Batista de

2005-01-01

A control room of a nuclear reactor is a complex system that controls a thermodynamic process used to produce electric energy. The operators interact with the control room through interfaces and several monitoring stations. These interfaces present significant implications for the safety of the nuclear power plant, once they influence the activities of the operators, affect the way how operators receive information related with the status from the main systems and determine the necessary requirements so that the operators understand and supervise the main parameters. This article intends to present the methodology and the results of the evaluation carried through in the advanced control room of a compact simulator, that uses as reference a nuclear plant PWR of the Westinghouse. The structure used for evaluation of the simulator is formed by the guideline of human factors of the NRC, the NUREG 700, checklist, questionnaires and the analysis of the operator's activity. (author)

A Methodology To Incorporate The Safety Culture Into Probabilistic Safety Assessments

Energy Technology Data Exchange (ETDEWEB)

Park, Sunghyun; Kim, Namyeong; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of)

2015-10-15

In order to incorporate organizational factors into PSA, a methodology needs to be developed. Using the AHP to weigh organizational factors as well as the SLIM to rate those factors, a methodology is introduced in this study. The safety issues related to nuclear safety culture have occurred increasingly. The quantification tool has to be developed in order to include the organizational factor into Probabilistic Safety Assessments. In this study, the state-of-the-art for the organizational evaluation methodologies has been surveyed. This study includes the research for organizational factors, maintenance process, maintenance process analysis models, a quantitative methodology using Analytic Hierarchy Process, Success Likelihood Index Methodology. The purpose of this study is to develop a methodology to incorporate the safety culture into PSA for obtaining more objective risk than before. The organizational factor considered in nuclear safety culture might affect the potential risk of human error and hardware-failure. The safety culture impact index to monitor the plant safety culture can be assessed by applying the developed methodology into a nuclear power plant.

A Methodology To Incorporate The Safety Culture Into Probabilistic Safety Assessments

International Nuclear Information System (INIS)

Park, Sunghyun; Kim, Namyeong; Jae, Moosung

2015-01-01

In order to incorporate organizational factors into PSA, a methodology needs to be developed. Using the AHP to weigh organizational factors as well as the SLIM to rate those factors, a methodology is introduced in this study. The safety issues related to nuclear safety culture have occurred increasingly. The quantification tool has to be developed in order to include the organizational factor into Probabilistic Safety Assessments. In this study, the state-of-the-art for the organizational evaluation methodologies has been surveyed. This study includes the research for organizational factors, maintenance process, maintenance process analysis models, a quantitative methodology using Analytic Hierarchy Process, Success Likelihood Index Methodology. The purpose of this study is to develop a methodology to incorporate the safety culture into PSA for obtaining more objective risk than before. The organizational factor considered in nuclear safety culture might affect the potential risk of human error and hardware-failure. The safety culture impact index to monitor the plant safety culture can be assessed by applying the developed methodology into a nuclear power plant

United States Department of Energy's reactor core protection evaluation methodology for fires at RBMK and VVER nuclear power plants. Revision 1

International Nuclear Information System (INIS)

1997-06-01

This document provides operators of Soviet-designed RBMK (graphite moderated light water boiling water reactor) and VVER (pressurized light water reactor) nuclear power plants with a systematic Methodology to qualitatively evaluate plant response to fires and to identify remedies to protect the reactor core from fire-initiated damage

GPS system simulation methodology

Science.gov (United States)

Ewing, Thomas F.

1993-01-01

The following topics are presented: background; Global Positioning System (GPS) methodology overview; the graphical user interface (GUI); current models; application to space nuclear power/propulsion; and interfacing requirements. The discussion is presented in vugraph form.

Study on an ISO 15926 based data modeling methodology for nuclear power industry

Energy Technology Data Exchange (ETDEWEB)

Cheon, Yang Ho; Park, Byeong Ho; Park, Seong Chan; Kim, Eun Kee [KEPCO E-C, Yongin (Korea, Republic of)

2014-10-15

The scope is therefore data integration and data to support the whole life of a plant. This representation is specified by a generic, conceptual Data Model (DM) that is independent of any particular application, but that is able to record data from the applications used in plant design, fabrication and operation. The data model is designed to be used in conjunction with Reference Data (RD): standard instances of the DM that represent information common to a number of users, plants, or both. This paper introduces a high level description of the structure of ISO 15926 and how this can be adapted to the nuclear power plant industry in particular. This paper introduces ISO 15926 methodology and how to extend the existing RDL for nuclear power industry. As the ISO 15926 representation is independent of applications, interfaces to existing or future applications have to be developed. Such interfaces are provided by Templates that takes input from external sources and 'lifts' it into an ISO 15926 repository, and/or 'lowers' the data into other applications. This is a similar process to the process defined by W3C. Data exchange can be done using e.g. XML messages, but the modelling is independent of technology used for the exchange.

Nuclear data adjustment methodology utilizing resonance parameter sensitivities and uncertainties

International Nuclear Information System (INIS)

Broadhead, B.L.

1983-01-01

This work presents the development and demonstration of a Nuclear Data Adjustment Method that allows inclusion of both energy and spatial self-shielding into the adjustment procedure. The resulting adjustments are for the basic parameters (i.e. resonance parameters) in the resonance regions and for the group cross sections elsewhere. The majority of this development effort concerns the production of resonance parameter sensitivity information which allows the linkage between the responses of interest and the basic parameters. The resonance parameter sensitivity methodology developed herein usually provides accurate results when compared to direct recalculations using existng and well-known cross section processing codes. However, it has been shown in several cases that self-shielded cross sections can be very non-linear functions of the basic parameters. For this reason caution must be used in any study which assumes that a linear relatonship exists between a given self-shielded group cross section and its corresponding basic data parameters. The study also has pointed out the need for more approximate techniques which will allow the required sensitivity information to be obtained in a more cost effective manner

A human error probability estimate methodology based on fuzzy inference and expert judgment on nuclear plants

International Nuclear Information System (INIS)

Nascimento, C.S. do; Mesquita, R.N. de

2009-01-01

Recent studies point human error as an important factor for many industrial and nuclear accidents: Three Mile Island (1979), Bhopal (1984), Chernobyl and Challenger (1986) are classical examples. Human contribution to these accidents may be better understood and analyzed by using Human Reliability Analysis (HRA), which has being taken as an essential part on Probabilistic Safety Analysis (PSA) of nuclear plants. Both HRA and PSA depend on Human Error Probability (HEP) for a quantitative analysis. These probabilities are extremely affected by the Performance Shaping Factors (PSF), which has a direct effect on human behavior and thus shape HEP according with specific environment conditions and personal individual characteristics which are responsible for these actions. This PSF dependence raises a great problem on data availability as turn these scarcely existent database too much generic or too much specific. Besides this, most of nuclear plants do not keep historical records of human error occurrences. Therefore, in order to overcome this occasional data shortage, a methodology based on Fuzzy Inference and expert judgment was employed in this paper in order to determine human error occurrence probabilities and to evaluate PSF's on performed actions by operators in a nuclear power plant (IEA-R1 nuclear reactor). Obtained HEP values were compared with reference tabled data used on current literature in order to show method coherence and valid approach. This comparison leads to a conclusion that this work results are able to be employed both on HRA and PSA enabling efficient prospection of plant safety conditions, operational procedures and local working conditions potential improvements (author)

Assessment of ISLOCA risk: Methodology and application to a Babcock and Wilcox nuclear power plant

International Nuclear Information System (INIS)

Galyean, W.J.; Gertman, D.I.

1992-04-01

This report presents information essential to understanding the risk associated with inter-system loss-of-coolant accidents (ISLOCAs). The methodology developed and presented in the report provides a state-of-the-art method for identifying and evaluating plant-specific hardware design, human performance issues, and accident consequence factors to relevant to the prediction of the ISLOCA risk. This ISLOCA methodology was developed and then applied to a Babcock and Wilcox (B ampersand W) nuclear power plants. The results from this application are described in detail. For this particular B ampersand W reference plant, the assessment indicated that the probability of a severe ISLOCA is approximately 2.2E-06/reactor-year. This document Volume 3 provides appendices A--H of the report. Topics are: Historical experience related to ISLOCA events; component failure rates; reference B ampersand W plant system descriptions; reference B ampersand W plant ISLOCA event trees; Human reliability analysis for the B ampersand W ISLOCA probabilistic risk assessment; thermal hydraulic calculations; bounding core uncovery time calculations; and system rupture probability

A technology-assessment methodology for electric utility planning: With application to nuclear power plant decommissioning

International Nuclear Information System (INIS)

Lough, W.T.

1987-01-01

Electric utilities and public service commissions have not taken full advantage of the many proven methodologies and techniques available for evaluating complex technological issues. In addition, evaluations performed are deficient in their use of (1) methods for evaluating public attitudes and (2) formal methods of analysis for decision making. These oversight are substantiated through an examination of the literature relevant to electric utility planning. The assessment process known as technology assessment or TA is proposed, and a TA model is developed for route in use in utility planning by electric utilities and state regulatory commissions. Techniques to facilitate public participation and techniques to aid decision making are integral to the proposed model and are described in detail. Criteria are provided for selecting an appropriate technique on a case-by-case basis. The TA model proved to be an effective methodology for evaluating technological issues associated with electric utility planning such as decommissioning nuclear power plants. Through the use of the nominal group technique, the attitudes of a group of residential ratepayers were successfully identified and included in the decision-making process

Using proliferation assessment methodologies for Safeguards-by-Design

International Nuclear Information System (INIS)

Van der Meer, K.; Rossa, R.; Turcanu, C.; Borella, A.

2013-01-01

MYRRHA, an accelerator driven system (ADS) is designed as a proton accelerator coupled to a liquid Pb-Bi spallation target, surrounded by a Pb-Bi cooled sub-critical neutron multiplying medium in a pool type configuration. An assessment based on three methodologies was made of the proliferation risks of the MYRRHA ADS in comparison with the BR2 MTR, an existing research reactor at the Belgian Nuclear Research Centre SCK-CEN. The used methodologies were the TOPS (Technical Opportunities to Increase the Proliferation Resistance of Nuclear Power Systems), the PR-PP and the INPRO methodologies. The various features of the methodologies are described and the results of the assessments are given and discussed. It is concluded that it would be useful to define one single methodology with two options to perform a quick and a more detailed assessment. The paper is followed by the slides of the presentation

O tratamento farmacológico do transtorno bipolar: uma revisão sistemática e crítica dos aspectos metodológicos dos estudos clínicos modernos The pharmacological treatment of bipolar disorder: a systematic and critical review of the methodological aspects of modern clinical trials

Directory of Open Access Journals (Sweden)

Elie Cheniaux

2011-03-01

Full Text Available OBJETIVO: Revisar sistematicamente os principais estudos clínicos sobre o tratamento farmacológico do transtorno bipolar e fazer uma análise crítica de seus aspectos metodológicos. MÉTODO: Realizou-se uma busca nas bases de dados Medline, ISI e PsycINFO, utilizando-se os seguintes termos de busca: "bipolar", "randomized", "placebo" e "controlled". Foram selecionados estudos clínicos randomizados, duplo-cegos e controlados por placebo sobre o tratamento farmacológico do transtorno bipolar. Além disso, de acordo com os nossos critérios, as amostras deveriam ser de no mínimo 100 pacientes e a substância testada deveria ser usada como monoterapia. RESULTADOS: 34 artigos se adequaram aos critérios de seleção. Todas as substâncias atualmente indicadas para mania, depressão bipolar e para o tratamento de manutenção foram mais eficazes que o placebo em pelo menos um estudo. Todavia, esses estudos tiveram amostras altamente selecionadas, altas taxas de abandono e baixas taxas de resposta clínica. CONCLUSÃO: Os modernos estudos clínicos sobre o tratamento farmacológico do transtorno bipolar apresentam algumas importantes limitações metodológicas. Assim, seus resultados devem ser considerados com cautela.OBJECTIVE: To review systematically the main clinical trials on the pharmacological treatment of bipolar disorder and to make a critical analysis of their methodological aspects. METHOD: A search in Medline, ISI and PsycINFO databases was conducted, using the following search terms: "bipolar", "randomized", "placebo" e "controlled". Randomized, double-blind, placebo-controlled clinical trials on the pharmacological treatment of bipolar disorder were selected. Besides, according to our criteria, samples had to consist of at least 100 patients and experimental drug had to be used as monotherapy. RESULTS: 34 articles met our selection criteria. All drugs currently indicated for mania, bipolar depression and maintenance treatment of

Nuclear power generation cost methodology

International Nuclear Information System (INIS)

Delene, J.G.; Bowers, H.I.

1980-08-01

A simplified calculational procedure for the estimation of nuclear power generation cost is outlined. The report contains a discussion of the various components of power generation cost and basic equations for calculating that cost. An example calculation is given. The basis of the fixed-charge rate, the derivation of the levelized fuel cycle cost equation, and the heavy water charge rate are included as appendixes

Application of best estimate and uncertainty safety analysis methodology to loss of flow events at Ontario's Power Generation's Darlington Nuclear Generating Station

International Nuclear Information System (INIS)

Huget, R.G.; Lau, D.K.; Luxat, J.C.

2001-01-01

Ontario Power Generation (OPG) is currently developing a new safety analysis methodology based on best estimate and uncertainty (BEAU) analysis. The framework and elements of the new safety analysis methodology are defined. The evolution of safety analysis technology at OPG has been thoroughly documented. Over the years, the use of conservative limiting assumptions in OPG safety analyses has led to gradual erosion of predicted safety margins. The main purpose of the new methodology is to provide a more realistic quantification of safety margins within a probabilistic framework, using best estimate results, with an integrated accounting of the underlying uncertainties. Another objective of the new methodology is to provide a cost-effective means for on-going safety analysis support of OPG's nuclear generating stations. Discovery issues and plant aging effects require that the safety analyses be periodically revised and, in the past, the cost of reanalysis at OPG has been significant. As OPG enters the new competitive marketplace for electricity, there is a strong need to conduct safety analysis in a less cumbersome manner. This paper presents the results of the first licensing application of the new methodology in support of planned design modifications to the shutdown systems (SDSs) at Darlington Nuclear Generating Station (NGS). The design modifications restore dual trip parameter coverage over the full range of reactor power for certain postulated loss-of-flow (LOF) events. The application of BEAU analysis to the single heat transport pump trip event provides a realistic estimation of the safety margins for the primary and backup trip parameters. These margins are significantly larger than those predicted by conventional limit of the operating envelope (LOE) analysis techniques. (author)

Methodology for the unconditional clearance of residual materials

International Nuclear Information System (INIS)

Rodriguez Gomez, M. A.; Gonzalez Gandal, R.; Garcia Acosta, F.; Gonzalez Crespo, M.

2011-01-01

This document is aimed to present a methodology for materials through its declassification conventional management and that it can be used by all Spanish nuclear plants, once approved by the Consejo de Seguridad Nuclear.

Three-dimensional RAMA fluence methodology benchmarking

International Nuclear Information System (INIS)

Baker, S. P.; Carter, R. G.; Watkins, K. E.; Jones, D. B.

2004-01-01

This paper describes the benchmarking of the RAMA Fluence Methodology software, that has been performed in accordance with U. S. Nuclear Regulatory Commission Regulatory Guide 1.190. The RAMA Fluence Methodology has been developed by TransWare Enterprises Inc. through funding provided by the Electric Power Research Inst., Inc. (EPRI) and the Boiling Water Reactor Vessel and Internals Project (BWRVIP). The purpose of the software is to provide an accurate method for calculating neutron fluence in BWR pressure vessels and internal components. The Methodology incorporates a three-dimensional deterministic transport solution with flexible arbitrary geometry representation of reactor system components, previously available only with Monte Carlo solution techniques. Benchmarking was performed on measurements obtained from three standard benchmark problems which include the Pool Criticality Assembly (PCA), VENUS-3, and H. B. Robinson Unit 2 benchmarks, and on flux wire measurements obtained from two BWR nuclear plants. The calculated to measured (C/M) ratios range from 0.93 to 1.04 demonstrating the accuracy of the RAMA Fluence Methodology in predicting neutron flux, fluence, and dosimetry activation. (authors)

Nuclear moments

CERN Document Server

Kopferman, H; Massey, H S W

1958-01-01

Nuclear Moments focuses on the processes, methodologies, reactions, and transformations of molecules and atoms, including magnetic resonance and nuclear moments. The book first offers information on nuclear moments in free atoms and molecules, including theoretical foundations of hyperfine structure, isotope shift, spectra of diatomic molecules, and vector model of molecules. The manuscript then takes a look at nuclear moments in liquids and crystals. Discussions focus on nuclear paramagnetic and magnetic resonance and nuclear quadrupole resonance. The text discusses nuclear moments and nucl

Application of the methodology of safety probabilistic analysis to the modelling the emergency feedwater system of Juragua nuclear power plant

International Nuclear Information System (INIS)

Troncoso, M.; Oliva, G.

1993-01-01

The application of the methodology developed in the framework of the national plan of safety probabilistic analysis (APS) to the emergency feed water system for the failures of small LOCAS and external electrical supply loss in the nuclear power plant is illustrated in this work. The facilities created by the ARCON code to model the systems and its documentation are also expounded

Development of assessment methodology for plant configuration control

Energy Technology Data Exchange (ETDEWEB)

Chung, Chang Hyun; You, Young Woo; Kim, Yoon Ik; Yang, Hui Chang; Huh, Byeong Gill; Lee, Dong Won; Ahn, Gwan Won [Seoul National Univ., Seoul (Korea, Republic of)

2001-03-15

The purpose of this study IS the development of effective and overall assessment methodology which reflects the characteristics of plants for the surveillance, maintenance, repair and operation of nuclear power plants. In this study, recent researches are surveyed and concept definition, procedures, current PSA methodologies, implementation of various models are evaluated. Through this survey, systematic assessment methodology is suggested. Configuration control assessment methodology suggested in this study for the purpose of the development of configuration control methodology reflecting the characteristics of Korean NPPs, can be utilized as the supplement of current PSA methodologies.

Intersystem LOCA risk assessment: methodology and results

International Nuclear Information System (INIS)

Galyean, W.J.; Kelly, D.L.; Schroeder, J.A.; Auflick, L.J.; Blackman, H.S.; Gertman, D.I.; Hanley, L.N.

1994-01-01

The United States Nuclear Regulatory Commission is sponsoring a research program to develop an improved understanding of the human factors, hardware and accident consequence issues that dominate the risk from an intersystem loss-of-coolant accident (ISLOCA) at a nuclear power plant. To accomplish the goals of this program, a mehtodology has been developed for estimating ISLOCA core damage frequency and risk. The steps in this methodology are briefly described, along with the results obtained from an application of the methodology at three pressurized water reactors. Also included are the results of a screening study of boiling water reactors. ((orig.))

A methodology to analize the safety of a coastal nuclear power plant against the Typhoon external flooding risks

International Nuclear Information System (INIS)

Chen Tian; He Mi; Chen Guofei; Joly, Antoine; Pan Rong; Ji Ping

2015-01-01

For the protection of coastal Nuclear Power Plant (NPP) against the external flooding hazard, the risks caused by natural events have to be taken into account. In this article, a methodology is proposed to analyze the risk of the typical natural event in China (Typhoon). It includes the simulation of the storm surge and the strong waves due to its passage in Chinese coastal zones and the quantification of the sequential overtopping flow rate. The simulation is carried out by coupling 2 modules of the hydraulic modeling system TELEMAC-MASCARET from EDF, TELEMAC2D (Shallow water module) and TOMAWAC (spectral wave module). As an open-source modeling system, this methodology could still be enriched by other phenomena in the near future to ameliorate its performance in safety analysis of the coastal NPPs in China. (author)

Development of assessment methodology for plant configuration control

Energy Technology Data Exchange (ETDEWEB)

Cheong, Chang Hyeon; Yu, Yeong Woo; Cho, Jae Seon; Kim, Ju Yeol; Kim, Yun Ik; Yang, Hui Chang; Park, Gang Min; Hur, Byeong Gil [Seoul National Univ., Seoul (Korea, Republic of)

1999-03-15

The purpose of this study is the development of effective and overall assessment methodology which reflects the characteristics of plants for the surveillance, maintenance, repair and operation of Nuclear Power Plant. The development of this methodology can contribute to enhance safety. In the first year of this study, recent researches are surveyed and concept definition, procedures, current PSA methodologies, implementation of various models are evaluated. Through this survey, systematic assessment methodology is suggested.

Methodological Proposal for Identification and Evaluation of Environmental Aspects and Impacts of IPEN Nuclear Facilities: A Case Study Applied to the Nuclear Fuel Center

International Nuclear Information System (INIS)

Mattos, Luis A. Terribile de; Filho, Tufic Madi; Meldonian, Nelson Leon

2013-06-01

This work presents an application of Failure Mode Effect Analysis (FMEA) to the process of identification of environmental aspects and impacts as a part of implementation and maintenance of an Environmental Management System (EMS) in accordance with the ISO 14001 standard. Also, it can contribute, as a complement, to the evaluation and improvement of safety of the installation focused. The study was applied to the Nuclear Fuel Center (CCN) of Nuclear and Energy Research Institute (IPEN), situated at the Campus of University of Sao Paulo, Brazil. The CCN facility has the objective of promoting scientific research and of producing nuclear fuel elements for the IEA-R1 Research Reactor. To identify the environmental aspects of the facility activities, products, and services, a systematic data collection was carried out by means of personal interviews, documents, reports and operation data records consulting. Furthermore, the processes and their interactions, failure modes, besides their causes and effects to the environment, were identified. As a result of a careful evaluation of these causes it was possible to identify and to classify the major potential environmental impacts, in order to set up and put in practice an Environmental Control Plan for the installation under study. The results have demonstrated the validity of the FMEA application to nuclear facility processes, identifying environmental aspects and impacts, whose controls are critical to achieve compliance with the environmental requirements of the Integrated Management System of IPEN. It was demonstrated that the methodology used in this work is a powerful management tool for resolving issues related to the conformity with applicable regulatory and legal requirements of the Brazilian Nuclear Energy Commission (CNEN) and the Brazilian Institute of Environment (IBAMA). (authors)

Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Safety of nuclear fuel cycle facilities. Vol. 9 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Nuclear Information System (INIS)

2008-11-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. The INPRO manual is comprised of an overview volume (No. 1), and eight additional volumes covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of nuclear reactors (Volume 8), and safety of nuclear fuel cycle facilities (laid out in this report) (Volume 9).This report elaborates on the guidance given in the INPRO report 'Methodology for the assessment of innovative nuclear reactors and fuel cycles', IAEA-TECDOC-1434, and the previous INPRO report 'Guidance for the evaluation for innovative nuclear reactors and fuel cycles', IAEA-TECDOC-1362 (2003), in the area of safety of nuclear reactors. The present version of this manual deals with safety issues related to design and operation of mining, milling, refining, conversion, enrichment, fuel fabrication, fuel storage and fuel reprocessing facilities. The INPRO Manual starts with an introduction in Chapter 1. Chapter 2 sets out the necessary input for an INPRO assessment of the safety of an innovative nuclear fuel cycle facility. This includes information on the design for the plant and the safety

A design methodology for unattended monitoring systems

International Nuclear Information System (INIS)

SMITH, JAMES D.; DELAND, SHARON M.

2000-01-01

The authors presented a high-level methodology for the design of unattended monitoring systems, focusing on a system to detect diversion of nuclear materials from a storage facility. The methodology is composed of seven, interrelated analyses: Facility Analysis, Vulnerability Analysis, Threat Assessment, Scenario Assessment, Design Analysis, Conceptual Design, and Performance Assessment. The design of the monitoring system is iteratively improved until it meets a set of pre-established performance criteria. The methodology presented here is based on other, well-established system analysis methodologies and hence they believe it can be adapted to other verification or compliance applications. In order to make this approach more generic, however, there needs to be more work on techniques for establishing evaluation criteria and associated performance metrics. They found that defining general-purpose evaluation criteria for verifying compliance with international agreements was a significant undertaking in itself. They finally focused on diversion of nuclear material in order to simplify the problem so that they could work out an overall approach for the design methodology. However, general guidelines for the development of evaluation criteria are critical for a general-purpose methodology. A poor choice in evaluation criteria could result in a monitoring system design that solves the wrong problem

Go-flow: a reliability analysis methodology applicable to piping system

International Nuclear Information System (INIS)

Matsuoka, T.; Kobayashi, M.

1985-01-01

Since the completion of the Reactor Safety Study, the use of probabilistic risk assessment technique has been becoming more widespread in the nuclear community. Several analytical methods are used for the reliability analysis of nuclear power plants. The GO methodology is one of these methods. Using the GO methodology, the authors performed a reliability analysis of the emergency decay heat removal system of the nuclear ship Mutsu, in order to examine its applicability to piping systems. By this analysis, the authors have found out some disadvantages of the GO methodology. In the GO methodology, the signal is on-to-off or off-to-on signal, therefore the GO finds out the time point at which the state of a system changes, and can not treat a system which state changes as off-on-off. Several computer runs are required to obtain the time dependent failure probability of a system. In order to overcome these disadvantages, the authors propose a new analytical methodology: GO-FLOW. In GO-FLOW, the modeling method (chart) and the calculation procedure are similar to those in the GO methodology, but the meaning of signal and time point, and the definitions of operators are essentially different. In the paper, the GO-FLOW methodology is explained and two examples of the analysis by GO-FLOW are given

Joint application of AI techniques, PRA and disturbance analysis methodology to problems in the maintenance and design of nuclear power plants. Final report

Energy Technology Data Exchange (ETDEWEB)

Okrent, D.

1989-03-01

This final report summarizes the accomplishments of a two year research project entitled ``Joint Application of Artificial Intelligence Techniques, Probabilistic Risk Analysis, and Disturbance Analysis Methodology to Problems in the Maintenance and Design of Nuclear Power Plants. The objective of this project is to develop and apply appropriate combinations of techniques from artificial intelligence, (AI), reliability and risk analysis and disturbance analysis to well-defined programmatic problems of nuclear power plants. Reactor operations issues were added to those of design and maintenance as the project progressed.

Development of a systematic methodology to select hazard analysis techniques for nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Vasconcelos, Vanderley de; Reis, Sergio Carneiro dos; Costa, Antonio Carlos Lopes da [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)]. E-mails: vasconv@cdtn.br; reissc@cdtn.br; aclc@cdtn.br; Jordao, Elizabete [Universidade Estadual de Campinas (UNICAMP), SP (Brazil). Faculdade de Engenharia Quimica]. E-mail: bete@feq.unicamp.br

2008-07-01

In order to comply with licensing requirements of regulatory bodies risk assessments of nuclear facilities should be carried out. In Brazil, such assessments are part of the Safety Analysis Reports, required by CNEN (Brazilian Nuclear Energy Commission), and of the Risk Analysis Studies, required by the competent environmental bodies. A risk assessment generally includes the identification of the hazards and accident sequences that can occur, as well as the estimation of the frequencies and effects of these unwanted events on the plant, people, and environment. The hazard identification and analysis are also particularly important when implementing an Integrated Safety, Health, and Environment Management System following ISO 14001, BS 8800 and OHSAS 18001 standards. Among the myriad of tools that help the process of hazard analysis can be highlighted: CCA (Cause- Consequence Analysis); CL (Checklist Analysis); ETA (Event Tree Analysis); FMEA (Failure Mode and Effects Analysis); FMECA (Failure Mode, Effects and Criticality Analysis); FTA (Fault Tree Analysis); HAZOP (Hazard and Operability Study); HRA (Human Reliability Analysis); Pareto Analysis; PHA (Preliminary Hazard Analysis); RR (Relative Ranking); SR (Safety Review); WI (What-If); and WI/CL (What-If/Checklist Analysis). The choice of a particular technique or a combination of techniques depends on many factors like motivation of the analysis, available data, complexity of the process being analyzed, expertise available on hazard analysis, and initial perception of the involved risks. This paper presents a systematic methodology to select the most suitable set of tools to conduct the hazard analysis, taking into account the mentioned involved factors. Considering that non-reactor nuclear facilities are, to a large extent, chemical processing plants, the developed approach can also be applied to analysis of chemical and petrochemical plants. The selected hazard analysis techniques can support cost

Development of a systematic methodology to select hazard analysis techniques for nuclear facilities

International Nuclear Information System (INIS)

Vasconcelos, Vanderley de; Reis, Sergio Carneiro dos; Costa, Antonio Carlos Lopes da; Jordao, Elizabete

2008-01-01

In order to comply with licensing requirements of regulatory bodies risk assessments of nuclear facilities should be carried out. In Brazil, such assessments are part of the Safety Analysis Reports, required by CNEN (Brazilian Nuclear Energy Commission), and of the Risk Analysis Studies, required by the competent environmental bodies. A risk assessment generally includes the identification of the hazards and accident sequences that can occur, as well as the estimation of the frequencies and effects of these unwanted events on the plant, people, and environment. The hazard identification and analysis are also particularly important when implementing an Integrated Safety, Health, and Environment Management System following ISO 14001, BS 8800 and OHSAS 18001 standards. Among the myriad of tools that help the process of hazard analysis can be highlighted: CCA (Cause- Consequence Analysis); CL (Checklist Analysis); ETA (Event Tree Analysis); FMEA (Failure Mode and Effects Analysis); FMECA (Failure Mode, Effects and Criticality Analysis); FTA (Fault Tree Analysis); HAZOP (Hazard and Operability Study); HRA (Human Reliability Analysis); Pareto Analysis; PHA (Preliminary Hazard Analysis); RR (Relative Ranking); SR (Safety Review); WI (What-If); and WI/CL (What-If/Checklist Analysis). The choice of a particular technique or a combination of techniques depends on many factors like motivation of the analysis, available data, complexity of the process being analyzed, expertise available on hazard analysis, and initial perception of the involved risks. This paper presents a systematic methodology to select the most suitable set of tools to conduct the hazard analysis, taking into account the mentioned involved factors. Considering that non-reactor nuclear facilities are, to a large extent, chemical processing plants, the developed approach can also be applied to analysis of chemical and petrochemical plants. The selected hazard analysis techniques can support cost

A parallel multi-domain solution methodology applied to nonlinear thermal transport problems in nuclear fuel pins

Energy Technology Data Exchange (ETDEWEB)

Philip, Bobby, E-mail: philipb@ornl.gov [Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831 (United States); Berrill, Mark A.; Allu, Srikanth; Hamilton, Steven P.; Sampath, Rahul S.; Clarno, Kevin T. [Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831 (United States); Dilts, Gary A. [Los Alamos National Laboratory, PO Box 1663, Los Alamos, NM 87545 (United States)

2015-04-01

This paper describes an efficient and nonlinearly consistent parallel solution methodology for solving coupled nonlinear thermal transport problems that occur in nuclear reactor applications over hundreds of individual 3D physical subdomains. Efficiency is obtained by leveraging knowledge of the physical domains, the physics on individual domains, and the couplings between them for preconditioning within a Jacobian Free Newton Krylov method. Details of the computational infrastructure that enabled this work, namely the open source Advanced Multi-Physics (AMP) package developed by the authors is described. Details of verification and validation experiments, and parallel performance analysis in weak and strong scaling studies demonstrating the achieved efficiency of the algorithm are presented. Furthermore, numerical experiments demonstrate that the preconditioner developed is independent of the number of fuel subdomains in a fuel rod, which is particularly important when simulating different types of fuel rods. Finally, we demonstrate the power of the coupling methodology by considering problems with couplings between surface and volume physics and coupling of nonlinear thermal transport in fuel rods to an external radiation transport code.

Modelling of nuclear power plant decommissioning financing.

Science.gov (United States)

Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

2015-06-01

Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Risk-Informed Assessment Methodology Development and Application

International Nuclear Information System (INIS)

Sung Goo Chi; Seok Jeong Park; Chul Jin Choi; Ritterbusch, S.E.; Jacob, M.C.

2002-01-01

Westinghouse Electric Company (WEC) has been working with Korea Power Engineering Company (KOPEC) on a US Department of Energy (DOE) sponsored Nuclear Energy Research Initiative (NERI) project through a collaborative agreement established for the domestic NERI program. The project deals with Risk-Informed Assessment (RIA) of regulatory and design requirements of future nuclear power plants. An objective of the RIA project is to develop a risk-informed design process, which focuses on identifying and incorporating advanced features into future nuclear power plants (NPPs) that would meet risk goals in a cost-effective manner. The RIA design methodology is proposed to accomplish this objective. This paper discusses the development of this methodology and demonstrates its application in the design of plant systems for future NPPs. Advanced conceptual plant systems consisting of an advanced Emergency Core Cooling System (ECCS) and Emergency Feedwater System (EFWS) for a NPP were developed and the risk-informed design process was exercised to demonstrate the viability and feasibility of the RIA design methodology. Best estimate Loss-of-Coolant Accident (LOCA) analyses were performed to validate the PSA success criteria for the NPP. The results of the analyses show that the PSA success criteria can be met using the advanced conceptual systems and that the RIA design methodology is a viable and appropriate means of designing key features of risk-significant NPP systems. (authors)

State-of-the-art report on the current status of methodologies for seismic PSA

International Nuclear Information System (INIS)

1998-01-01

unlikely to exist at any other plant, even another similar plant. Sometimes the issue is site-related, and sometimes it is design-related. Also, even in areas where earthquakes are very uncommon phenomena, these types of accident sequences often appear as important contributors to the residual risk, typically because in such areas the attention given to designing nuclear stations against earthquakes is much less than in earthquake-prone areas. Given this background, it is obvious that no full-scope PSA can be considered complete without an examination of earthquakes. This report is a review of the methodology for conducting a seismic-PSA at a nuclear power station. The objective of this review is as follows: To provide an up-to-date review of the state-of-the-art of the various sub-methodologies that comprise the overall seismic- PSA methodology for addressing the safety of nuclear power stations, plus an overview of the whole methodological picture. In preparing this review, the author has had in mind several categories of readers and users: policy-level decision-makers (such as managers of nuclear power stations and regulators of nuclear safety), seismic- PSA practitioners, and PSA practitioners more broadly. The review will concentrate on evaluating the extent to which today's seismic-PSA methodology produces reliable and useful results and insights, at its current state-of-the-art level, for assessing nuclear-power station safety. Also, this review paper will deal exclusively with seismic-PSA for addressing nuclear-power-station safety. Because the author is based in the U.S., it is natural that this review will contain more emphasis on U.S. experience than on experience in other countries. However, significant experience elsewhere is a major part of the basis for this evaluation. In summary, this report is an up-to-date review of the state-of-the-art of the methodologies for conducting a seismic- PSA at a nuclear power station, including the six sub-methodologies that

Investigating surety methodologies for cognitive systems.

Energy Technology Data Exchange (ETDEWEB)

Caudell, Thomas P. (University of New Mexico, Albuquerque, NM); Peercy, David Eugene; Mills, Kristy (University of New Mexico, Albuquerque, NM); Caldera, Eva (University of New Mexico, Albuquerque, NM)

2006-11-01

Advances in cognitive science provide a foundation for new tools that promise to advance human capabilities with significant positive impacts. As with any new technology breakthrough, associated technical and non-technical risks are involved. Sandia has mitigated both technical and non-technical risks by applying advanced surety methodologies in such areas as nuclear weapons, nuclear reactor safety, nuclear materials transport, and energy systems. In order to apply surety to the development of cognitive systems, we must understand the concepts and principles that characterize the certainty of a system's operation as well as the risk areas of cognitive sciences. This SAND report documents a preliminary spectrum of risks involved with cognitive sciences, and identifies some surety methodologies that can be applied to potentially mitigate such risks. Some potential areas for further study are recommended. In particular, a recommendation is made to develop a cognitive systems epistemology framework for more detailed study of these risk areas and applications of surety methods and techniques.

Balancing work, study and home: a research with master’s students in a Brazilian University / Equilibrando trabalho, estudo e lar: um estudo com mestrandos em uma universidade brasileira

Directory of Open Access Journals (Sweden)

Amanda Magri Eller

2016-06-01

Full Text Available Purpose: Understand the tactics that nontraditional students use to manage the boundaries between work, home and study. Originality/gap/relevance/implications: The originality of this study relies on transfer of the focus from the conflict to the balance between work, home and study. It also breaks new ground by directing attention to the micro level of individual action, in contrast to a literature that traditionally studied organizational actions. Finally, it performs an innovative reading of the interface between work, home and study domains from the perspective of the boundary theory. Key methodological aspects: This qualitative study was held from 18 interviews that were recorded, transcribed and content analyzed, which revealed a list of individual tactics employed by respondents to reconcile the demands of work, home and study. Summary of key results: The analysis allowed us to identify 18 tactics that our respondents employ to negotiate the level of permeability between the boundaries between work, school and home. These tactics were classified as behavioral, communicative, physical and temporal. Key considerations/conclusions: The study revealed that students develop an active role by interpreting the expectations of the social actors from the home and work domains and from the institution where they study and adopt boundaries with degrees of permeability that enable a state of greater balance between these domains Objetivo: Compreender as táticas que estudantes não tradicionais utilizam para gerenciar as fronteiras entre trabalho, lar e estudo. Originalidade/Lacuna/Relevância/Implicações: O estudo se mostra original ao transferir o foco do conflito para o equilíbrio entre trabalho, lar e estudos. Além disso, também inova ao direcionar a atenção para o nível micro da ação individual, contrastando com uma literatura que tradicionalmente estuda ações organizacionais. Por fim, realiza uma leitura inovadora do fenômeno da

Exploiting Semantic Search Methodologies to Analyse Fast Nuclear Reactor Nuclear Related Information

International Nuclear Information System (INIS)

Costantini, L.

2016-01-01

Full text: This paper describes an experiment to evaluate the outcomes of using the semantic search engine together with the entity extraction approach and the visualisation tools in large set of nuclear data related to fast nuclear reactors (FNR) documents originated from INIS database and the IAEA web publication. The INIS database has been used because is the larger collection of nuclear related data and a sub-set of it can be utilised to verify the efficiency and the effectiveness of this approach. In a nutshell, the goal of the study was to: 1) find and monitor documents dealing with FNR; 2) building knowledge base (KB) according to the FNR nuclear components and populate the KB with relevant documents; 3) communicate the conclusion of the analysis by utilising visualisation tools. The semantic search engine used in the case study has the capability to perform what is called evidential reasoning: accruing, weighing and evaluating the evidence to determinate a mathematical score for each article that measures its relevance to the subject of interest. This approach provides a means to differentiate between articles that closely meet the search criteria versus those less relevant articles. Tovek software platform was chosen for this case study. (author

Nuclear accidents and epidemiology

International Nuclear Information System (INIS)

1987-01-01

A consultation on epidemiology related to the Chernobyl accident was held in Copenhagen in May 1987 as a basis for concerted action. This was followed by a joint IAEA/WHO workshop in Vienna, which reviewed appropriate methodologies for possible long-term effects of radiation following nuclear accidents. The reports of these two meetings are included in this volume, and cover the subjects: 1) Epidemiology related to the Chernobyl nuclear accident. 2) Appropriate methodologies for studying possible long-term effects of radiation on individuals exposed in a nuclear accident. Figs and tabs

A methodology for calculating the levelized cost of electricity in nuclear power systems with fuel recycling

International Nuclear Information System (INIS)

De Roo, Guillaume; Parsons, John E.

2011-01-01

In this paper we show how the traditional definition of the levelized cost of electricity (LCOE) can be extended to alternative nuclear fuel cycles in which elements of the fuel are recycled. In particular, we define the LCOE for a cycle with full actinide recycling in fast reactors in which elements of the fuel are reused an indefinite number of times. To our knowledge, ours is the first LCOE formula for this cycle. Others have approached the task of evaluating this cycle using an 'equilibrium cost' concept that is different from a levelized cost. We also show how the LCOE implies a unique price for the recycled elements. This price reflects the ultimate cost of waste disposal postponed through the recycling, as well as other costs in the cycle. We demonstrate the methodology by estimating the LCOE for three classic nuclear fuel cycles: (i) the traditional Once-Through Cycle, (ii) a Twice-Through Cycle, and (iii) a Fast Reactor Recycle. Given our chosen input parameters, we show that the 'equilibrium cost' is typically larger than the levelized cost, and we explain why.

Methodology for ranking restoration options

DEFF Research Database (Denmark)

Jensen, Per Hedemann

1999-01-01

techniques as a function of contamination and site characteristics. The project includes analyses of existing remediation methodologies and contaminated sites, and is structured in the following steps:-characterisation of relevant contaminated sites -identication and characterisation of relevant restoration...... techniques -assessment of the radiological impact -development and application of a selection methodology for restoration options -formulation ofgeneric conclusions and development of a manual The project is intended to apply to situations in which sites with nuclear installations have been contaminated...

Update of Part 61 Impacts Analysis Methodology. Methodology report. Volume 1

International Nuclear Information System (INIS)

Oztunali, O.I.; Roles, G.W.

1986-01-01

Under contract to the US Nuclear Regulatory Commission, the Envirosphere Company has expanded and updated the impacts analysis methodology used during the development of the 10 CFR Part 61 rule to allow improved consideration of the costs and impacts of treatment and disposal of low-level waste that is close to or exceeds Class C concentrations. The modifications described in this report principally include: (1) an update of the low-level radioactive waste source term, (2) consideration of additional alternative disposal technologies, (3) expansion of the methodology used to calculate disposal costs, (4) consideration of an additional exposure pathway involving direct human contact with disposed waste due to a hypothetical drilling scenario, and (5) use of updated health physics analysis procedures (ICRP-30). Volume 1 of this report describes the calculational algorithms of the updated analysis methodology

Update of Part 61 Impacts Analysis Methodology. Methodology report. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Oztunali, O.I.; Roles, G.W.

1986-01-01

Under contract to the US Nuclear Regulatory Commission, the Envirosphere Company has expanded and updated the impacts analysis methodology used during the development of the 10 CFR Part 61 rule to allow improved consideration of the costs and impacts of treatment and disposal of low-level waste that is close to or exceeds Class C concentrations. The modifications described in this report principally include: (1) an update of the low-level radioactive waste source term, (2) consideration of additional alternative disposal technologies, (3) expansion of the methodology used to calculate disposal costs, (4) consideration of an additional exposure pathway involving direct human contact with disposed waste due to a hypothetical drilling scenario, and (5) use of updated health physics analysis procedures (ICRP-30). Volume 1 of this report describes the calculational algorithms of the updated analysis methodology.

Proceedings of International monitoring conference 'Development of rehabilitation methodology of environment of the Semipalatinsk region polluted by nuclear tests'

International Nuclear Information System (INIS)

2002-01-01

The aim of the monitoring conference is draw an attention of government, national and international agencies, scientific societies, and local administrations to the ecological problems of Semipalatinsk nuclear test site, to combine the efforts of scientists to solve problems of soil disinfection, purification of surface and ground water from radioactive and heavy metals. It is expected that the knowledge, experience and methodology accumulated on the monitoring conference might be successfully transferred to solve analogous environmental problems of Kazakhstan

Digraph-fault tree methodology for the assessment of material control systems

International Nuclear Information System (INIS)

Lambert, H.E.; Lim, J.J.; Gilman, F.M.

1979-01-01

The Lawrence Livermore Laboratory, under contract to the United States Nuclear Regulatory Commission, is developing a procedure to assess the effectiveness of material control and accounting systems at nuclear fuel cycle facilities. The purpose of a material control and accounting system is to prevent the theft of special nuclear material such as plutonium or highly enriched uranium. This report presents the use of a directed graph and fault tree analysis methodology in the assessment procedure. This methodology is demonstrated by assessing a simulated material control system design, the Test Bed

Supplement to a Methodology for Succession Planning for Technical Experts

Energy Technology Data Exchange (ETDEWEB)

Kirk, Bernadette Lugue [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Cain, Ronald A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Agreda, Carla L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-11-01

This report complements A Methodology for Succession Planning for Technical Experts (Ron Cain, Shaheen Dewji, Carla Agreda, Bernadette Kirk, July 2017), which describes a draft methodology for identifying and evaluating the loss of key technical skills at nuclear operations facilities. This report targets the methodology for identifying critical skills, and the methodology is tested through interviews with selected subject matter experts.

FPGA Design Methodologies Applicable to Nuclear Power Plants

International Nuclear Information System (INIS)

Kwong, Yongil; Jeong, Choongheui

2013-01-01

In order to solve the above problem, NPPs in some countries such as the US, Canada and Japan have already applied FPGA-based equipment which has advantages as follows: It is easier to verify the performance because it needs only HDL code to configure logic circuits without other software, compared to microprocessor-based equipment, It is much cheaper than ASIC in a small quantity, Its logic circuits are re configurable, It has enough resources like logic blocks and memory blocks to implement I and C functions, Multiple functions can be implemented in a FPGA chip, It is stronger with respect to carboy security than microprocessor-based equipment because its configuration cannot be changed by external access, It is simple to replace it with new one when it is obsolete, Its power consumption is lower. However, FPGA-based equipment does not have only the merits. There are some issues on its application to NPPs. First of all, the experiences in applying it to NPPs are much less than to other industries, and international standards or guidelines are also very few. And there is the small number of FPGA platforms for I and C systems. Finally, the specific guidelines on FPGA design are required because the design has both hardware and software characteristics. In order to handle the above issues, KINS(Korea Institute of Nuclear Safety) built a test platform last year and have developed regulatory guidelines for FPGA-application in NPPs. I and C systems of NPPs have been increasingly using FPGA-based equipment as an alternative of microprocessor-based equipment which is not simple to be evaluated for safety due to its complexity. This paper explained the FPGA design flow and design guidelines. Those methodologies can be used as the guidelines on FPGA verification for safety of I and C systems

Interfacing system LOCA risk assessment: Methodology and application

International Nuclear Information System (INIS)

Galyean, W.J.; Schroeher, J.A.; Hanson, D.J.

1991-01-01

The United States Nuclear Regulatory Commission (NRC) is sponsoring a research program to develop an improved understanding of the human factors hardware, and accident consequence issues that dominate the risk from an Interfacing Systems Loss-of-Coolant Accident (ISLOCA) at a nuclear power plant. To accomplish this program, a methodology has been developed for estimating the core damage frequency and risk associated with an ISLOCA. The steps of the methodology are described with emphasis on one step which is unique, estimation of the probability of rupture of the low pressure systems. A trial application of the methodology was made for a Pressurized Water Reactor (PWR). The results are believed to be plant specific and indicate that human errors during startup and shutdown could be significant contributors to ISLOCA risk at the plant evaluated. 10 refs

A three-dimensional methodology for the assessment of neutron damage and nuclear energy deposition in graphite components of advanced gas-cooled reactors

Energy Technology Data Exchange (ETDEWEB)

Morgan, D.O.; Robinson, A.T.; Allen, D.A.; Picton, D.J.; Thornton, D.A. [TCS, Serco, Rutherford House, Olympus Park, Quedgeley, Gloucester, Gloucestershire GL2 4NF (United Kingdom); Shaw, S.E. [EDF Energy, Barnet Way, Barnwood, Gloucester GL4 3RS (United Kingdom)

2011-07-01

This paper describes the development of a three-dimensional methodology for the assessment of neutron damage and nuclear energy deposition (or nuclear heating) throughout the graphite cores of the UK's Advanced Gas-cooled Reactors. Advances in the development of the Monte Carlo radiation transport code MCBEND have enabled the efficient production of detailed fully three-dimensional models that utilise three-dimensional source distributions obtained from Core Follow data supplied by the reactor physics code PANTHER. The calculational approach can be simplified to reduce both the requisite number of intensive radiation transport calculations, as well as the quantity of data output. These simplifications have been qualified by comparison with explicit calculations and they have been shown not to introduce significant systematic uncertainties. Simple calculational approaches are described that allow users of the data to address the effects on neutron damage and nuclear energy deposition predictions of the feedback resulting from the mutual dependencies of graphite weight loss and nuclear energy deposition. (authors)

The study of evaluation methodology of the aging and degradation researches

International Nuclear Information System (INIS)

Cho, C. J.; Park, Z. H.; Jeong, I. S.

2001-01-01

To judge the usefulness of aging related researches like PLIM (Plant lifetime Management) and aging related degradation, et. al. in PSR(Periodic Safety Review), the evaluation methodology of the R and D have been proposed up to now are reviewed. The infometric methodology is considered to be the optimum method for the evaluation of the nuclear related researches. And finally, to increase the objectiveness and reliability of the infometric methodology in the aging and degradation researches, the indexes of safety, technology and economics are introduced. From this study, the infometric methodology has the advantage of the actual engineering evaluation in the nuclear related researches with other methodologies, but for the further research, the effective construction of DB and survey of various statistics in the technical reports and papers are needed

Towards the Development of a Methodology for the Cyber Security Analysis of Safety Related Nuclear Digital I and C Systems

International Nuclear Information System (INIS)

Khand, Parvaiz Ahmed; Seong, Poong Hyun

2007-01-01

In nuclear power plants the redundant safety related systems are designed to take automatic action to prevent and mitigate accident conditions if the operators and the non-safety systems fail to maintain the plant within normal operating conditions. In case of an event, the failure of these systems has catastrophic consequences. The tendency in the industry over the past 10 years has been to use of commercial of the shelf (COTS) technologies in these systems. COTS software was written with attention to function and performance rather than security. COTS hardware usually designed to fail safe, but security vulnerabilities could be exploited by an attacker to disable the fail safe mechanisms. Moreover, the use of open protocols and operating systems in these technologies make the plants to become vulnerable to a host of cyber attacks. An effective security analysis process is required during all life cycle phases of these systems in order to ensure the security from cyber attacks. We are developing a methodology for the cyber security analysis of safety related nuclear digital I and C Systems. This methodology will cover all phases of development, operation and maintenance processes of software life cycle. In this paper, we will present a security analysis process for the concept stage of software development life cycle

Metodologia de rating em cooperativas agropecuárias: um estudo de caso Rating methodology in agricultural cooperatives: a case study

Directory of Open Access Journals (Sweden)

Davi Rogério de Moura Costa

2009-12-01

Full Text Available A partir do início da década de 90, ocorreram diversas mudanças no ambiente institucional do cooperativismo brasileiro, em função dos problemas macroeconômicos que elevaram a alavancagem e a necessidade de as cooperativas obterem recursos financeiros junto a terceiros. Essa situação se intensificou nos últimos anos para manter a competitividade das organizações cooperativas no mercado. Em função da importância desse novo cenário, procurou-se estudar mecanismos de sinalização, com o objetivo de reduzir a assimetria de informações entre o mercado e os gestores das cooperativas. Assim, este trabalho desenvolve uma metodologia de rating para ser aplicada em cooperativas agropecuárias de forma a reduzir os problemas de seleção adversa e risco moral (moral hazard, que geram ineficiência no relacionamento entre essas organizações e o mercado financeiro; objetiva-se, também, averiguar a sua aplicabilidade, por meio de um estudo de caso. A partir dos resultados alcançados, é possível concluir que a metodologia é aplicável e que o sinalizador gerado, bem como as avaliações e os pesos, deveriam ser discutidos em comitês de rating, a exemplo do que é feito pelas agências especializadas. Como consideração final, é sugerida uma agenda de novas aplicações da metodologia para testá-la junto a outras organizações, de forma a consolidá-la como um sinalizador a ser usado pelo mercado e pelo sistema cooperativo.Owing to macroeconomic problems in Brazil in the late nineties, some modifications occurred in the agricultural cooperatives institutional environment that had influence on debt level and compromised the cooperative enterprises leverage on financial market resources. This situation has improved, in recent years, to maintain cooperatives' organizational competition level in markets. Owing to the significant implications of this important new business environment, this paper tries to discuss the tools to reduce the

Methodology for the integral comparison of nuclear reactors: selecting a reactor for Mexico

International Nuclear Information System (INIS)

Reyes R, R.; Martin del Campo M, C.

2006-01-01

In this work it was built a methodology to compare nuclear reactors of third generation that can be contemplated for future electric planning in Mexico. This methodology understands the selection of the reactors to evaluate eliminating the reactors that still are not sufficiently mature at this time of the study. A general description of each reactor together with their main ones characteristic is made. It was carried out a study for to select the group of parameters that can serve as evaluation indicators, which are the characteristics of the reactors with specific values for each considered technology, and it was elaborated an evaluation matrix indicators including the reactors in the columns and those indicators in the lines. Since that none reactor is the best in all the indicators were necessary to use a methodology for multi criteria taking decisions that we are presented. It was used the 'Fuzzy Logic' technique, the which is based in those denominated diffuse groups and in a system of diffuse inference based on heuristic rules in the way 'If Then consequence> ', where the linguistic values of the condition and of the consequence is defined by diffuse groups, it is as well as the rules always they transform a diffuse group into another. Later on they combine all the diffuse outputs to create a single output and an inverse transformation is made that it transfers the output from the diffuse domain to the real one. They were carried out two studies one with the entirety of the indicators and another in which the indicators were classified in three approaches: the first one refers to indicators related with the planning of the plants inside the context of the general electric sector, the second approach includes indicators related with the characteristics of the fuel and the third it considers indicators related with the acting of the plant in safety and environmental impact. This second study allowed us to know the qualities of each reactor in each one of the

Enhancing the seismic margin review methodology to obtain risk insights

International Nuclear Information System (INIS)

Budnitz, R.J.

1992-01-01

This paper discusses methods for obtaining risk insights from the seismic margin review (SMR) methodology. The SMR methodology was originally developed in 1984-1987 with the objective of analyzing an individual nuclear power plant to ascertain whether the plant has the ability to withstand earthquakes substantially beyond the design-basis earthquake without suffering a core-damage accident. Recently, in the context of Nuclear Regulatory Commission's (NRC's) Individual Plant Evaluation for External Events (IPEEE) program, the SMR methodology has been developed further by NRC to allow plants to identify plant-specific vulnerabilities (in the IPEEE sense) to seismic events. The objective of these enhancements has been to provide a methodology for IPEEE seismic review that is substantially less expensive than a full-scope seismic PRA, but that achieves the IPEEE's vulnerability-search objectives. In this paper, the steps involved in the enhanced methodology are discussed

The development and application of a prioritization methodology for the decommissioning of the Iraq Former Nuclear Complex

International Nuclear Information System (INIS)

Jarjies, A.; Abbas, M.; Fernandes, H.M.; Coates, R.

2008-01-01

There are a number of sites in Iraq which have been used for nuclear activities and which contain potentially significant amounts of radioactive waste. The principal nuclear site is Al-Tuwaitha, the former nuclear research centre which contains about 18 facilities including research reactors, hot cells and waste treatment and storage facilities. There are a further nine sites identified in the country which principally processed uranic material. Many of these sites suffered substantial physical damage during the Gulf Wars and have been subjected to subsequent looting. All require decommissioning in order to ensure both radiological and non-radiological safety. However, it is not possible to undertake the decommissioning of all sites and facilities at the same time. A prioritization methodology has therefore been developed in order to aid the decision-making process. The process comprises three principal stages of assessment: A quantitative surrogate risk assessment based primarily on radiological risk, but also taking account of other hazards; A range of sensitivity analyses to assess the robustness of the quantitative assessment, motivated by the present incomplete and uncertain data set on which the assessment is based; The inclusion of qualitative Other Modifying Factors, e g., social, political and pragmatic management inputs, which can have a significant influence on the prioritization ranking resulting from the above quantitative assessment. The output from this prioritization methodology has robustly identified and consistently ranked a group of Tuwaitha facilities with the highest risk, followed by a middle ranking grouping of Tuwaitha facilities and some other sites, and a relatively large group of lower risk facilities and sites. However, the initial order of priority for undertaking dismantling and decommissioning work has crucially been influenced by some of the Other Modifying Factors. In particular, given Iraq's isolation from the international

The development and application of a prioritization methodology for the decommissioning of the Iraq Former Nuclear Complex

Energy Technology Data Exchange (ETDEWEB)

Jarjies, A. [Ministry of Science and Technology (MoST), Baghdad (Iraq); Abbas, M. [Consultant to MoST, Baghdad (Iraq); Fernandes, H.M. [lnternational Atomic Energy Agency, Vienna (Austria); Coates, R. [Formerly with the International Atomic Energy Agency, Vienna (Austria)

2008-07-01

There are a number of sites in Iraq which have been used for nuclear activities and which contain potentially significant amounts of radioactive waste. The principal nuclear site is Al-Tuwaitha, the former nuclear research centre which contains about 18 facilities including research reactors, hot cells and waste treatment and storage facilities. There are a further nine sites identified in the country which principally processed uranic material. Many of these sites suffered substantial physical damage during the Gulf Wars and have been subjected to subsequent looting. All require decommissioning in order to ensure both radiological and non-radiological safety. However, it is not possible to undertake the decommissioning of all sites and facilities at the same time. A prioritization methodology has therefore been developed in order to aid the decision-making process. The process comprises three principal stages of assessment: A quantitative surrogate risk assessment based primarily on radiological risk, but also taking account of other hazards; A range of sensitivity analyses to assess the robustness of the quantitative assessment, motivated by the present incomplete and uncertain data set on which the assessment is based; The inclusion of qualitative Other Modifying Factors, e g., social, political and pragmatic management inputs, which can have a significant influence on the prioritization ranking resulting from the above quantitative assessment. The output from this prioritization methodology has robustly identified and consistently ranked a group of Tuwaitha facilities with the highest risk, followed by a middle ranking grouping of Tuwaitha facilities and some other sites, and a relatively large group of lower risk facilities and sites. However, the initial order of priority for undertaking dismantling and decommissioning work has crucially been influenced by some of the Other Modifying Factors. In particular, given Iraq's isolation from the international

IAEA methodology of the ITDB information analysis from nuclear security perspective

International Nuclear Information System (INIS)

2010-01-01

The IAEA methodology of the Illicit Trafficking database analyses general and specific risks, trends and patterns. This methodology assist in identification of security needs that are specific to material , activity , location ,country or even regional.Finally the methodology also analyses the lessons learned.

An application of the value tree analysis methodology within the integrated risk informed decision making for the nuclear facilities

International Nuclear Information System (INIS)

Borysiewicz, Mieczysław; Kowal, Karol; Potempski, Sławomir

2015-01-01

A new framework of integrated risk informed decision making (IRIDM) has been recently developed in order to improve the risk management of the nuclear facilities. IRIDM is a process in which qualitatively different inputs, corresponding to different types of risk, are jointly taken into account. However, the relative importance of the IRIDM inputs and their influence on the decision to be made is difficult to be determined quantitatively. An improvement of this situation can be achieved by application of the Value Tree Analysis (VTA) methods. The aim of this article is to present the VTA methodology in the context of its potential usage in the decision making on nuclear facilities. The benefits of the VTA application within the IRIDM process were identified while making the decision on fuel conversion of the research reactor MARIA. - Highlights: • New approach to risk informed decision making on nuclear facilities was postulated. • Value tree diagram was developed for decision processes on nuclear installations. • An experiment was performed to compare the new approach with the standard one. • Benefits of the new approach were reached in fuel conversion of a research reactor. • The new approach makes the decision making process more transparent and auditable

NUSAM Methodology for Assessment.

Energy Technology Data Exchange (ETDEWEB)

Leach, Janice [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Snell, Mark K. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-07-01

This document provides a methodology for the performance-based assessment of security systems designed for the protection of nuclear and radiological materials and the processes that produce and/or involve them. It is intended for use with both relatively simple installations and with highly regulated complex sites with demanding security requirements.

Methodology for modular nuclear plant design and construction

International Nuclear Information System (INIS)

Lapp, C.W.; Golay, M.

1992-01-01

During the past decade, the rising cost of nuclear power plant construction has caused the cancellation of many projects and has forced some utilities into bankruptcy. Many factors have contributed to capital cost increases, including regulatory changes, the absence of standard designs, and low worker productivity. Low worker productivity can be attributed to the conventional building process, which is not conductive to productive labor. This study presents innovative ways to reduce the capital cost of nuclear plants through more efficient construction processes designed to increase worker productivity. A major portion of the plant capital cost is the interest paid during construction on borrowed capital. Modular fabrication could potentially reduce interest payments by compressing the construction schedule of nuclear facilities. Additional cost savings expected from modular designs arise from improved quality, productivity, and schedule control in fabrication of plant elements within a factory environment

Methodology of aging management in structures, systems and components of a nuclear power plant and its application to a pilot program in Laguna Verde

International Nuclear Information System (INIS)

Jarvio C, G.; Fernandez S, G.

2009-10-01

From its origin the nuclear power plants confront the effects of time and of environment, giving as result the aging of its structures, systems and components. In this document the general process is described for the establishment of Aging Management Program developed by IAEA. Following the program methodology is guaranteed that a nuclear power plant manages the aging effects appropriately and to make decisions for its solution, assuring the characteristic functions of structures, systems and components of same nuclear power plant. On the other hand, the implantation of an aging management program constitutes the base for development of a licence renovation program, like it can be the specific case of the Central Laguna Verde Units 1 and 2. (Author)

Methodology for identifying credible disruptions to isolation of nuclear waste within Columbia River basalts

International Nuclear Information System (INIS)

Davis, J.D.

1982-01-01

Analysis of potential preclosure and postclosure disruptive events and processes is comprised of evaluation of (1) potential uncertainties and omissions associated with characterization of the site; (2) credible events and processes resulting from the dynamics of natural systems; (3) potential, credible changes in isolation conditions induced by the presence of the repository, and (4) potential, credible future changes impacting isolation capability resulting from man's activities, independent of repository construction/operation. This report presents the overall methodology for identification, classification and analysis of disruptive events based on Nuclear Regulatory Commission and Environmental Protection Agency guidelines proposed in drafts of 10 CFR 60 and 40 CFR 191. Potential credible disruptive events, processes, and conditions are considered with respect to whether they are anticipated or unanticipated, and determined to have reasonably foreseeable, very unlikely, or extremely unlikely probability of occurrence. 85 refs., 2 figs., 7 tabs

Study of virtual reality application in training programs on nuclear technology; Estudo da aplicacao de realidade virtual em programas de treinamento sobre tecnologia nuclear

Energy Technology Data Exchange (ETDEWEB)

Pastura, Valeria da Fonseca e Silva

2016-07-01

The activities developed in the units which organize the National Nuclear Energy Commission (CNEN) are present in various sectors of the Brazilian society, being them in medicine, industry, electricity generation, mining, and among the others. Based on the assumption that the employees are CNEN's mayor differential and the training programs play an important role in the process of organizational development, because they align the professionals with the strategies of the institution properly. Focusing on these matters, this master's thesis aimed to evaluate the training programs which are applied by CNEN, in order to propose and evaluate the use of the Virtual Reality (VR) expertise as a new method to be applied in the training programs. To accomplish this purpose, we performed two methodological approaches through questionnaires. And from the analysis of the results obtained, we could realize that there was no efficient training program which is systematically applied by CNEN, and the use of the RV technique improves the training programs in the understanding of themes whose assimilation is challengeable, such as those related to nuclear power. In this sense, for a better functional performance, the training programs adopted by CNEN must be structured so as to enable the development of each server's skills as well as abilities and, it is actually hoped that the virtual reality tools could be inserted in these programs to pursue only this purpose. (author)

Verification and software validation for nuclear instrumentation; Verificacion y validacion de software para instrumentacion nuclear

Energy Technology Data Exchange (ETDEWEB)

Gaytan G, E. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Salgado G, J. R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico); De Andrade O, E. [Universidad Federal de Rio de Janeiro, Caixa Postal 68509, 21945-970 Rio de Janeiro (Brazil); Ramirez G, A., E-mail: elvira.gaytan@inin.gob.mx [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Alto Lucero, Veracruz (Mexico)

2014-10-15

In this work is presented a Verification Methodology and Software Validation, to be applied in instruments of nuclear use with associate software. This methodology was developed under the auspices of IAEA, through the regional projects RLA4022 (ARCAL XCIX) and RLA1011 (RLA CXXIII), led by Mexico. In the first project three plans and three procedures were elaborated taking into consideration IEEE standards, and in the second project these documents were updated considering ISO and IEC standards. The developed methodology has been distributed to the participant countries of Latin America in the ARCAL projects and two related courses have been imparted with the participation of several countries, and participating institutions of Mexico like Instituto Nacional de Investigaciones Nucleares (ININ), Comision Federal de Electricidad (CFE) and Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). In the ININ due to the necessity to work with Software Quality Guarantee in systems for the nuclear power plant of the CFE, a Software Quality Guarantee Plan and five procedures were developed in the year 2004, obtaining the qualification of the ININ for software development for the nuclear power plant of CFE. These first documents were developed taking like reference IEEE standards and regulator guides of NRC, being the first step for the development of the methodology. (Author)

Measuring the social value of nuclear energy using contingent valuation methodology

International Nuclear Information System (INIS)

Jun, Eunju; Joon Kim, Won; Hoon Jeong, Yong; Heung Chang, Soon

2010-01-01

As one of the promising energy sources for the next few decades, nuclear energy receives more attention than before as environmental issues become more important and the supply of fossil fuels becomes unstable. One of the reasons for this attention is based on the rapid innovation of nuclear technology which solves many of its technological constraints and safety issues. However, regardless of these rapid innovations, social acceptance for nuclear energy has been relatively low and unchanged. Consequently, the social perception has often been an obstacle to the development and execution of nuclear policy requiring enormous subsidies which are not based on the social value of nuclear energy. Therefore, in this study, we estimate the social value of nuclear energy-consumers' willingness-to-pay for nuclear energy-using the Contingent Valuation Method (CVM) and suggest that the social value of nuclear energy increases approximately 68.5% with the provision of adequate information about nuclear energy to the public. Consequently, we suggest that the social acceptance management in nuclear policy development is important along with nuclear technology innovation.

Revised INPRO Methodology in the Area of Proliferation Resistance

International Nuclear Information System (INIS)

Park, J.H.; Lee, Y.D.; Yang, M.S.; Kim, J.K.; Haas, E.; Depisch, F.

2008-01-01

The official INPRO User Manual in the area of proliferation resistance is being processed for the evaluation of innovative nuclear energy systems. Proliferation resistance is one of the goals to be satisfied for future nuclear energy systems in INPRO. The features of currently updated and released INPRO methodology were introduced on basic principles, user requirements and indicators. The criteria for an acceptance limit were specified. The DUPIC fuel cycle was evaluated based on the updated INPRO methodology for the applicability of the INPRO User Manual. However, the INPRO methodology has some difficulty in quantifying the multiplicity and robustness as well as the total cost to improve proliferation resistance. Moreover, the integration method for the evaluation results still needs to be improved.

Proposed methodology for completion of scenario analysis for the Basalt Waste Isolation Project. [Assessment of post-closure performance for a proposed repository for high-level nuclear waste

Energy Technology Data Exchange (ETDEWEB)

Roberds, W.J.; Plum, R.J.; Visca, P.J.

1984-11-01

This report presents the methodology to complete an assessment of postclosure performance, considering all credible scenarios, including the nominal case, for a proposed repository for high-level nuclear waste at the Hanford Site, Washington State. The methodology consists of defensible techniques for identifying and screening scenarios, and for then assessing the risks associated with each. The results of the scenario analysis are used to comprehensively determine system performance and/or risk for evaluation of compliance with postclosure performance criteria (10 CFR 60 and 40 CFR 191). In addition to describing the proposed methodology, this report reviews available methodologies for scenario analysis, discusses pertinent performance assessment and uncertainty concepts, advises how to implement the methodology (including the organizational requirements and a description of tasks) and recommends how to use the methodology in guiding future site characterization, analysis, and engineered subsystem design work. 36 refs., 24 figs., 1 tab.

Experimental study of a methodology for Fission-track Dating without neutron irradiation

International Nuclear Information System (INIS)

Hadler, J.C.; Iunes, P.J.; Tello, C.A.; Chemale, F.; Kawashita, K.; Curvo, E.A.C.; Santos, F.G.S.; Gasparini, T.E.; Moreira, P.A.F.P.; Guedes, S.

2009-01-01

To carry out the dating by the Fission Track Method (FTM) the international community that works with this method employs methodologies in which the mineral to be dated must be irradiated with neutrons. Such irradiation, performed in a nuclear reactor, demand a relatively long waiting time so that the activity of the sample attain a proper level for handling. The present work aims to establish a methodology that makes possible the dating by FTM using a mass spectrometer instead of a nuclear reactor. This methodology was applied to apatite samples from Durango, Mexico.

MIRD methodology; Metodologia MIRD

Energy Technology Data Exchange (ETDEWEB)

Rojo, Ana M [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina); Gomez Parada, Ines [Sociedad Argentina de Radioproteccion, Buenos Aires (Argentina)

2004-07-01

The MIRD (Medical Internal Radiation Dose) system was established by the Society of Nuclear Medicine of USA in 1960 to assist the medical community in the estimation of the dose in organs and tissues due to the incorporation of radioactive materials. Since then, 'MIRD Dose Estimate Report' (from the 1 to 12) and 'Pamphlets', of great utility for the dose calculations, were published. The MIRD system was planned essentially for the calculation of doses received by the patients during nuclear medicine diagnostic procedures. The MIRD methodology for the absorbed doses calculations in different tissues is explained.

Development of design methodology for communication network in nuclear power plants

International Nuclear Information System (INIS)

Kim, Dong Hoon; Seong, Seung Hwan; Jang Gwi Sook; Koo, In Soo; Lee Soon Sung.

1996-06-01

This report describe the design methodology of communication network (CN) in nuclear power plants (NPPs). The construction procedure for the NPP CN consists of 4 phases, in study and review phase, design concepts and goals are established through technical review, collection of background information and feasibility study. In design phase, all of design activities such as extraction of requirements, communication modelling, overall and detail architecture design are performed. Implementation and test phase includes the manufacturing, installation and testing of hardware and software. In operation phase, CN construction is finalized through the evaluation and correction during operation. The requirements of CN consist of general requirements such as function, structure, reliability, standardization and detail requirements related with protocol, media, error, performance and etc. CN design also should follow the safety-related requirements such as isolation, redundancy, reliability and verify these requirements. For the selection of each technical element form commercial CN, the evaluation and selection elements are extracted from reliability, performance, operating factors and the required-level which classified into essential, primary, preference, recommendation should be assigned to each element. This report will be used as a technical reference for the CN implementation in NPP. (author). 3 tabs., 5 figs., 25 refs

Childhood leukaemia near British nuclear installations: Methodological issues and recent results

International Nuclear Information System (INIS)

Bithell, J. F.; Keegan, T. J.; Kroll, M. E.; Murphy, M. F. G.; Vincent, T. J.

2008-01-01

In 2008, the German Childhood Cancer Registry published the results of the Kinderkrebs in der Umgebung von Kernkraftwerken (KiKK) study of childhood cancer and leukaemia around German nuclear power stations. The positive findings appeared to conflict with the results of a recent British analysis carried out by the Committee on Medical Aspects of Radiation in the Environment (COMARE), published in 2005. The present paper first describes the COMARE study, which was based on data from the National Registry of Children's Tumours (NRCT); in particular, the methodology used in this study is described. Although the results of the COMARE study were negative for childhood leukaemia, this apparent discrepancy could be accounted for by a number of differences in approach, especially those relating to the distances from the power stations and the ages of the children studied. The present study was designed to match the KiKK study as far as possible. The incidence observed (18 cases within 5 km against 14.58 expected, p = 0.21) was not significantly raised. The risk estimate for proximity in the regression fitted was actually negative, though the confidence intervals involved are so wide that the difference from that reported in the KiKK study is only marginally statistically significant (p = 0.063). (authors)

Comparison between dispersed nuclear power plants and a nuclear energy center at a hypothetical site on Kentucky Lake, Tennessee. Vol. IV. A site selection methodology

International Nuclear Information System (INIS)

Rosemarin, C.S.; Yaffee, S.L.

1976-09-01

A methodology has been developed for selecting suitable sites for development as nuclear energy centers. First, the forty-eight contiguous states were screened on the basis of four variables: (1) seismic stability; (2) distance from projected population centers; (3) adequate water supply; and (4) noninterference with scenic and reserved lands. After location of a surrogate area in north central Tennessee, further screening was performed using 22 variables to find a suitable 75-sq-mile surrogate site within this 1500-sq-mile area. A computer method for screening the surrogate area is presented, and the use of the data for the 22 variables is illustrated

A methodology for semiautomatic taxonomy of concepts extraction from nuclear scientific documents using text mining techniques

International Nuclear Information System (INIS)

Braga, Fabiane dos Reis

2013-01-01

This thesis presents a text mining method for semi-automatic extraction of taxonomy of concepts, from a textual corpus composed of scientific papers related to nuclear area. The text classification is a natural human practice and a crucial task for work with large repositories. The document clustering technique provides a logical and understandable framework that facilitates the organization, browsing and searching. Most clustering algorithms using the bag of words model to represent the content of a document. This model generates a high dimensionality of the data, ignores the fact that different words can have the same meaning and does not consider the relationship between them, assuming that words are independent of each other. The methodology presents a combination of a model for document representation by concepts with a hierarchical document clustering method using frequency of co-occurrence concepts and a technique for clusters labeling more representatives, with the objective of producing a taxonomy of concepts which may reflect a structure of the knowledge domain. It is hoped that this work will contribute to the conceptual mapping of scientific production of nuclear area and thus support the management of research activities in this area. (author)

Training in radionuclide methodology and applications in biomedical area

International Nuclear Information System (INIS)

Signoretta, C.

1998-01-01

Full text: Training in the field of radionuclide methodology and applications in biomedical area is important to assure that radionuclide should duly be used without risk for patients or for technicians manipulating them. The National Atomic Energy Commission (CNEA) from its creation is giving training courses of different technical levels to those working in science and technology. The Course on Radionuclide Methodology and application is the most continuous, varied and requested within CNEA. This is a basic course mainly given to Biochemistry and Medicine. Its goal is to give both theoretical and practical knowledge for use and application of radionuclides bearing in mind radiological safety regulations. Personnel from CNEA and Nuclear Regulatory Authority (ARN) carry out teaching. On the other hand, a course for Technicians in Nuclear Medicine is giving supplying knowledge in this field, as well as expertise and practice to attend a responsible Medical Doctor. These curses comprise radionuclide methodology, anatomy, physiology, instrumentation and practical applications in Nuclear Medicine. Statistics concerning these course are giving. (author) [es

Estudo fitoquímico de Senna alata por duas metodologias Phytochemical study of Senna alata using two methodologies

Directory of Open Access Journals (Sweden)

I.M.C. Rodrigues

2009-01-01

Full Text Available Senna alata, mais conhecida como mata-pasto na região Norte do Brasil, é uma planta utilizada pela medicina popular em várias partes do mundo e considerada espécie problemática em pastagens do Estado do Pará. No presente estudo, compararam-se duas metodologias distintas para a determinação das principais classes de constituintes potenciais aleloquímicos das diferentes frações (caules, flores, folhas, raízes, sementes e vagens de S. alata. O material vegetal foi seco e sofreu extração exaustiva com solvente hidrometanólico, para obtenção dos extratos brutos; uma pequena parte dele foi solubilizada em metanol para obtenção das soluções utilizadas nos testes fitoquímicos. As metodologias utilizadas foram: testes por cromatografia em camada delgada (CCD para determinação do perfil cromatográfico qualitativo; e ensaios para detecção preliminar dos diferentes constituintes químicos, com base na extração destes com solventes apropriados e na aplicação de testes de coloração. Os resultados em ambos os métodos demonstraram pouca semelhança, sendo o CCD o mais simples, barato, rápido e adequado para análise preliminar de compostos químicos derivados de plantas, embora seja um método qualitativo. Este método foi mais sensível para a detecção de flavonoides, porém, para detecção de alcaloides, o reativo de Bouchardat foi mais sensível do que o de Dragendorff, assim como o hidróxido de amônia 10% foi mais sensível às antraquinonas do que o hidróxido de potássio. O estudo comprovou a alta diversidade de compostos químicos presentes em Senna alata, justificando sua ampla utilização na medicina popular e indicando ainda o potencial alelopático para a sua utilização.Senna alata, known as mata-pasto in northern Brazil, is a plant used in popular medicine in several parts of the world, and considered harmful to pastures in the state of Pará. In this study, two different methodologies are compared to

Nuclear forensics

International Nuclear Information System (INIS)

Karadeniz, O.; Guenalp, G.

2010-01-01

This review discusses the methodology of nuclear forensics and illicit trafficking of nuclear materials. Nuclear forensics is relatively new scientific branch whose aim it is to read out material inherent from nuclear material. Nuclear forensics investigations have to be considered as part of a comprehensive set of measures for detection,interception, categorization and characterization of illicitly trafficking nuclear material. Prevention, detection and response are the main elements in combating illicit trafficking. Forensics is a key element in the response process. Forensic science is defined as the application of a broad spectrum of sciences to answer questions of interest to the legal system. Besides, in this study we will explain age determination of nuclear materials.

European methodology for qualification of NDT as developed by ENIQ

International Nuclear Information System (INIS)

Champigny, F.; Sandberg, U.; Engl, G.; Crutzen, S.; Lemaitre, P.

1997-01-01

The European Network for Inspection Qualification (ENIQ) groups the major part of the nuclear power plant operators in the European Union (and Switzerland). The main objective of ENIQ is to co-ordinate and manage at European level expertise and resources for the qualification of NDE inspection systems, primarily for nuclear components. In the framework of ENIQ the European methodology for qualification of NDT has been developed. In this paper the main principles of the European methodology are given besides the main activities and organisation of ENIQ. (orig.)

Recent nuclear data work in China

International Nuclear Information System (INIS)

Zhigang, Ge

2014-01-01

A brief introduction about China nuclear activities will be introduced in this presentation, which includes the view of nuclear data measurement, evaluation activity system of China and the progress of the nuclear data measurements and evaluations during recent years. As the main output of China Nuclear Data Center, the scheme of the new Chinese Evaluated Nuclear Data Library (CENDL) will also be introduced in this article. The new version of CENDL is general purpose evaluated nuclear data file which consists of the neutron reaction sub-library, the activation sub-library, decay data sub-library and fission yield sub-library. CENDL-3.2 can be used for the nuclear engineering, nuclear medicine and nuclear science etc. fields. The CENDL-3.2 is based on the previous version of CENDL and other special purpose libraries established by CNDC, the updated experimental information and new nuclear data evaluation methodologies. The progress of the evaluation methodologies during recent years in China will be introduced in this presentation. (author)

Recent nuclear data work in China

International Nuclear Information System (INIS)

Ge Zhigang

2015-01-01

A brief of introduction about China nuclear activities will be introduced in this presentation, which including the view of nuclear data measurement, evaluation activity system of China and the progress of the nuclear data measurements and evaluations during recently years. As the main output of China Nuclear Data Center, The scheme of the new Chinese Evaluated Nuclear Data Library (CENDL) will be introduced also in this article. The new version of CENDL is general purpose evaluated nuclear data file which consists of the neutron reaction sub-library, the activation sub-library, decay data sub-library and fission yield sub-library. CENDL-3.2 can be used for the nuclear engineering, nuclear medicine and nuclear science etc. fields. The CENDL-3.2 is based on the previous version of CENDL and other special purpose libraries established by CNDC, the updated experimental information and new nuclear data evaluation methodologies. The progress of the evaluation methodologies during recently years in China will be introduced in this presentation. (author)

Regional Shelter Analysis Methodology

Energy Technology Data Exchange (ETDEWEB)

Dillon, Michael B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dennison, Deborah [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kane, Jave [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Walker, Hoyt [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Miller, Paul [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2015-08-01

The fallout from a nuclear explosion has the potential to injure or kill 100,000 or more people through exposure to external gamma (fallout) radiation. Existing buildings can reduce radiation exposure by placing material between fallout particles and exposed people. Lawrence Livermore National Laboratory was tasked with developing an operationally feasible methodology that could improve fallout casualty estimates. The methodology, called a Regional Shelter Analysis, combines the fallout protection that existing buildings provide civilian populations with the distribution of people in various locations. The Regional Shelter Analysis method allows the consideration of (a) multiple building types and locations within buildings, (b) country specific estimates, (c) population posture (e.g., unwarned vs. minimally warned), and (d) the time of day (e.g., night vs. day). The protection estimates can be combined with fallout predictions (or measurements) to (a) provide a more accurate assessment of exposure and injury and (b) evaluate the effectiveness of various casualty mitigation strategies. This report describes the Regional Shelter Analysis methodology, highlights key operational aspects (including demonstrating that the methodology is compatible with current tools), illustrates how to implement the methodology, and provides suggestions for future work.

Methodology for Identification of the Coolant Thermalhydraulic Regimes in the Core of Nuclear Reactors

International Nuclear Information System (INIS)

Sharaevsky, L.G.; Sharaevskaya, E.I.; Domashev, E.D.; Arkhypov, A.P.; Kolochko, V.N.

2002-01-01

The paper deals with one of the acute for the nuclear energy problem of accident regimes of NPPs recognition diagnostics using noise signal diagnostics methodology. The methodology intends transformation of the random noise signals of the main technological parameters at the exit of a nuclear facility (neutron flow, dynamic pressure etc.) which contain the important information about the technical status of the equipment. The effective algorithms for identification of random processes wore developed. After proper transformation its were considered as multidimensional random vectors. Automatic classification of these vectors in the developed algorithms is realized on the basis of the probability function in particular Bayes classifier and decision functions. Till now there no mathematical models for thermalhydraulic regimes of fuel assemblies recognition on the acoustic and neutron noises parameters in the core of nuclear facilities. The two mathematical models for analysis of the random processes submitted to the automatic classification is proposed, i.e. statistical (using Bayes classifier of acoustic spectral density diagnosis signals) and geometrical (on the basis of formation in the featured space of dividing hyper-plane). The theoretical basis of the bubble boiling regimes in the fuel assemblies is formulated as identification of these regimes on the basis of random parameters of auto spectral density of acoustic noise (ASD) measured in the fuel assemblies (dynamic pressure in the upper plenum in the paper). The elaborated algorithms allow recognize realistic status of the fuel assemblies. For verification of the proposed mathematical models the analysis of experimental measurements was carried out. The research of the boiling onset and definition of the local values of the flow parameters in the seven-beam fuel assembly (length of 1.3 m, diameter of 6 mm) have shown the correct identification of the bubble boiling regimes. The experimental measurements on

Educating nuclear engineers by nuclear science and technology master at UPM

Energy Technology Data Exchange (ETDEWEB)

Ahnert, C.; Minguez, E.; Perlado, M. [Universidad Politecnica de Madrid (Spain). Dept. de Ingenieria Nuclear; and others

2014-05-15

One of the main objectives of the Master on Nuclear Science and Technology implemented in the Universidad Politecnica de Madrid, is the training for the development of methodologies of simulation and advanced analysis necessary in research and in professional work in the nuclear field, for Fission Reactors and Nuclear Fusion, including fuel cycle and safety aspects. The students are able to use the current computational methodologies/codes for nuclear engineering that covers a difficult gap between nuclear reactor theory and simulations. Also they are able to use some facilities, as the Interactive Graphical Simulator of PWR power plant that is an optimal tool to transfer the knowledge of the physical phenomena that are involved in the nuclear power plants, from the nuclear reactor to the whole set of systems and equipment on a nuclear power plant. The new Internet reactor laboratory to be implemented will help to understand the Reactor Physics concepts. The experimental set-ups for neutron research and for coating fabrication offer new opportunities for training and research activities. All of them are relevant tools for motivation of the students, and to complete the theoretical lessons. They also follow the tendency recommended for the European Space for higher Education (Bologna) adapted studies. (orig.)

Educating nuclear engineers by nuclear science and technology master at UPM

International Nuclear Information System (INIS)

Ahnert, C.; Minguez, E.; Perlado, M.

2014-01-01

One of the main objectives of the Master on Nuclear Science and Technology implemented in the Universidad Politecnica de Madrid, is the training for the development of methodologies of simulation and advanced analysis necessary in research and in professional work in the nuclear field, for Fission Reactors and Nuclear Fusion, including fuel cycle and safety aspects. The students are able to use the current computational methodologies/codes for nuclear engineering that covers a difficult gap between nuclear reactor theory and simulations. Also they are able to use some facilities, as the Interactive Graphical Simulator of PWR power plant that is an optimal tool to transfer the knowledge of the physical phenomena that are involved in the nuclear power plants, from the nuclear reactor to the whole set of systems and equipment on a nuclear power plant. The new Internet reactor laboratory to be implemented will help to understand the Reactor Physics concepts. The experimental set-ups for neutron research and for coating fabrication offer new opportunities for training and research activities. All of them are relevant tools for motivation of the students, and to complete the theoretical lessons. They also follow the tendency recommended for the European Space for higher Education (Bologna) adapted studies. (orig.)

Estudos de atmosfera

Directory of Open Access Journals (Sweden)

Carlos Eduardo Riccioppo

2016-11-01

Full Text Available Joker e Estudos de balística possuíam formas distintas dos cadernos ou livros quando foram exibidos pela primeira vez, na mostra Dual Overdrive. De algum modo, o flagrante das imagens dos cartazes da campanha política parisiense e daquelas cusparadas sobre o asfalto era preservado no modo como eram mostrados os trabalhos, que repunham não apenas a orientação espacial dos objetos fotografados, mas, igualmente, sua escala: Joker apresentava-se na parede, em dimensões relativamente próximas às dos cartazes lambe-lambe que retratavam; e Estudos de balística, no chão da galeria, também com ampliação suficiente para que se tivesse a impressão de que se tratava de imagens “em tamanho real”.

Behavior, society, and nuclear war

International Nuclear Information System (INIS)

Tetlock, P.E.; Husbands, J.L.; Jervis, R.; Stern, P.C.; Tilly, C.

1989-01-01

This book contains chapters on the following topics related to nuclear arms and nuclear war: crisis decision making; behavioral aspects of negotiations on mutual security; democracy, public opinion, and nuclear weapons; the case of wars; A review of theories; methodological themes and variations

Methodology for categorization of nuclear material in pyroprocessing facility

Energy Technology Data Exchange (ETDEWEB)

Lee, Chanki; Choi, Sungyeol [UNIST, Ulsan (Korea, Republic of); Kim, Woo Jin; Kim, Min Su; Jeong, Yon Hong [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2016-10-15

For the pyroprocessing facility to be commercialized in future, current regulations should be evaluated and developed in advance, based on the new types of nuclear materials in the facility. Physical protection system, especially, requires reasonable and reliable categorization of nuclear materials, to prevent from the theft of nuclear materials. In this paper, therefore, current categorization methods of nuclear material are investigated and applied to the pyroprocessing facility. After inconsistencies and gaps are found among methods, they are compared and discussed based on eight considering points (i.e, degrees of attractiveness, levels of category, discount factor, physical barriers, chemical barriers, isotopic barriers, radiological barriers, and capabilities of adversaries), to roughly suggest a new method for categorization. Current categorization methods of nuclear material, including IAEA's INFCIRC/225, U.S. DOE's method, newly expected U.S. NRC's method, FOM, and Bunn's approach, are different and can bring inconsistencies of physical protection requirements. The gap among methods will be significant if advanced fuel cycles are applied to them for the future. For example, the categorization results of 5 target materials in pyroprocessing facility show clear inconsistencies, while TRU ingot is considered the most attractive material. To resolve inconsistencies, it is necessary to determine new method suitable to pyroproessing facility, by considering the effects of eight points (i.e, degrees of attractiveness, levels of category, discount factor, physical barriers, chemical barriers, isotopic barriers, radiological barriers, and capabilities of adversaries)

Methodology for categorization of nuclear material in pyroprocessing facility

International Nuclear Information System (INIS)

Lee, Chanki; Choi, Sungyeol; Kim, Woo Jin; Kim, Min Su; Jeong, Yon Hong

2016-01-01

For the pyroprocessing facility to be commercialized in future, current regulations should be evaluated and developed in advance, based on the new types of nuclear materials in the facility. Physical protection system, especially, requires reasonable and reliable categorization of nuclear materials, to prevent from the theft of nuclear materials. In this paper, therefore, current categorization methods of nuclear material are investigated and applied to the pyroprocessing facility. After inconsistencies and gaps are found among methods, they are compared and discussed based on eight considering points (i.e, degrees of attractiveness, levels of category, discount factor, physical barriers, chemical barriers, isotopic barriers, radiological barriers, and capabilities of adversaries), to roughly suggest a new method for categorization. Current categorization methods of nuclear material, including IAEA's INFCIRC/225, U.S. DOE's method, newly expected U.S. NRC's method, FOM, and Bunn's approach, are different and can bring inconsistencies of physical protection requirements. The gap among methods will be significant if advanced fuel cycles are applied to them for the future. For example, the categorization results of 5 target materials in pyroprocessing facility show clear inconsistencies, while TRU ingot is considered the most attractive material. To resolve inconsistencies, it is necessary to determine new method suitable to pyroproessing facility, by considering the effects of eight points (i.e, degrees of attractiveness, levels of category, discount factor, physical barriers, chemical barriers, isotopic barriers, radiological barriers, and capabilities of adversaries)

Measuring the Social Value of Nuclear Energy using Contingent Valuation Methodology

International Nuclear Information System (INIS)

Jun, Eun Ju; Kim, Won Joon; Chang, Soon Heung

2009-01-01

In recent years, in addition to unstable energy supply and volatile energy prices, environmental concerns make energy security as the principal objective of energy policy in many nations. The International Energy Agency (2007) released what is probably its most pessimistic World Energy Outlook to date saying that oil and natural gas imports, coal use and greenhouse gas emissions are set to grow inexorably through 2030 - trends that threaten to undermine energy security and accelerate climate change, if countries do not change their energy use policies. In near term, nuclear is expected to be accepted as one of the promising alternatives which can achieve both energy security and prevention of climate change. However, nuclear energy has some vulnerable points in the view of social acceptance due to the history of its development and previous. Many countries which use nuclear power as one the major energy sources have been solving the problem of low social acceptance of nuclear energy by allocating enormous subsidy to local government. Korea decided to give 300 million dollar to the local government, Gyeongjoo, for constructing low level waste management facilities. Japan also paid 120 million dollar to Rokkasho-mura area for constructing nuclear waste repository. Sellarfield in England, Cabril in Spain also received subsidy every year from the related industries and their government. However these subsidies were provided without any appropriate estimation for the value of risk taking of nuclear energy. In addition, those subsidies are expected to increase and burden the central government for the further development and usage of nuclear. This study, therefore, aims to evaluate the value of nuclear energy in view of social acceptance in order to contribute to effective application for the future nuclear development and policy making. We estimate the Willingness-To-Pay of nuclear energy using Contingent Valuation Method (CVM). We find high social cost of nuclear

Estudos de caso como estratégia de ensino na formação de professores de física Case studies as a methodological strategy in Physics teachers' preparation

Directory of Open Access Journals (Sweden)

Marília Paixão Linhares

2008-01-01

Full Text Available O estudo é parte de um projeto de pesquisa que investiga estratégias para a formação de professores de ciência apoiada em um ambiente virtual de aprendizagem. O artigo descreve a estrutura de uma proposta curricular adotada num curso de licenciatura em Física, baseada na idéia de aprendizagem como construção de conhecimentos e na necessidade de transformar o pensamento espontâneo do professor sobre docência. Analisa parte dos resultados obtidos da aplicação desta proposta em que Estudos de Caso foram adotados como estratégia para a promoção do desenvolvimento profissional docente, orientado por atividades de investigação desenvolvidas em torno de problemas curriculares. A análise das concepções dos futuros professores indica que, a partir da reflexão sobre problemas da prática docente, os licenciandos se apropriam dos conhecimentos teóricos disponíveis e modificam suas concepções iniciais sobre conteúdos didáticos, metodologia e ambiente de trabalho.The work is part of a research project that investigates strategies for the formation of science teachers supported by a virtual learning environment. This paper describes a curricular proposal adopted in a physics teacher preparation course, based on knowledge as a construction and on the teacher's spontaneous thought transformation. Cases had been adopted as strategy for the promotion of the teaching of professional development, guided by investigation activities about curricular problems. Future teacher conceptions analyzed indicate that the available theoretical knowledge was appropriate for the students and its initial conceptions about didactic contents, methodology and work environment were modified.

ESTUDOS ESTILÍSTICOS NO BRASIL

Directory of Open Access Journals (Sweden)

Carlos Eduardo Falcão Uchôa

2013-06-01

Full Text Available Este artigo objetiva mostrar os inícios e a progressão dos estudos estilísticos no Brasil. Após uma introdução sobre o surgimento, na Europa, da Estilística como disciplina de pesquisa no campo da linguagem, detém-se, sucessivamente, nas contribuições de filólogos, linguistas, teóricos da literatura e gramáticos para o estudo dos mais variados recursos estilísticos ocorrentes sobretudo em autores brasileiros.

Development of an accident sequence precursor methodology and its application to significant accident precursors

Energy Technology Data Exchange (ETDEWEB)

Jang, Seung Hyun; Park, Sung Hyun; Jae, Moo Sung [Dept. of of Nuclear Engineering, Hanyang University, Seoul (Korea, Republic of)

2017-03-15

The systematic management of plant risk is crucial for enhancing the safety of nuclear power plants and for designing new nuclear power plants. Accident sequence precursor (ASP) analysis may be able to provide risk significance of operational experience by using probabilistic risk assessment to evaluate an operational event quantitatively in terms of its impact on core damage. In this study, an ASP methodology for two operation mode, full power and low power/shutdown operation, has been developed and applied to significant accident precursors that may occur during the operation of nuclear power plants. Two operational events, loss of feedwater and steam generator tube rupture, are identified as ASPs. Therefore, the ASP methodology developed in this study may contribute to identifying plant risk significance as well as to enhancing the safety of nuclear power plants by applying this methodology systematically.

A methodology for optimisation of countermeasures for animal products after a nuclear accident and its application

International Nuclear Information System (INIS)

Hwang, Won Tae; Cho, Gyuseong; Han, Moon Hee

1999-01-01

A methodology for the optimisation of the countermeasures associated with the contamination of animal products was designed based on cost-benefit analysis. Results are discussed for the hypothetical deposition of radionuclides on 15 August, when pastures are fully developed in Korean agricultural conditions. A dynamic food chain model, DYNACON, was used to evaluate the effectiveness of the countermeasures for reducing the ingestion dose. The countermeasures considered were: (1) a ban on food consumption; and (2) the substitution of clean fodder. These are effective in reducing the ingestion dose as well as simple and easy to carry out in the first year after deposition. The net benefit of the countermeasures was quantitatively estimated in terms of avertable doses and monetary costs. The benefit depends on a variety of factors, such as radionuclide concentrations on the ground, starting time and duration of the countermeasures. It is obvious that a fast reaction after deposition is important in maximising the cost effectiveness of the countermeasures. In most cases, the substitution of clean fodder is more cost effective than a ban on food consumption. The methodology used in this study may serve as a basis for rapid decision-making on the introduction of countermeasures relating to the contamination of animal products after a nuclear accident

Development of a Long Term Cooling Analysis Methodology Using Rappel

International Nuclear Information System (INIS)

Lee, S. I.; Jeong, J. H.; Ban, C. H.; Oh, S. J.

2012-01-01

Since the revision of the 10CFR50.46 in 1988, which allowed BE (Best-Estimate) method in analyzing the safety performance of a nuclear power plant, safety analysis methodologies have been changed continuously from conservative EM (Evaluation Model) approaches to BE ones. In this context, LSC (Long-Term core Cooling) methodologies have been reviewed by the regulatory bodies of USA and Korea. Some non-conservatism and improperness of the old methodology have been identified, and as a result, USNRC suspended the approval of CENPD-254-P-A which is the old LSC methodology for CE-designed NPPs. Regulatory bodies requested to remove the non-conservatisms and to reflect system transient behaviors in all the LSC methodologies used. In the present study, a new LSC methodology using RELAP5 is developed. RELAP5 and a newly developed code, BACON (Boric Acid Concentration Of Nuclear power plant) are used to calculate the transient behavior of the system and the boric acid concentration, respectively. Full range of break spectrum is considered and the applicability is confirmed through plant demonstration calculations. The result shows a good comparison with the old-fashioned ones, therefore, the methodology could be applied with no significant changes of current LSC plans

O desamparo aprendido revisitado: estudos com animais

Directory of Open Access Journals (Sweden)

Maria Helena Leite Hunziker

Full Text Available O desamparo aprendido tem sido definido como a dificuldade de aprendizagem apresentada por indivíduos que tiveram experiência prévia com estímulos aversivos incontroláveis. O objetivo deste trabalho é fazer uma revisão crítica dos estudos sobre o desamparo aprendido, com animais. Nessa análise, são considerados aspectos conceituais e metodológicos dos estudos em questão e as interpretações teóricas sobre esse efeito comportamental. Aborda-se a evolução histórica desses estudos, bem como alguns aspectos controversos das publicações que se acumularam ao longo de quatro décadas de pesquisa. A associação do desamparo aprendido com a depressão clínica é analisada criticamente, destacando-se a necessidade de maior rigor metodológico e conceitual nos estudos da área.

Nuclear methodology development for clinical analysis

International Nuclear Information System (INIS)

Oliveira, Laura Cristina de

2003-01-01

In the present work the viability of using the neutron activation analysis to perform urine and blood clinical analysis was checked. The aim of this study is to investigate the biological behavior of animals that has been fed with chow doped by natural uranium for a long period. Aiming at time and cost reduction, the absolute method was applied to determine element concentration on biological samples. The quantitative results of urine sediment using NAA were compared with the conventional clinical analysis and the results were compatible. This methodology was also used on bone and body organs such as liver and muscles to help the interpretation of possible anomalies. (author)

The status of proliferation resistance evaluation methodology development in GEN IV international forum

International Nuclear Information System (INIS)

Inoue, Naoko; Kawakubo, Yoko; Seya, Michio; Suzuki, Mitsutoshi; Kuno, Yusuke; Senzaki, Masao

2010-01-01

The Generation IV Nuclear Energy Systems International Forum (GIF) Proliferation Resistance and Physical Protection Working Group (PR and PP WG) was established in December 2002 in order to develop the PR and PP evaluation methodology for GEN IV nuclear energy systems. The methodology has been studied and established by international consensus. The PR and PP WG activities include development of the measures and metrics; establishment of the framework of PR and PP evaluation, the demonstration study using Example Sodium Fast Reactor (ESFR), which included the development of three evaluation approaches; the Case Study using ESFR and four kinds of threat scenarios; the joint study with GIF System Steering Committees (SSCs) of the six reactor design concepts; and the harmonization study with the IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). This paper reviews the status of GIF PR and PP studies and identifies the challenges and directions for applying the methodology to evaluate future nuclear energy systems in Japan. (author)

Actualization of the Brazilian nuclear regulations; Atualizacao das normas nucleares brasileiras

Energy Technology Data Exchange (ETDEWEB)

Wieland, Patricia; Soares, Abner Duarte; Nogueira, Tindyua de Moraes; Monteiro, Iara Arraes; Pitta, Maria Adelia Rocha; Bruno, Natanael Carvalho; Pereira, Enneite Souza; Pinto, Marvio dos S.; Lidington, Regina Marcia Rocha; Rocha, Marco Aurelio Toledo, E-mail: pwieland@cnen.gov.b, E-mail: asoares@cnen.gov.b, E-mail: tnogueira@cnen.gov.b, E-mail: iara@cnen.gov.b, E-mail: mpitta@cnen.gov.b, E-mail: nbruno@cnen.gov.b, E-mail: espereira@cnen.gov.b, E-mail: marvio@cnen.gov.b, E-mail: , E-mail: rmliding@cnen.gov.b, E-mail: mtoledo@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Div. de Normas

2011-10-26

The present work has the objective of making public the methodological approach adopted by the Brazilian Nuclear Energy Commission (CNEN) to create a nuclear normative structure up-dated and coherent. According to the Law 4118/62, 6189/74 and 7781/89, is the attribution the CNEN to establish specific guidelines for nuclear safety and radiological protection, and also do dictate safety norms through the emission of Resolutions

Review of Software Reliability Assessment Methodologies for Digital I and C Software of Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Cho, Jae Hyun; Lee, Seung Jun; Jung, Won Dea [KAERI, Daejeon (Korea, Republic of)

2014-08-15

Digital instrumentation and control (I and C) systems are increasingly being applied to current nuclear power plants (NPPs) due to its advantages; zero drift, advanced data calculation capacity, and design flexibility. Accordingly, safety issues of software that is main part of the digital I and C system have been raised. As with hardware components, the software failure in NPPs could lead to a large disaster, therefore failure rate test and reliability assessment of software should be properly performed, and after that adopted in NPPs. However, the reliability assessment of the software is quite different with that of hardware, owing to the nature difference between software and hardware. The one of the most different thing is that the software failures arising from design faults as 'error crystal', whereas the hardware failures are caused by deficiencies in design, production, and maintenance. For this reason, software reliability assessment has been focused on the optimal release time considering the economy. However, the safety goal and public acceptance of the NPPs is so distinctive with other industries that the software in NPPs is dependent on reliability quantitative value rather than economy. The safety goal of NPPs compared to other industries is exceptionally high, so conventional methodologies on software reliability assessment already used in other industries could not adjust to safety goal of NPPs. Thus, the new reliability assessment methodology of the software of digital I and C on NPPs need to be developed. In this paper, existing software reliability assessment methodologies are reviewed to obtain the pros and cons of them, and then to assess the usefulness of each method to software of NPPs.

Review of Software Reliability Assessment Methodologies for Digital I and C Software of Nuclear Power Plants

International Nuclear Information System (INIS)

Cho, Jae Hyun; Lee, Seung Jun; Jung, Won Dea

2014-01-01

Digital instrumentation and control (I and C) systems are increasingly being applied to current nuclear power plants (NPPs) due to its advantages; zero drift, advanced data calculation capacity, and design flexibility. Accordingly, safety issues of software that is main part of the digital I and C system have been raised. As with hardware components, the software failure in NPPs could lead to a large disaster, therefore failure rate test and reliability assessment of software should be properly performed, and after that adopted in NPPs. However, the reliability assessment of the software is quite different with that of hardware, owing to the nature difference between software and hardware. The one of the most different thing is that the software failures arising from design faults as 'error crystal', whereas the hardware failures are caused by deficiencies in design, production, and maintenance. For this reason, software reliability assessment has been focused on the optimal release time considering the economy. However, the safety goal and public acceptance of the NPPs is so distinctive with other industries that the software in NPPs is dependent on reliability quantitative value rather than economy. The safety goal of NPPs compared to other industries is exceptionally high, so conventional methodologies on software reliability assessment already used in other industries could not adjust to safety goal of NPPs. Thus, the new reliability assessment methodology of the software of digital I and C on NPPs need to be developed. In this paper, existing software reliability assessment methodologies are reviewed to obtain the pros and cons of them, and then to assess the usefulness of each method to software of NPPs

BIBGTR: nuclear data libraries for the programs Unimug and Anisn

International Nuclear Information System (INIS)

Ono, S.; Caldeira, A.D.

1989-11-01

Nuclear data libraries generable by the NJOY for the programs UNIMUG and ANISN, using evaluated data from ENDF/B-IV and ENDF/B-V are described. These libraries will be used by Radioisotope Thermoelectric Generators Project of Instituto de Estudos Avancados. (author) [pt

An LWR design decision Methodology

International Nuclear Information System (INIS)

Leahy, T.J.; Rees, D.C.; Young, J.

1982-01-01

While all parties involved in nuclear plant regulation endeavor to make decisions which optimize the considerations of plant safety and financial impacts, these decisions are generally made without the benefit of a systematic and rigorous approach to the questions confronting the decision makers. A Design Decision Methodology has been developed which provides such a systematic approach. By employing this methodology, which makes use of currently accepted probabilistic risk assessment techniques and cost estimation, informed decisions may be made against a background of comparisons between the relative levels of safety and costs associated with various design alternatives

Study of methodology for low power/shutdown fire PSA

International Nuclear Information System (INIS)

Yan Zhen; Li Zhaohua; Li Lin; Song Lei

2014-01-01

As a risk assessment technology based on probability, the fire PSA is accepted abroad by nuclear industry in its application in the risk assessment for nuclear power plants. Based on the industry experience, the fire-induced impact on the plant safety during low power and shutdown operation cannot be neglected, therefore fire PSA can be used to assess the corresponding fire risk. However, there is no corresponding domestic guidance/standard as well as accepted analysis methodology up to date. Through investigating the latest evolvement on fire PSA during low power and shutdown operation, and integrating its characteristic with the corresponding engineering experience, an engineering methodology to evaluate the fire risk during low power and shutdown operation for nuclear power plant is established in this paper. In addition, an analysis demonstration as an example is given. (authors)

Development and Attestation of Gamma-Ray Measurement Methodologies for use by Rostekhnadzor Inspectors in the Russian Federation

International Nuclear Information System (INIS)

Jeff Sanders

2006-01-01

Development and attestation of gamma-ray non-destructive assay measurement methodologies for use by inspectors of the Russian Federal Service for Environmental, Technological, and Nuclear Oversight (Rostekhnadzor, formerly Gosatomnadzor or GAN), as well as for use by Russian nuclear facilities, has been completed. Specifically, a methodology utilizing the gamma-ray multi group analysis (MGA) method for determining plutonium isotopic composition has been developed, while existing methodologies to determining uranium enrichment and isotopic composition have been revised to make them more appropriate to the material types and conditions present in nuclear facilities in the Russian Federation. This paper will discuss the development and revision of these methodologies, the metrological characteristics of the final methodologies, as well as the limitations and concerns specific to the utilization of these analysis methods in the Russian Federation

Evaluation method of nuclear nonproliferation credibility

International Nuclear Information System (INIS)

Kwon, Eun-ha; Ko, Won Il

2009-01-01

This paper presents an integrated multicriteria analysis method for the quantitative evaluation of a state's nuclear nonproliferation credibility level. Underscoring the implications of policy on the sources of political demand for nuclear weapons rather than focusing on efforts to restrict the supply of specific weapons technology from the 'haves' to the 'have-nots', the proposed methodology considers the political, social, and cultural dimensions of nuclear proliferation. This methodology comprises three steps: (1) identifying the factors that influence credibility formation and employing them to construct a criteria tree that will illustrate the relationships among these factors; (2) defining the weight coefficients of each criterion through pairwise comparisons of the Analytical Hierarchy Process (AHP); and (3) assigning numerical scores to a state under each criterion and combining them with the weight coefficients in order to provide an overall assessment of the state. The functionality of this methodology is examined by assessing the current level of nuclear nonproliferation credibility of four countries: Japan, North Korea, South Korea, and Switzerland.

Nuclear methods in environmental and energy research

Energy Technology Data Exchange (ETDEWEB)

Vogt, J. R. [ed.

1977-01-01

The topics considered in the seven sessions were nuclear methods in atmospheric research; nuclear and atomic methodology; nuclear methods in tracer applications; energy exploration, production, and utilization; nuclear methods in environmental monitoring; nuclear methods in water research; and nuclear methods in biological research. Individual abstracts were prepared for each paper. (JSR)

Qualified software development methodologies for nuclear class 1E equipment

International Nuclear Information System (INIS)

Koch, Shlomo; Ruether, J.

1992-01-01

This article describes the experience learned at Northern States Power and Spectrum Technologies, during the development of a computer based Safeguard Load Sequencer, for Prairie Island Nuclear Generating Plant. The Safeguard Load Sequencer (SLS) performs the function of 4kV emergency bus voltage restoration, load shedding, and emergency diesel generator loading. The system is designed around an Allen-Bradley PLC-5 programmable controller. The Safeguard Load Sequencer is the vehicle to demonstrate the software engineering procedures and methodologies. The article analyzes the requirements imposed by the NUREG 4640 handbook, and the relevant IEEE standards. The article tries to answer the question what is software engineering, and describe the waterfall life cycle phases of software development. The effects of each phase on software quality and V and V plan is described. Issues designing a V and V plan is addressed, and considerations of cost and time to implement the program are described. The article also addresses the subject of tools that can increase productivity and reduce the cost and time of an extensive V and V plan. It describes the tools the authors used, and more importantly presents a wish list of tools that they as developers would like to have. The role of testing is presented. They show that testing at the final stage has a lower impact on software quality then generally assumed. Full coverage of testing is almost always impossible, and they demonstrate how alternative audits and test during the development phase can improve software reliability

Methodology of radionuclides dis incorporation in people related to nuclear and radiological accidents

International Nuclear Information System (INIS)

Jimenez F, E. A.

2014-01-01

In this paper a classification of the radiological and nuclear accidents is presented, describing which the activities are, where they have occurred, their incidence and the learned lessons in these successes. The radiological accidents in which radioactive materials intervene can occur anywhere, and they are related to no controlled dangerous sources (abandoned, lost, stolen, or found sources), improper use of dangerous industrial and medical sources, exposition and contamination of people in general by an unknown origin, serious over expositions, menaces and willful misconduct, emergencies during transportation of radioactive material. A person can receive a dose of radiation from an external source, because of radioactive material placed on skin or on equipment, or because of ingestion or inhalation of radiological particles. The ingestion or the inhalation of radioactive material can cause an internal dose to the whole body or to a specific organ during a period of time. That is why a description of the processes of incorporation, the stages of incorporation and a description of the biokinetic models are also realized to understand the ingestion, transference and the excretion of the radioactive elements. In order to offer help to a victim of internal contamination, the dosimetric and medical diagnosis is very important. The most important techniques of dosimetric diagnosis are the dosimetry in vivo (cytogenetics and the counting in vivo of the whole body) and the bioassays. These techniques allow obtain data such as the radionuclide, the target organ, the absorbed dose, etc. At the same time, the doctor in charge must be attentive to the patients symptoms and their manifestation time, since they are an indicator, first, the patient suffered an irradiation, and second, of the range esteem of the received radiation dose. These are the parameters that are useful as criterion to decide if a person has to receive some treatment and select the methodologies that

Bowtie Risk Management methodology and Modern Nuclear Safety Reports

International Nuclear Information System (INIS)

Ilizastigui Pérez, F.

2016-01-01

The Safety Report (SR) plays a crucial role within the nuclear licensing regime as the principal means for demonstrating the adequacy of safety analysis for a nuclear facility to ensure that it can be constructed, operated, maintained, shut down, and decommissioned safely and in compliance with applicable laws and regulations. It serves as the basis for granting authorizations for the commencement of the main stages of the facility’s life cycle as well as decision-making processes related to safety. Historically, the majority of nuclear safety reports have operated under rather prescriptive regimes, with emphasis placed on demonstrations of the robustness of the facility’s design (design safety) against prescriptive technical requirements set by the regulatory body, and less attention paid to demonstrating the adequacy and effectiveness of Operator’s management system for managing risks to daily operation.

77 FR 10576 - Methodology for Low Power/Shutdown Fire PRA

Science.gov (United States)

2012-02-22

... NUCLEAR REGULATORY COMMISSION [NRC-2011-0295] Methodology for Low Power/Shutdown Fire PRA AGENCY.../Shutdown Fire PRA.'' In response to request from members of the public, the NRC is extending the public... risk assessment (PRA) method for quantitatively analyzing fire risk in commercial nuclear power plants...

Verification and software validation for nuclear instrumentation

International Nuclear Information System (INIS)

Gaytan G, E.; Salgado G, J. R.; De Andrade O, E.; Ramirez G, A.

2014-10-01

In this work is presented a Verification Methodology and Software Validation, to be applied in instruments of nuclear use with associate software. This methodology was developed under the auspices of IAEA, through the regional projects RLA4022 (ARCAL XCIX) and RLA1011 (RLA CXXIII), led by Mexico. In the first project three plans and three procedures were elaborated taking into consideration IEEE standards, and in the second project these documents were updated considering ISO and IEC standards. The developed methodology has been distributed to the participant countries of Latin America in the ARCAL projects and two related courses have been imparted with the participation of several countries, and participating institutions of Mexico like Instituto Nacional de Investigaciones Nucleares (ININ), Comision Federal de Electricidad (CFE) and Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). In the ININ due to the necessity to work with Software Quality Guarantee in systems for the nuclear power plant of the CFE, a Software Quality Guarantee Plan and five procedures were developed in the year 2004, obtaining the qualification of the ININ for software development for the nuclear power plant of CFE. These first documents were developed taking like reference IEEE standards and regulator guides of NRC, being the first step for the development of the methodology. (Author)

Nuclear methods in environmental and energy research

Energy Technology Data Exchange (ETDEWEB)

Vogt, J R [ed.

1980-01-01

A total of 75 papers were presented on nuclear methods for analysis of environmental and biological samples. Sessions were devoted to software and mathematical methods; nuclear methods in atmospheric and water research; nuclear and atomic methodology; nuclear methods in biology and medicine; and nuclear methods in energy research.

Nuclear methods in environmental and energy research

International Nuclear Information System (INIS)

Vogt, J.R.

1980-01-01

A total of 75 papers were presented on nuclear methods for analysis of environmental and biological samples. Sessions were devoted to software and mathematical methods; nuclear methods in atmospheric and water research; nuclear and atomic methodology; nuclear methods in biology and medicine; and nuclear methods in energy research

Evaluation methodology for fixed-site physical protection systems

International Nuclear Information System (INIS)

Bennett, H.A.; Olascoaga, M.T.

1980-01-01

A system performance evaluation methodology has been developed to aid the Nuclear Regulatory Commission (NRC) in the implementation of new regulations designed to upgrade the physical protection of nuclear fuel cycle facilities. The evaluation methodology, called Safeguards Upgrade Rule Evaluation (SURE), provides a means of explicitly incorporating measures for highly important and often difficult to quantify performance factors, e.g., installation, maintenance, training and proficiency levels, compatibility of components in subsystems, etc. This is achieved by aggregating responses to component and system questionaires through successive levels of a functional hierarchy developed for each primary performance capability specified in the regulations, 10 CFR 73.45. An overall measure of performance for each capability is the result of this aggregation process. This paper provides a descripton of SURE

A methodology for determining the dynamic exchange of resources in nuclear fuel cycle simulation

Energy Technology Data Exchange (ETDEWEB)

Gidden, Matthew J., E-mail: gidden@iiasa.ac.at [International Institute for Applied Systems Analysis, Schlossplatz 1, A-2361 Laxenburg (Austria); University of Wisconsin – Madison, Department of Nuclear Engineering and Engineering Physics, Madison, WI 53706 (United States); Wilson, Paul P.H. [University of Wisconsin – Madison, Department of Nuclear Engineering and Engineering Physics, Madison, WI 53706 (United States)

2016-12-15

Highlights: • A novel fuel cycle simulation entity interaction mechanism is proposed. • A framework and implementation of the mechanism is described. • New facility outage and regional interaction scenario studies are described and analyzed. - Abstract: Simulation of the nuclear fuel cycle can be performed using a wide range of techniques and methodologies. Past efforts have focused on specific fuel cycles or reactor technologies. The CYCLUS fuel cycle simulator seeks to separate the design of the simulation from the fuel cycle or technologies of interest. In order to support this separation, a robust supply–demand communication and solution framework is required. Accordingly an agent-based supply-chain framework, the Dynamic Resource Exchange (DRE), has been designed implemented in CYCLUS. It supports the communication of complex resources, namely isotopic compositions of nuclear fuel, between fuel cycle facilities and their managers (e.g., institutions and regions). Instances of supply and demand are defined as an optimization problem and solved for each timestep. Importantly, the DRE allows each agent in the simulation to independently indicate preference for specific trading options in order to meet both physics requirements and satisfy constraints imposed by potential socio-political models. To display the variety of possible simulations that the DRE enables, example scenarios are formulated and described. Important features include key fuel-cycle facility outages, introduction of external recycled fuel sources (similar to the current mixed oxide (MOX) fuel fabrication facility in the United States), and nontrivial interactions between fuel cycles existing in different regions.

A methodology for determining the dynamic exchange of resources in nuclear fuel cycle simulation

International Nuclear Information System (INIS)

Gidden, Matthew J.; Wilson, Paul P.H.

2016-01-01

Highlights: • A novel fuel cycle simulation entity interaction mechanism is proposed. • A framework and implementation of the mechanism is described. • New facility outage and regional interaction scenario studies are described and analyzed. - Abstract: Simulation of the nuclear fuel cycle can be performed using a wide range of techniques and methodologies. Past efforts have focused on specific fuel cycles or reactor technologies. The CYCLUS fuel cycle simulator seeks to separate the design of the simulation from the fuel cycle or technologies of interest. In order to support this separation, a robust supply–demand communication and solution framework is required. Accordingly an agent-based supply-chain framework, the Dynamic Resource Exchange (DRE), has been designed implemented in CYCLUS. It supports the communication of complex resources, namely isotopic compositions of nuclear fuel, between fuel cycle facilities and their managers (e.g., institutions and regions). Instances of supply and demand are defined as an optimization problem and solved for each timestep. Importantly, the DRE allows each agent in the simulation to independently indicate preference for specific trading options in order to meet both physics requirements and satisfy constraints imposed by potential socio-political models. To display the variety of possible simulations that the DRE enables, example scenarios are formulated and described. Important features include key fuel-cycle facility outages, introduction of external recycled fuel sources (similar to the current mixed oxide (MOX) fuel fabrication facility in the United States), and nontrivial interactions between fuel cycles existing in different regions.

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)

Reference values in blood elements in crioula breed horses by nuclear methodology

International Nuclear Information System (INIS)

Baptista, Tatyana Spinosa

2010-01-01

In this study the reference value for Br (0,0008 - 0,0056 gL -1 ), Ca (0,089 - 0,369 gL -1 ), Cl (2,10 - 3,26 gL -1 ), Fe (0,381 - 0,689 gL -1 ), I (0,00018 - 0,00266 gL -1 ), K (1,14 - 2,74 gL -1 ), Mg (0,030 - 0,074 gL -1 ), Na (1,36 - 2,80 gL -1 ), P ( -1 ), S (0,99 - 2,79 gL -1 ) and Zn (0,0012 - 0,0048 gL -1 ) as well as the correlation matrix in blood of Crioulo breed horses were determined using nuclear methodology (Neutron Activation Analysis Technique). These data allowed to identifying physiological alterations related to the sex and regime of exercise (hyperimmune sera production at Butantan Institute, Sao Paulo, Brasil). To perform these analyses was used 20 adult horses (8 males and 12 females), with average mass 350 kg, without clinical signs of disease, 1-3 years old, kept on pasture in Sao Joaquim Farm at Butantan Institute (Sao Paulo city). Other group just immunized, composed by 6 equines males (same age and weight), were also analyzed. These data are an important support to understand the physiological functions of these elements in blood during the process of sera production. (author)

A study on assessment methodology of surveillance test interval and allowed outage time

Energy Technology Data Exchange (ETDEWEB)

Chung, Chang Hyun; You, Young Woo; Cho, Jae Seon; Huh, Chang Wook; Kim, Do Hyoung; Kim, Ju Youl; Kim, Yoon Ik; Yang, Hui Chang; Park, Kang Min [Seoul National Univ., Seoul (Korea, Republic of)

1998-03-15

The objectives of this study is the development of methodology by which assesses the optimization of Surveillance Test Internal(STI) and Allowed Outage Time(AOT) using PSA method that can supplement the current deterministic methods and the improvement of Korean nuclear power plant safety. In this study, the survey about the assessment methodologies, modelings and results performed by domestic and international researches are performed as the basic step before developing the assessment methodology of this study. The assessment methodology that supplement the revealed problems in many other studies is presented and the application of new methodology into the example system assures the feasibility of this method. The sensitivity analyses about the failure factors of the components are performed in the bases of the and AOT is quantified. And the reliability assessment methodology about the diesel generator is reviewed and applied to the PSA code. The qualitative assessment for the STI/AOR of RPS/ESFAS assured safety the most important system in the nuclear power plant are performed.

Study of social responsibility of the Nuclear and Energy Research Institute of Sao Paulo (IPEN/CNEN-SP); Estudo da responsabilidade social do Instituto de Pesquisas Energeticas e Nucleares de Sao Paulo (IPEN/CNEN-SP)

Energy Technology Data Exchange (ETDEWEB)

Mutarelli, Rita de Cassia

2014-07-01

Over the years, the socio-environmental concept has grown through programs, conferences and several activities that have been held in Brazil and worldwide. Sustainability and social responsibility are now an integral part of everyday life of organizations The Instituto de Pesquisas Energeticas e Nucleares (IPEN), which is the focus of this research, is committed to the improvement of Brazilian quality of life. Based on IPEN's mission, and due to the lack of tools for assessing socio-environmental actions, this research aims to propose an assessment tool for social responsibility, which may also be a methodological resource committed to the improvement of the Institute. Through indicators and dimensions, a methodology to assess social responsibility and identify both strengths and weaknesses was designed. The methodology was administered to IPEN, and the results demonstrated positive aspects regarding actions towards the internal publics and negative aspects towards the external publics that require improvement. The results obtained were satisfactory. Nevertheless, as the subject of this study is a broad theme, further studies are suggested. IPEN's board may use the results of this research as a tool to help them identify feasible socio-environmental actions to be implemented in the institute. (author)

Covariance Evaluation Methodology for Neutron Cross Sections

Energy Technology Data Exchange (ETDEWEB)

Herman,M.; Arcilla, R.; Mattoon, C.M.; Mughabghab, S.F.; Oblozinsky, P.; Pigni, M.; Pritychenko, b.; Songzoni, A.A.

2008-09-01

We present the NNDC-BNL methodology for estimating neutron cross section covariances in thermal, resolved resonance, unresolved resonance and fast neutron regions. The three key elements of the methodology are Atlas of Neutron Resonances, nuclear reaction code EMPIRE, and the Bayesian code implementing Kalman filter concept. The covariance data processing, visualization and distribution capabilities are integral components of the NNDC methodology. We illustrate its application on examples including relatively detailed evaluation of covariances for two individual nuclei and massive production of simple covariance estimates for 307 materials. Certain peculiarities regarding evaluation of covariances for resolved resonances and the consistency between resonance parameter uncertainties and thermal cross section uncertainties are also discussed.

Evaluation methodology based on physical security assessment results: a utility theory approach

International Nuclear Information System (INIS)

Bennett, H.A.; Olascoaga, M.T.

1978-03-01

This report describes an evaluation methodology which aggregates physical security assessment results for nuclear facilities into an overall measure of adequacy. This methodology utilizes utility theory and conforms to a hierarchical structure developed by the NRC. Implementation of the methodology is illustrated by several examples. Recommendations for improvements in the evaluation process are given

Development of in-service inspection plans for nuclear components at the Surry 1 nuclear power station

International Nuclear Information System (INIS)

Vo, T.V.; Simonen, F.A.; Doctor, S.R.; Smith, B.W.; Gore, B.F.

1993-01-01

As part of the nondestructive evaluation reliability program sponsored by the US Nuclear Regulatory Commission at Pacific Northwest Laboratory, a methodology has been developed for establishing in-service inspection priorities of nuclear power plant components. The method uses results of probabilistic risk assessment in conjunction with the techniques of failure modes and effects analysis to identify and prioritize the most risk-important systems and components for inspection at nuclear power plants. Surry nuclear power station unit 1 was selected for demonstrating the methodology. The specific systems selected for analysis were the reactor pressure vessel, the reactor coolant, the low pressure injection including the accumulators, and the auxiliary feedwater. The results provide a risk-based ranking of components that can be used to establish a prioritization of the components and a basis for developing improved in-service inspection plans at nuclear power plants

National Inventories and Management Strategies for Spent Nuclear Fuel and Radioactive Waste. Extended Methodology for the Common Presentation of Data

International Nuclear Information System (INIS)

Volckaert, Geert; Dionisi, Mario; Heath, Maurice; Kugel, Karin; Garamszeghy, Miklos; Leclaire, Arnaud; Deryabin, Sergey; Hedberg, Bengt; Dapei, Dominic; Lebedev, Vladimir; )

2017-01-01

Radioactive waste inventory data are an important element in the development of a national radioactive waste management program since these data affect the design and selection of the ultimate disposal methods. Inventory data are generally presented as an amount of radioactive waste under various waste classes, according to the waste classification scheme developed and adopted by the country or national program in question. Various waste classification schemes have evolved in most countries, and these schemes classify radioactive waste according to its origin, to criteria related to the protection of workers or to the physical, chemical and radiological properties of the waste and the planned disposal method(s). The diversity in classification schemes across countries has restricted the possibility of comparing waste inventories and led to difficulties in interpreting waste management practices, both nationally and internationally. To help improve this situation, the Nuclear Energy Agency developed a methodology that ensures consistency of national radioactive waste and spent fuel inventory data when presenting them in a common scheme in direct connection with accepted management strategy and disposal routes. This report is a follow up to the 2016 report that introduced the methodology and presenting scheme for spent fuel, and it now extends this methodology and presenting scheme to all types of radioactive waste and corresponding management strategies

The effective communication methodology and influence of merit information on nuclear power

International Nuclear Information System (INIS)

Oiso, Shinichi

2007-01-01

It was found by the survey the author carried out in 2005 that there is a possibility that even the person who opposes nuclear power generation may change his or her opinion after understanding the advantage of nuclear power. Then, how should merit information be transmitted? Is there a possibility that people feel repulsion after receiving merit information? What is the influence of providing merit information of nuclear power? Those kinds of questions were investigated in 2006. As a result, it was found that the use of magazine and NPO/NGO is effective. The utilization of all-night television broadcasting, iPod, energy environmental education in schools and science cafe have an effect too, especially for young generation. It was also found that 20% or less of the people feel repulsion for providing merit information of nuclear power. Concerning people's attitude towards nuclear power utilization, it was found that the number of those who support nuclear power generation tended to increase significantly by providing information depicting merits or benefits of nuclear power, however, it did not increase by explaining electric power companies' effort to promote nuclear power. Further more, concerning to the image of a nuclear power station site, it became clear that merit information of nuclear power provided positive effect for some items in explaining nuclear power generation. (author)

Challenges for nuclear medicine in the 1990s

International Nuclear Information System (INIS)

Ell, P.J.

1992-01-01

This article discusses the problems facing nuclear medicine in the coming decade and outlines the areas in which new developments or expansion can be expected. The questions considered include legislative requirements, the need to educate the public and the medical profession on the strengths of nuclear medicine, approaches to cost-benefit analysis, and development of new technologies and new radiopharmaceuticals. There is also an evaluation of expansion in nuclear medicine using both existing methodology and new methodologies. (author)

Establishment of Assessment Methodology Improvement of IAEA INPRO Proliferation Resistance

Energy Technology Data Exchange (ETDEWEB)

Park, J. H.; Yang, M. S.; Song, K. C.; Ko, W. I.; Kim, H. D.; Kim, Y. I.; Rhee, B. W.; Kim, H. T.

2008-03-15

For the development of assessment methodology of acquisition and diversion pathway of nuclear material, the PR assessment methodology which has been developed by GEN-IV PR and PP group was reviewed regarding the acquisition and diversion pathway of nuclear material and we proposed the research areas to develop the model of acquisition and diversion pathway of nuclear material including misuse of fuel cycle facilities and one of the IAEA INPRO CRPs which is aiming to develop its model. From the present study, its preliminary model for acquisition and diversion pathway of nuclear material was obtained. For preliminary evaluation of DUPIC system using methodology of acquisition/diversion pathway of nm and review of pyro-processing system characteristics, the research direction and work procedure was established to develop the assessment methodology of User Requirement 4 of INPRO PR by; 1) selection of the possible pathway to acquire and divert the nuclear material of DUPIC system, 2) the analysis of selected pathway, 3) the development of the assessment methodology of robustness and multiplicity of an INS. And, the PR characteristics and process/material flow analysis of the Pyro-processing system were preliminarily studied. For establishment of R and D direction for an INS and supporting international cooperation research, the collaborative research project titled as 'Acquisition and Diversion pathway analysis of Proliferation Resistance' as one of activities of IAEA INPRO was proposed, since Korean Government decided to actively support the IAEA INPRO. In order to review and clarify the Terms of Reference (TOR) of a Korean Proposed Collaborative Project (ROK1), two INPRO Consultancy Meetings were held. Its results were presented at two INPRO Steering Committees and the finalized TOR of Korean Proposal submit the 12-th INPRO Steering Committee Meeting which was held Dec. 3-5 2007. Four participants including USA, Canada, China and European Community (EC

Establishment of Assessment Methodology Improvement of IAEA INPRO Proliferation Resistance

International Nuclear Information System (INIS)

Park, J. H.; Yang, M. S.; Song, K. C.; Ko, W. I.; Kim, H. D.; Kim, Y. I.; Rhee, B. W.; Kim, H. T.

2008-03-01

For the development of assessment methodology of acquisition and diversion pathway of nuclear material, the PR assessment methodology which has been developed by GEN-IV PR and PP group was reviewed regarding the acquisition and diversion pathway of nuclear material and we proposed the research areas to develop the model of acquisition and diversion pathway of nuclear material including misuse of fuel cycle facilities and one of the IAEA INPRO CRPs which is aiming to develop its model. From the present study, its preliminary model for acquisition and diversion pathway of nuclear material was obtained. For preliminary evaluation of DUPIC system using methodology of acquisition/diversion pathway of nm and review of pyro-processing system characteristics, the research direction and work procedure was established to develop the assessment methodology of User Requirement 4 of INPRO PR by; 1) selection of the possible pathway to acquire and divert the nuclear material of DUPIC system, 2) the analysis of selected pathway, 3) the development of the assessment methodology of robustness and multiplicity of an INS. And, the PR characteristics and process/material flow analysis of the Pyro-processing system were preliminarily studied. For establishment of R and D direction for an INS and supporting international cooperation research, the collaborative research project titled as 'Acquisition and Diversion pathway analysis of Proliferation Resistance' as one of activities of IAEA INPRO was proposed, since Korean Government decided to actively support the IAEA INPRO. In order to review and clarify the Terms of Reference (TOR) of a Korean Proposed Collaborative Project (ROK1), two INPRO Consultancy Meetings were held. Its results were presented at two INPRO Steering Committees and the finalized TOR of Korean Proposal submit the 12-th INPRO Steering Committee Meeting which was held Dec. 3-5 2007. Four participants including USA, Canada, China and European Community (EC) have decided

Update of Part 61 impacts analysis methodology

International Nuclear Information System (INIS)

Oztunali, O.I.; Roles, G.W.

1986-01-01

The US Nuclear Regulatory Commission is expanding the impacts analysis methodology used during the development of the 10 CFR Part 61 rule to allow improved consideration of costs and impacts of disposal of waste that exceeds Class C concentrations. The project includes updating the computer codes that comprise the methodology, reviewing and updating data assumptions on waste streams and disposal technologies, and calculation of costs for small as well as large disposal facilities. This paper outlines work done to date on this project

Update of Part 61 impacts analysis methodology

International Nuclear Information System (INIS)

Oztunali, O.I.; Roles, G.W.; US Nuclear Regulatory Commission, Washington, DC 20555)

1985-01-01

The US Nuclear Regulatory Commission is expanding the impacts analysis methodology used during the development of the 10 CFR Part 61 regulation to allow improved consideration of costs and impacts of disposal of waste that exceeds Class C concentrations. The project includes updating the computer codes that comprise the methodology, reviewing and updating data assumptions on waste streams and disposal technologies, and calculation of costs for small as well as large disposal facilities. This paper outlines work done to date on this project

Compilation of the nuclear codes available in CTA

International Nuclear Information System (INIS)

D'Oliveira, A.B.; Moura Neto, C. de; Amorim, E.S. do; Ferreira, W.J.

1979-07-01

The present work is a compilation of some nuclear codes available in the Divisao de Estudos Avancados of the Instituto de Atividades Espaciais, (EAV/IAE/CTA). The codes are organized as the classification given by the Argonne National Laboratory. In each code are given: author, institution of origin, abstract, programming language and existent bibliography. (Author) [pt

Development of a simplified statistical methodology for nuclear fuel rod internal pressure calculation

International Nuclear Information System (INIS)

Kim, Kyu Tae; Kim, Oh Hwan

1999-01-01

A simplified statistical methodology is developed in order to both reduce over-conservatism of deterministic methodologies employed for PWR fuel rod internal pressure (RIP) calculation and simplify the complicated calculation procedure of the widely used statistical methodology which employs the response surface method and Monte Carlo simulation. The simplified statistical methodology employs the system moment method with a deterministic statistical methodology employs the system moment method with a deterministic approach in determining the maximum variance of RIP. The maximum RIP variance is determined with the square sum of each maximum value of a mean RIP value times a RIP sensitivity factor for all input variables considered. This approach makes this simplified statistical methodology much more efficient in the routine reload core design analysis since it eliminates the numerous calculations required for the power history-dependent RIP variance determination. This simplified statistical methodology is shown to be more conservative in generating RIP distribution than the widely used statistical methodology. Comparison of the significances of each input variable to RIP indicates that fission gas release model is the most significant input variable. (author). 11 refs., 6 figs., 2 tabs

Nuclear medicine and mathematics

Energy Technology Data Exchange (ETDEWEB)

Pedroso de Lima, J.J. [Dept. de Biofisica e Proc. de Imagem, IBILI - Faculdade de Medicina, Coimbra (Portugal)

1996-06-01

The purpose of this review is not to present a comprehensive description of all the mathematical tools used in nuclear medicine, but to emphasize the importance of the mathematical method in nuclear medicine and to elucidate some of the mathematical concepts currently used. We can distinguish three different areas in which mathematical support has been offered to nuclear medicine: Physiology, methodology and data processing. Nevertheless, the boundaries between these areas can be indistinct. It is impossible in a single article to give even an idea of the extent and complexity of the procedures currently usede in nuclear medicine, such as image processing, reconstruction from projections and artificial intelligence. These disciplines do not belong to nuclear medicine: They are already branches of engineering, and my interest will reside simply in revealing a little of the elegance and the fantastic potential of these new `allies` of nuclear medicine. In this review the mathematics of physiological interpretation and methodology are considered together in the same section. General aspects of data-processing methods, including image processing and artificial intelligence, are briefly analysed. The mathematical tools that are most often used to assist the interpretation of biological phenomena in nuclear medicine are considered; these include convolution and deconvolution methods, Fourier analysis, factorial analysis and neural networking. (orig.)

Nuclear medicine and mathematics

International Nuclear Information System (INIS)

Pedroso de Lima, J.J.

1996-01-01

The purpose of this review is not to present a comprehensive description of all the mathematical tools used in nuclear medicine, but to emphasize the importance of the mathematical method in nuclear medicine and to elucidate some of the mathematical concepts currently used. We can distinguish three different areas in which mathematical support has been offered to nuclear medicine: Physiology, methodology and data processing. Nevertheless, the boundaries between these areas can be indistinct. It is impossible in a single article to give even an idea of the extent and complexity of the procedures currently usede in nuclear medicine, such as image processing, reconstruction from projections and artificial intelligence. These disciplines do not belong to nuclear medicine: They are already branches of engineering, and my interest will reside simply in revealing a little of the elegance and the fantastic potential of these new 'allies' of nuclear medicine. In this review the mathematics of physiological interpretation and methodology are considered together in the same section. General aspects of data-processing methods, including image processing and artificial intelligence, are briefly analysed. The mathematical tools that are most often used to assist the interpretation of biological phenomena in nuclear medicine are considered; these include convolution and deconvolution methods, Fourier analysis, factorial analysis and neural networking. (orig.)

Eliciting and communicating expert judgments: methodology and application to nuclear safety

International Nuclear Information System (INIS)

Winterfeldt, D. von; Commission of the European Communities, Ispra

1989-01-01

Expert judgment has always been used informally in the analysis of complex engineering problems. Increasingly, however, the use of expert judgment has been formalized by eliciting judgments in an explicit, documented and often quantitative way. In nuclear safety studies the need for formal elicitation of expert judgments arises because of the lack of data and experiences, the need to adapt model results to the specific circumstances of a plant, and the large uncertainties surrounding the events and quantities that characterize an accident sequence. The recognition of the need for a formal elicitation of expert judgments has led to one of the most extensive expert elicitation processes to date in the context of the NUREG 1150 study. About 30 safety issues were quantified using expert judgments about probabilities of various uncertain events and quantities, ranging from the failure of a check valve in the cooling system to the pressure built up due to hydrogen production to release fractions of various radionuclides. In total, some 1000 probability distributions were elicited from some 50 experts. This paper first motivates the use of formal expert elicitation in complex engineering studies and describes the methodology of formal expert elicitation. Subsequently, it describes the overall approach of NUREG 1150 and provides an example of the elicitation of the probability of a bypass failure in a pressurized water reactor. The paper ends by discussing some lessons learned, problems encountered and by providing some recommendations

Methodology for qualification of in-service inspection systems for WWER nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

International Nuclear Information System (INIS)

1998-03-01

Program was initiated by IAEA in 1990 with the aim to assist the countries of Central and Eastern Europe and former Soviet Union in evaluating the safety of their first generation WWER-440/230 nuclear power plants. The main objectives were: to identify major design and operational safety issues; to establish international consensus on priorities for safety improvements; and to provide assistance in the review of the competence and and adequacy of safety improvement programs. The scope was extended in 1992 to include RBMK, WWER-440/312 and WWER-1000 plants in operation and under construction. Integrity of primary circuit is fundamental for the safe operation of any nuclear power plant. In-service inspection (ISI) in general terms and in particular, non-destructive tests (NDT) play a key role in maintaining primary circuit integrity. This report provides a methodology for qualification of ISI systems which might be used by WWER operating countries as a commonly accepted basis for further development of the necessary qualification related infrastructures. It also provides several qualification principles defining the administrative framework needed for the practical implementation of the methodology, a description of the process of qualification of an inspection system, specifying its minimum technical and documentation related requirements, as well as specific requirements with regard to the NDT procedures, equipment and personnel to be qualified and the test specimen to be used in practical trials. Finally, the report suggests an appropriate distribution of responsibilities among all the parties involved in a qualification process, based on international practice

A performance assessment methodology for low-level waste facilities

International Nuclear Information System (INIS)

Kozak, M.W.; Chu, M.S.Y.; Mattingly, P.A.

1990-07-01

A performance assessment methodology has been developed for use by the US Nuclear Regulatory Commission in evaluating license applications for low-level waste disposal facilities. This report provides a summary of background reports on the development of the methodology and an overview of the models and codes selected for the methodology. The overview includes discussions of the philosophy and structure of the methodology and a sequential procedure for applying the methodology. Discussions are provided of models and associated assumptions that are appropriate for each phase of the methodology, the goals of each phase, data required to implement the models, significant sources of uncertainty associated with each phase, and the computer codes used to implement the appropriate models. In addition, a sample demonstration of the methodology is presented for a simple conceptual model. 64 refs., 12 figs., 15 tabs

Methodology For Evaluation Of Regulatory Effectiveness In Physical Protection

International Nuclear Information System (INIS)

Izmaylov, Alexander; Valente, John; Griggs, James R.; Rexroth, Paul; Piskarev, Alexander; Babkin, Vladimir; Sokolov, Egor; Melton, Ronald B.; Cunningham, Mitchel E.; Baker, Kathryn A.; Brothers, Alan J.

2005-01-01

Material protection, control, and accounting (MPC and A) regulatory documents play an important role in securing and protecting nuclear material by regulating a variety of activities at different hierarchical levels. The development, implementation, and practical application of these regulatory documents requires a significant investment of financial and material resources. Therefore, it is important to evaluate the effectiveness of the regulatory development process and the extent to which regulations improve the effectiveness of MPC and A at nuclear sites. The joint Russian and U.S. Regulatory Development Project has a goal of evaluating the effectiveness of regulatory documents developed for MPC and A. As part of this joint Project, a methodology for evaluating effectiveness has been developed. This methodology was developed around physical protection objectives. The developed methodology specifies physical protection objectives to be accomplished through the implementation of a regulatory system based on the physical protection goals at the nuclear sites. It includes approaches to assessing regulatory effectiveness, the hierarchical structure of physical protection objectives to be accomplished through implementing regulations, a 'mapping' of the physical protection objectives to the regulatory framework, a list of criteria for evaluating the effectiveness of physical protection regulations and effectiveness indicators, as well as means and methods for gathering information and implementation of this evaluation.

Study of the distribution of ions and metals in blood using nuclear methodology; Estudo da distribuicao de ions e metais em sangue via metodologia nuclear

Energy Technology Data Exchange (ETDEWEB)

Oliveira, Laura Cristina de

2008-07-01

The present study consists of using nuclear tools aiming to establish an alternative procedure to perform biochemistry analyses in whole blood to help the diagnosis of diverse pathologies. The aim is to determine the ions and metals concentrations in whole blood of human beings (specifically: Br, Cl, K e Na), using neutron activation analysis, providing the limits of normality, as well as, the matrix of the correlation for these elements. To perform this study, 283 samples of whole blood had been analyzed (of healthy volunteers selected from blood banks), resulting in the limits of normality for Br (0.0067 - 0.0263 gl{sup -1}), Cl (2.54 - 3.50 gl{sup -1}), K (1.33 - 1.89 gl{sup -1}) and Na (1.48 - 2.06 gl{sup -1}). These data are the first estimates for reference values in whole blood of the Brazilian population. These limits were evaluated in function of the sex and age for checking the biological differences. The behavior of these limits was also evaluated for different populations, i.e., in two distinct regions: Southeast (blood collection carried out in Sao Paulo city) and Northeast (blood collection carried out in Recife city). These places were chosen in function of the similarities (cities with high concentration people and industrialized). Furthermore, a systematic study of these limits was also evaluated, in the period of 4 (four) years, in Sao Paulo city. This analysis was elaborated in function of time due the necessity to update these data, therefore they act as environment monitors. The estimation for Ca and Fe were also proposal for a set of 22 samples of whole blood.(author)

Doença Pulmonar Obstrutiva Crónica em Portugal: estudo Pneumobil (1995 e estudo de prevalência de 2002 revisitados

Directory of Open Access Journals (Sweden)

J. Cardoso

2013-05-01

Full Text Available Resumo: Introdução: A doença pulmonar obstrutiva crónica (DPOC tem sido, ao longo dos anos, uma importante causa de morbilidade e mortalidade no mundo. Em 1995, a implementação de um rastreio da função respiratória pareceu a forma mais adequada para alertar para os sintomas respiratórios negligenciados e sensibilizar para os rastreios espirométricos. Em 2002, foram criadas novas normas consensuais de diagnóstico e o reconhecimento de que a prevalência da DPOC depende dos critérios de definição de obstrução das vias aéreas. O objetivo deste estudo foi revisitar estes 2 estudos e publicar alguns dos resultados e respetivas metodologias. Métodos: Dos 12 684 indivíduos que constavam da base de dados do Pneumobil, apenas os indivíduos com 40 e mais anos (n = 9061 foram considerados para esta análise. No estudo de 2002 foi incluída uma amostra aleatorizada e representativa de 1384 indivíduos, com idades entre os 35 e os 69 anos. Resultados: A prevalência da DPOC foi de 8,96% no estudo Pneumobil e de 5,34% no estudo de 2002. Em ambos os estudos, a presença da DPOC foi superior no sexo masculino, tendo-se verificado uma associação positiva entre a presença da DPOC e os grupos etários mais velhos. Nos fumadores e ex-fumadores encontrou-se maior proporção de casos com DPOC. Conclusões: A prevalência em Portugal é mais baixa do que noutros países europeus, o que pode estar relacionado com uma menor prevalência de tabagismo. De um modo geral, os fatores de risco mais importantes que mostraram a associação com a DPOC foram a idade maior do que 60 anos, o sexo masculino e a exposição tabágica. Todos os aspetos e as limitações que se referem a diferentes critérios de definição e a metodologias de recrutamento realçam a necessidade de métodos padronizados para determinar a prevalência da DPOC e os

User requirements for innovative nuclear reactors and fuel cycle technologies in the area of economics, environment, safety, waste management, proliferation resistance and cross cutting issues, and methodology for innovative technologies assessment

International Nuclear Information System (INIS)

Kupitz, Juergen; Depisch, Frank; Allan, Colin

2003-01-01

The IAEA General Conference in 2000 has invited ''all interested Member States to combine their efforts under the aegis of the Agency in considering the issues of the nuclear fuel cycle, in particular by examining innovative and proliferation-resistant nuclear technology''. In response to this invitation, the IAEA initiated an ''International Project on Innovative Nuclear Reactors and Fuel Cycles'', INPRO. The overall objectives of INPRO is to help to ensure that nuclear energy is available to contribute in fulfilling in a sustainable manner energy needs in the 21st century, and to bring together all interested Member States, both technology holders and technology users, to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles that use sound and economically competitive technology. Phase-I of INPRO was initiated in May 2001. During Phase-I, work was subdivided in two sub phase: Phase 1A (finished in June 2003) and Phase 1B (started in June 2003). Phase 1A dealt with the definition of Basic Principles, User Requirements and Criteria, and the development of a methodology for the evaluation of innovative nuclear technologies. In Phase 1A, task groups for several areas were established: (a) Prospects and Potentials of Nuclear Power, (b) Economics; (c) Sustainability and Environment, (d) Safety of Nuclear Installations, (e) Waste Management, (f) Proliferation Resistance, (g) Crosscutting issues and (h) for the Methodology for Assessment. In Phase-IB evaluations of innovative nuclear energy technologies will be performed by Member States against the INPRO Basic Principles, User Requirements and Criteria. This paper summarizes the results achieved in the Phase 1A of INPRO and is a cooperative effort of the INPRO team, consisting of all INPRO cost free experts and task managers. (author)

EnergiTools. A methodology for performance monitoring and diagnosis

International Nuclear Information System (INIS)

Ancion, P.; Bastien, R.; Ringdahl, K.

2000-01-01

EnergiTools is a performance monitoring and diagnostic tool that combines the power of on-line process data acquisition with advanced diagnosis methodologies. Analytical models based on thermodynamic principles are combined with neural networks to validate sensor data and to estimate missing or faulty measurements. Advanced diagnostic technologies are then applied to point out potential faults and areas to be investigated further. The diagnosis methodologies are based on Bayesian belief networks. Expert knowledge is captured in the form of the fault-symptom relationships and includes historical information as the likelihood of faults and symptoms. The methodology produces the likelihood of component failure root causes using the expert knowledge base. EnergiTools is used at Ringhals nuclear power plants. It has led to the diagnosis of various performance issues. Three case studies based on this plant data and model are presented and illustrate the diagnosis support methodologies implemented in EnergiTools . In the first case, the analytical data qualification technique points out several faulty measurements. The application of a neural network for the estimation of the nuclear reactor power by interpreting several plant indicators is then illustrated. The use of the Bayesian belief networks is finally described. (author)

Demonstration of an infiltration evaluation methodology

International Nuclear Information System (INIS)

Smyth, J.D.; Gee, G.W.; Kincaid, C.T.; Nichols, W.M.; Bresler, E.

1990-07-01

An Infiltration Evaluation Methodology (IEM) was developed for the US Nuclear Regulatory Commission (NRC) by Pacific Northwest Laboratory (PNL) to provide a consistent, well formulated approach for evaluating drainage through engineered covers at low-level radioactive waste (LLW) sites. The methodology is designed to help evaluate the ability of proposed waste site covers to minimize drainage for LLW site license applications and for sites associated with the Uranium Mill Tailings Remedial Action (UMTRA) program. The objective of this methodology is to estimate the drainage through an engineered burial site cover system. The drainage estimate can be used as an input to a broader performance assessment methodology currently under development by the NRC. The methodology is designed to simulate, at the field scale, significant factors and hydrologic conditions which determine or influence estimates of infiltration, long-term moisture content profiles, and drainage from engineered covers and barriers. The IEM developed under this study acknowledges the uncertainty inherent in soil properties and quantifies the influence of such uncertainty on the estimates of drainage in engineered cover systems at waste disposal sites. 6 refs., 1 fig

Experience and benefits from using the EPRI MOV Performance Prediction Methodology in nuclear power plants

International Nuclear Information System (INIS)

Walker, T.; Damerell, P.S.

1999-01-01

The EPRI MOV Performance Prediction Methodology (PPM) is an effective tool for evaluating design basis thrust and torque requirements for MOVs. Use of the PPM has become more widespread in US nuclear power plants as they close out their Generic Letter (GL) 89-10 programs and address MOV periodic verification per GL 96-05. The PPM has also been used at plants outside the US, many of which are implementing programs similar to US plants' GL 89-10 programs. The USNRC Safety Evaluation of the PPM and the USNRC's discussion of the PPM in GL 96-05 make the PPM an attractive alternative to differential pressure (DP) testing, which can be costly and time-consuming. Significant experience and benefits, which are summarized in this paper, have been gained using the PPM. Although use of PPM requires a commitment of resources, the benefits of a solidly justified approach and a reduced need for DP testing provide a substantial safety and economic benefit. (author)

Development of an Evaluation Methodology for Loss of Large Area Induced from Extreme Events with Malicious Origin

International Nuclear Information System (INIS)

Kim, S.C.; Park, J.S.; Chang, D.J.; Kim, D.H.; Lee, S.W.; Lee, Y.J.; Kim, H.W.

2016-01-01

Event of loss of large area (LOLA) induced from extreme external event at multi-units nuclear installation has been emerged a new challenges in the realm of nuclear safety and regulation after Fukushima Dai-Ichi accident. The relevant information and experience on evaluation methodology and regulatory requirements are rarely available and negative to share due to the security sensitivity. Most of countries has been prepared their own regulatory requirements and methodologies to evaluate impact of LOLA at nuclear power plant. In Korea, newly amended the Nuclear Safety Acts requires to assess LOLA in terms of EDMG (Extended Damage Mitigation Guideline). Korea Institute of Nuclear Safety (KINS) has performed a pilot research project to develop the methodology and regulatory review guidance on LOLA at multi-units nuclear power plant since 2014. Through this research, we proposed a methodology to identify the strategies for preventive and mitigation of the consequences of LOLA utilizing PSA techniques or its results. The proposed methodology is comprised of 8 steps including policy consideration, threat evaluation, identification of damage path sets, SSCs capacity evaluation and identification of mitigation measures and strategies. The consequence of LOLA due to malevolent aircraft crash may significantly susceptible with analysis assumptions including type of aircraft, amount of residual fuel, and hittable angle and so on, which cannot be shared overtly. This paper introduces a evaluation methodology for LOLA using PSA technique and its results. Also we provide a case study to evaluate hittable access angle using flight simulator for two types of air crafts and to identify potential path sets leading to core damage by affected SSCs within damaged area.(author).

Supplement to the Disposal Criticality Analysis Methodology

International Nuclear Information System (INIS)

Thomas, D.A.

1999-01-01

The methodology for evaluating criticality potential for high-level radioactive waste and spent nuclear fuel after the repository is sealed and permanently closed is described in the Disposal Criticality Analysis Methodology Topical Report (DOE 1998b). The topical report provides a process for validating various models that are contained in the methodology and states that validation will be performed to support License Application. The Supplement to the Disposal Criticality Analysis Methodology provides a summary of data and analyses that will be used for validating these models and will be included in the model validation reports. The supplement also summarizes the process that will be followed in developing the model validation reports. These reports will satisfy commitments made in the topical report, and thus support the use of the methodology for Site Recommendation and License Application. It is concluded that this report meets the objective of presenting additional information along with references that support the methodology presented in the topical report and can be used both in validation reports and in answering request for additional information received from the Nuclear Regulatory Commission concerning the topical report. The data and analyses summarized in this report and presented in the references are not sufficient to complete a validation report. However, this information will provide a basis for several of the validation reports. Data from several references in this report have been identified with TBV-1349. Release of the TBV governing this data is required prior to its use in quality affecting activities and for use in analyses affecting procurement, construction, or fabrication. Subsequent to the initiation of TBV-1349, DOE issued a concurrence letter (Mellington 1999) approving the request to identify information taken from the references specified in Section 1.4 as accepted data

Methodology for ranking restoration options

International Nuclear Information System (INIS)

Hedemann Jensen, Per

1999-04-01

The work described in this report has been performed as a part of the RESTRAT Project FI4P-CT95-0021a (PL 950128) co-funded by the Nuclear Fission Safety Programme of the European Commission. The RESTRAT project has the overall objective of developing generic methodologies for ranking restoration techniques as a function of contamination and site characteristics. The project includes analyses of existing remediation methodologies and contaminated sites, and is structured in the following steps: characterisation of relevant contaminated sites; identification and characterisation of relevant restoration techniques; assessment of the radiological impact; development and application of a selection methodology for restoration options; formulation of generic conclusions and development of a manual. The project is intended to apply to situations in which sites with nuclear installations have been contaminated with radioactive materials as a result of the operation of these installations. The areas considered for remedial measures include contaminated land areas, rivers and sediments in rivers, lakes, and sea areas. Five contaminated European sites have been studied. Various remedial measures have been envisaged with respect to the optimisation of the protection of the populations being exposed to the radionuclides at the sites. Cost-benefit analysis and multi-attribute utility analysis have been applied for optimisation. Health, economic and social attributes have been included and weighting factors for the different attributes have been determined by the use of scaling constants. (au)

Methodology for Environmental Impact Assessment; Metodik foer miljoekonsekvensbedoemning

Energy Technology Data Exchange (ETDEWEB)

Malmlund, Anna (Structor Miljoebyraan Stockholm AB (Sweden))

2010-12-15

This report is an appendix to 'Environmental Impact Assessment Interim storage, encapsulation and disposal of spent nuclear fuel'. The appendix presents the methodology and criteria used in support investigations to conduct impact assessments.

ANL calculational methodologies for determining spent nuclear fuel source term

International Nuclear Information System (INIS)

McKnight, R. D.

2000-01-01

Over the last decade Argonne National Laboratory has developed reactor depletion methods and models to determine radionuclide inventories of irradiated EBR-II fuels. Predicted masses based on these calculational methodologies have been validated using available data from destructive measurements--first from measurements of lead EBR-II experimental test assemblies and later using data obtained from processing irradiated EBR-II fuel assemblies in the Fuel Conditioning Facility. Details of these generic methodologies are described herein. Validation results demonstrate these methods meet the FCF operations and material control and accountancy requirements

Development Methodology of a Cyber Security Risk Analysis and Assessment Tool for Digital I and C Systems in Nuclear Power Plant

International Nuclear Information System (INIS)

Cha, K. H.; Lee, C. K.; Song, J. G.; Lee, Y. J.; Kim, J. Y.; Lee, J. W.; Lee, D. Y.

2011-01-01

With the use of digital computers and communication networks the hot issues on cyber security were raised about 10 years ago. The scope of cyber security application has now been extended from the safety Instrumentation and Control (I and C) system to safety important systems, plant security system, and emergency preparedness system. Therefore, cyber security should be assessed and managed systematically throughout the development life cycle of I and C systems in order for their digital assets to be protected from cyber attacks. Fig. 1 shows the concept of a cyber security risk management of digital I and C systems in nuclear power plants (NPPs). A lot of cyber security risk assessment methods, techniques, and supported tools have been developed for Information Technology (IT) systems, but they have not been utilized widely for cyber security risk assessments of the digital I and C systems in NPPs. The main reason is a difference in goals between IT systems and nuclear I and C systems. Confidentiality is important in IT systems, but availability and integrity are important in nuclear I and C systems. Last year, it was started to develop a software tool to be specialized for the development process of nuclear I and C systems. This paper presents a development methodology of the Cyber Security Risk analysis and Assessment Tool (CSRAT) for the digital I and C systems in NPP

Development Methodology of a Cyber Security Risk Analysis and Assessment Tool for Digital I and C Systems in Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Cha, K. H.; Lee, C. K.; Song, J. G.; Lee, Y. J.; Kim, J. Y.; Lee, J. W.; Lee, D. Y. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2011-05-15

With the use of digital computers and communication networks the hot issues on cyber security were raised about 10 years ago. The scope of cyber security application has now been extended from the safety Instrumentation and Control (I and C) system to safety important systems, plant security system, and emergency preparedness system. Therefore, cyber security should be assessed and managed systematically throughout the development life cycle of I and C systems in order for their digital assets to be protected from cyber attacks. Fig. 1 shows the concept of a cyber security risk management of digital I and C systems in nuclear power plants (NPPs). A lot of cyber security risk assessment methods, techniques, and supported tools have been developed for Information Technology (IT) systems, but they have not been utilized widely for cyber security risk assessments of the digital I and C systems in NPPs. The main reason is a difference in goals between IT systems and nuclear I and C systems. Confidentiality is important in IT systems, but availability and integrity are important in nuclear I and C systems. Last year, it was started to develop a software tool to be specialized for the development process of nuclear I and C systems. This paper presents a development methodology of the Cyber Security Risk analysis and Assessment Tool (CSRAT) for the digital I and C systems in NPP

Methodology to evaluate the crack growth rate by stress corrosion cracking in dissimilar metals weld in simulated environment of PWR nuclear reactor

International Nuclear Information System (INIS)

Paula, Raphael G.; Figueiredo, Celia A.; Rabelo, Emerson G.

2013-01-01

Inconel alloys weld metal is widely used to join dissimilar metals in nuclear reactors applications. It was recently observed failures of weld components in plants, which have triggered an international effort to determine reliable data on the stress corrosion cracking behavior of this material in reactor environment. The objective of this work is to develop a methodology to determine the crack growth rate caused by stress corrosion in Inconel alloy 182, using the specimen (Compact Tensile) in simulated PWR environment. (author)

Use of cesium-137 methodology in the evaluation of superficial erosive processes

Directory of Open Access Journals (Sweden)

Avacir Casanova Andrello

2003-06-01

Full Text Available Superficial erosion is one of the main soil degradation agents and erosion rates estimations for different edaphicclimate conditions for the conventional models, as USLE and RUSLE, are expensive and time-consuming. The use of cesium-137 antrophogenic radionuclide is a new methodology that has been much studied and its application in the erosion soil evaluation has grown in countries as USA, UK, Australia and others. A brief narration of this methodology is being presented, as the development of the equations utilized for the erosion rates quantification through the cesium-137 measurements. Two watersheds studied in Brazil have shown that the cesium-137 methodology was practicable and coherent with the survey in field for applications in erosion studies.A erosão superficial é um dos principais agentes de degradação dos solos e estimativas das taxas de erosão para diferentes condições edafoclimáticas pelos modelos tradicionais como USLE, RUSLE, são onerosos e demorados. Uma metodologia que tem sido muito estudada e sua aplicação no estudo da erosão vem crescendo em países como EUA, Reino Unido, Austrália, e outros, é a do uso do radionuclídeo antropogênico césio-137. Um resumo da história desta metodologia é apresentado, assim como a evolução das equações utilizadas para quantificar as taxas de erosão através da medida do césio-137. Duas bacias estudadas no Brasil mostraram que a metodologia do césio-137 é viável e coerente com as observações em campo para aplicação no estudo da erosão.

Probabilistic risk assessment methodology for risk management and regulatory applications

International Nuclear Information System (INIS)

See Meng Wong; Kelly, D.L.; Riley, J.E.

1997-01-01

This paper discusses the development and potential applications of PRA methodology for risk management and regulatory applications in the U.S. nuclear industry. The new PRA methodology centers on the development of This paper discusses the time-dependent configuration risk profile for evaluating the effectiveness of operational risk management programs at U.S. nuclear power plants. Configuration-risk profiles have been used as risk-information tools for (1) a better understanding of the impact of daily operational activities on plant safety, and (2) proactive planning of operational activities to manage risk. Trial applications of the methodology were undertaken to demonstrate that configuration-risk profiles can be developed routinely, and can be useful for various industry and regulatory applications. Lessons learned include a better understanding of the issues and characteristics of PRA models available to industry, and identifying the attributes and pitfalls in the developement of risk profiles

Methodology to analysis of aging processes of containment spray system

International Nuclear Information System (INIS)

Borges, D. da Silva; Lava, D.D.; Moreira, M. de L.; Ferreira Guimarães, A.C.; Fernandes da Silva, L.

2015-01-01

This paper presents a contribution to the study of aging process of components in commercial plants of Pressurized Water Reactors (PWRs). The motivation for write this work emerged from the current perspective nuclear. Numerous nuclear power plants worldwide have an advanced operating time. This problem requires a process to ensure the confiability of the operative systems of these plants, because of this, it is necessary a methodologies capable of estimate the failure probability of the components and systems. In addition to the safety factors involved, such methodologies can to be used to search ways to ensure the extension of the life cycle of nuclear plants, which inevitably will pass by the decommissioning process after the operating time of 40 years. This process negatively affects the power generation, besides demanding an enormous investment for such. Thus, this paper aims to present modeling techniques and sensitivity analysis, which together can generate an estimate of how components, which are more sensitive to the aging process, will behave during the normal operation cycle of a nuclear power plant. (authors)

DEVELOPMENT OF A METHODOLOGY TO ASSESS PROLIFERATION RESISTANCE AND PHYSICAL PROTECTION FOR GENERATION IV SYSTEMS

International Nuclear Information System (INIS)

Nishimura, R.; Bari, R.; Peterson, P.; Roglans-Ribas, J.; Kalenchuk, D.

2004-01-01

Enhanced proliferation resistance and physical protection (PR and PP) is one of the technology goals for advanced nuclear concepts, such as Generation IV systems. Under the auspices of the Generation IV International Forum, the Office of Nuclear Energy, Science and Technology of the U.S. DOE, the Office of Nonproliferation Policy of the National Nuclear Security Administration, and participating organizations from six other countries are sponsoring an international working group to develop an evaluation methodology for PR and PP. This methodology will permit an objective PR and PP comparison between alternative nuclear systems (e.g., different reactor types or fuel cycles) and support design optimization to enhance robustness against proliferation, theft and sabotage. The paper summarizes the proposed assessment methodology including the assessment framework, measures used to express the PR and PP characteristics of the system, threat definition, system element and target identification, pathway identification and analysis, and estimation of the measures

Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Overview of the methodology. Vol. 1 of 9 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) including a CD-ROM comprising all volumes

International Nuclear Information System (INIS)

2008-11-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. This document follows the guidelines of the INPRO report 'Methodology for the assessment of innovative nuclear reactors and fuel cycles, Report of Phase 1B (first part) of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)', IAEA-TECDOC-1434 (2004), together with its previous report Guidance for the evaluation for innovative nuclear reactors and fuel cycles, Report of Phase 1A of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), IAEA-TECDOC-1362 (2003). This INPRO manual is comprised of an overview volume (laid out in this report), and eight additional volumes (available on a CD-ROM attached to the inside back cover of this report) covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of reactors (Volume 8), and safety of nuclear fuel cycle facilities (Volume 9). The overview volume sets out the philosophy of INPRO and a general discussion of the INPRO methodology. This overview volume discusses the relationship of INPRO with the UN concept of sustainability to demonstrate how the

Development of a methodology for safety classification on a non-reactor nuclear facility illustrated using an specific example; Entwicklung einer Methodik zur Sicherheitsklassifizierung fuer eine kerntechnische Anlage ohne Reaktor an einem spezifischen Beispiel

Energy Technology Data Exchange (ETDEWEB)

Scheuermann, F.; Lehradt, O.; Traichel, A. [NUKEM Technologies Engineering Services GmbH, Alzenau (Germany)

2015-07-01

To realize the safety of personnel and environment systems and components of nuclear facilities are classified according to their potential danger into safety classes. Based on this classification different demands on the manufacturing quality result. The objective of this work is to present the standardized method developed by NUKEM Technologies Engineering Services for the categorization into the safety classes restricted to Non-reactor nuclear facilities (NRNF). Exemplary the methodology is used on the complex Russian normative system (four safety classes). For NRNF only the lower two safety classes are relevant. The classification into the lowest safety class 4 is accordingly if the maximum resulting dose following from clean-up actions in case of incidents/accidents remains below 20 mSv and the volume activity restrictions of set in NRB-99/2009 are met. The methodology is illustrated using an example. In short the methodology consists of: - Determination of the working time to remove consequences of incidents, - Calculation of the dose resulting from direct radiation and due to inhalation during these works. The application of this methodology avoids over-conservative approaches. As a result some previously higher classified equipment can be classified into the lower safety class.

Holistic safety analysis for advanced nuclear power plants

International Nuclear Information System (INIS)

Alvarenga, M.A.B.; Guimaraes, A.C.F.

1992-01-01

This paper reviews the basic methodology of safety analysis used in the ANGRA-I and ANGRA-II nuclear power plants, its weaknesses, the problems with public acceptance of the risks, the future of the nuclear energy in Brazil, as well as recommends a new methodology, HOLISTIC SAFETY ANALYSIS, to be used both in the design and licensing phases, for advanced reactors. (author)

Uma ferramenta para planejamento de estudos para concursos

Directory of Open Access Journals (Sweden)

Leonardo Pimentel

2015-11-01

Full Text Available De acordo com a constituição brasileira, a única forma de se tornar um empregado do governo é passar em um concurso público. O exame de conhecimento do cargo é um dos componentes mais importantes de um concurso. Estudar para esse exame é uma tarefa que requer planejamento. Um meio de obter um bom planejamento é construir uma grade de horários que relacione as matérias a serem estudadas com os respectivos horários disponíveis para o estudo. Esse tipo de problema se assemelha bastante à gerência de projetos, em que se procura estabelecer a distribuição das atividades ao longo do tempo disponível. Assim, torna-se interessante explorar a dinâmica de estudos para concursos como um projeto. O presente trabalho apresenta a ferramenta de apoio ao estudos - Passe-me, baseada no ciclo PDCA (do inglês, Plan-Do-Check-Act. Por se tratar de uma ferramenta web, o tempo de resposta para produzir uma grade de estudos é fundamental. A ferramenta faz uso de algoritmo genético para calcular a grade de horários priorizando a velocidade de resposta. A ferramenta foi avaliada em diferentes cenários de uso e obteve desempenho satisfatório durante a produção da grade de estudos.

Country report: a methodology

International Nuclear Information System (INIS)

Colin, A.

2013-01-01

This paper describes a methodology which could be applicable to establish a country report. In the framework of nuclear non proliferation appraisal and IAEA safeguards implementation, it is important to be able to assess the potential existence of undeclared nuclear materials and activities as undeclared facilities in the country under review. In our views a country report should aim at providing detailed information on nuclear related activities for each country examined taken 'as a whole' such as nuclear development, scientific and technical capabilities, etc. In order to study a specific country, we need to know if there is already an operating nuclear civil programme or not. In the first case, we have to check carefully if it could divert nuclear material, if there are misused declared facilities or if they operate undeclared facilities and conduct undeclared activities aiming at manufacturing nuclear weapon. In the second case, we should pay attention to the development of a nuclear civil project. A country report is based on a wide span of information (most of the time coming from open sources but sometimes coming also from confidential or private ones). Therefore, it is important to carefully check the nature and the credibility (reliability?) of these sources through cross-check examination. Eventually, it is necessary to merge information from different sources and apply an expertise filter. We have at our disposal a lot of performing tools to help us to assess, understand and evaluate the situation (cartography, imagery, bibliometry, etc.). These tools allow us to offer the best conclusions as far as possible. The paper is followed by the slides of the presentation. (author)

A study on the operator's errors of commission (EOC) in accident scenarios of nuclear power plants: methodology development and application

International Nuclear Information System (INIS)

Kim, Jae Whan; Jung, Won Dea; Park, Jin Kyun; Kang, Da Il

2003-04-01

As the concern on the operator's inappropriate interventions, the so-called Errors Of Commission (EOCs), that can exacerbate the plant safety has been raised, much of interest in the identification and analysis of EOC events from the risk assessment perspective has been increased. Also, one of the items in need of improvement for the conventional PSA and HRA that consider only the system-demanding human actions is the inclusion of the operator's EOC events into the PSA model. In this study, we propose a methodology for identifying and analysing human errors of commission that might be occurring from the failures in situation assessment and decision making during accident progressions given an initiating event. In order to achieve this goal, the following research items have been performed: Firstly, we analysed the error causes or situations contributed to the occurrence of EOCs in several incidents/accidents of nuclear power plants. Secondly, limitations of the advanced HRAs in treating EOCs were reviewed, and a requirement for a new methodology for analysing EOCs was established. Thirdly, based on these accomplishments a methodology for identifying and analysing EOC events inducible from the failures in situation assessment and decision making was proposed and applied to all the accident sequences of YGN 3 and 4 NPP which resulted in the identification of about 10 EOC situations

Capacidade de Carga Turística: Um Estudo no Caminhos Rurais de Porto Alegre, RS

Directory of Open Access Journals (Sweden)

Juliane Magagnin Da Soller

2013-10-01

Full Text Available Nesse artigo, apresenta-se o contexto do turismo de base comunitária, além de breve histórico e discussão acerca do conceito e da metodologia da Capacidade de Carga Turística, assim como a adaptação da metodologia para estudo aqui relatado. Descreve-se o estudo realizado para determinar a Capacidade de Carga Turística, tendo por amostra as propriedades rurais partícipes da Associação Porto Alegre Rural (POA RURAL, mais especialmente do roteiro Caminhos Rurais de Porto Alegre, no estado do Rio Grande do Sul. Propôs-se adaptar a para o local a metodologia de cálculo de Capacidade de Carga Turística a partir de Cifuentes (1992; et al 1996, considerando suas particularidades, principalmente aquelas que dizem respeito a saúde e ao bem-estar das famílias que recebem os visitantes e aos impactos ambientais causados pelas construções de infraestrutura turística. A Capacidade de Carga Turística é uma metodologia desenvolvida para áreas preservadas de uso público. Assim, não costuma dar enfoque às questões referentes à comunidade local e aos resíduos gerados pelas instalações e pelos serviços prestados no Turismo.  Tourist Carrying Capacity: A study in the Caminhos Rurais de Porto Alegre, RS  - This paper presents the community based tourism and a brief history, concept and methodology of Tourist Carrying Capacity, and the adaptation of that methodology to the present case. The paper presents the study to determine the Tourist Carrying Capacity in rural proprieties that currently constitute the Porto Alegre Rural Association (RURAL POA, the tourist destination Caminhos Rurais de Porto Alegre, Rio Grande do Sul. The research proposes to adapt the methodology of Tourist Carrying Capacity from Cifuentes (1992, et al 1996, to the Caminhos Rurais, considering its particularities, especially those relate to health and well-being of families who receives visitors, and the environmental impacts caused by the construction of

Nuclear physics workshop

International Nuclear Information System (INIS)

1988-01-01

This Workshop in Nuclear Physics related to the TANDAR, took place in Buenos Aires in April from 23 to 26, 1987, with attendance of foreign scientists. There were presented four seminars and a lot of studies which deal with the following fields: Nuclear Physics at medium energies, Nuclear Structure, Nuclear Reactions, Nuclear Matter, Instrumentation and Methodology for Nuclear Spectroscopy, Classical Physics, Quantum Mechanics and Field Theory. It must be emphasized that the Electrostatic Accelerator TANDAR allows to work with heavy ions of high energy, that opens a new field of work in PIXE (particle induced X-ray emission). This powerful analytic technique makes it possiblethe analysis of nearly all the elements of the periodic table with the same accuracy. (M.E.L.) [es

Applications of nuclear safety probabilistic risk assessment to nuclear security for optimized risk mitigation

Energy Technology Data Exchange (ETDEWEB)

Donnelly, S.K.; Harvey, S.B. [Amec Foster Wheeler, Toronto, Ontario (Canada)

2016-06-15

Critical infrastructure assets such as nuclear power generating stations are potential targets for malevolent acts. Probabilistic methodologies can be applied to evaluate the real-time security risk based upon intelligence and threat levels. By employing this approach, the application of security forces and other protective measures can be optimized. Existing probabilistic safety analysis (PSA) methodologies and tools employed. in the nuclear industry can be adapted to security applications for this purpose. Existing PSA models can also be adapted and enhanced to consider total plant risk, due to nuclear safety risks as well as security risks. By creating a Probabilistic Security Model (PSM), safety and security practitioners can maximize the safety and security of the plant while minimizing the significant costs associated with security upgrades and security forces. (author)

Debates críticos: os Estudos de Segurança e o futuro dos Estudos da Paz e dos Conflitos 10.5102/uri.v11i2.2526

Directory of Open Access Journals (Sweden)

André Barrinha

2013-11-01

Full Text Available Irremediavelmente ligados pela proximidade dos respetivos objetos de estudo, Estudos de Segurança e Estudos da Paz e dos Conflitos constituíram-se e evoluíram ao longo da Guerra Fria como disciplinas antagónicas. Essa divisão operou-se sobretudo na Europa, onde Galtung e seus discípulos encaminharam o estudo das questões da guerra e da paz para uma agenda claramente normativa e crítica, enquanto o estudo das questões de segurança se centrava numa abordagem orientada para o policy-making. Como é defendido neste artigo, o final do conflito bipolar correspondeu, até certo ponto, a uma inversão de papéis, com os Estudos da Paz e dos Conflitos acomodados a um empirismo desprovido de normatividade e os Estudos de Segurança, pelo menos na Europa, a abrirem-se a novas abordagens de cariz mais crítico. É aqui sugerido que esta inversão contém, em si, importantes lições para os Estudos da Paz e da Segurança, nomeadamente sobre a centralidade da teoria na definição de uma nova agenda crítica que permita uma aproximação entre as duas disciplinas.

Current status and future directions of development of PR/PP evaluation methodology

International Nuclear Information System (INIS)

Kim, D. Y.; Kwon, E. H.; Kim, H. D.

2012-01-01

A mandatory design requirement for the introduction of generation IV nuclear energy systems (NESs) is defined as the characteristic of a nuclear energy system that impedes the diversion or undeclared production of nuclear material, or misuse of technology, by State in order to acquire nuclear weapons or other nuclear explosive devices. The same report also defines physical protection (PP) as the use of technical, administrative, and operational measures to prevent the theft of nuclear/radioactive material for the purpose of producing nuclear weapons, producing nuclear devices for nuclear terrorism, or using the facility or transportation system for radiological sabotage. Since the early 1970s right after the Indian nuclear test, the international community has recognized the limits of political and diplomatic means to prevent overt proliferation by states and looked for ways to incorporate technical features that are inherent in NESs. As a first step, active research has been conducted to develop a methodology to evaluate PR and PP components of NESs and has now been reduced to two main R and D streams: the Generation IV International Forum (GIF) and International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). (Currently, GIF and INPRO are leading the debate as major projects for PR and PP evaluation methods.) This paper presents an overview of the R and D accomplishments during the development of PR and PP evaluation methodology. It also suggests some directions for future research

Current status and future directions of development of PR/PP evaluation methodology

Energy Technology Data Exchange (ETDEWEB)

Kim, D. Y.; Kwon, E. H.; Kim, H. D. [KAERI, Daejeon (Korea, Republic of)

2012-10-15

A mandatory design requirement for the introduction of generation IV nuclear energy systems (NESs) is defined as the characteristic of a nuclear energy system that impedes the diversion or undeclared production of nuclear material, or misuse of technology, by State in order to acquire nuclear weapons or other nuclear explosive devices. The same report also defines physical protection (PP) as the use of technical, administrative, and operational measures to prevent the theft of nuclear/radioactive material for the purpose of producing nuclear weapons, producing nuclear devices for nuclear terrorism, or using the facility or transportation system for radiological sabotage. Since the early 1970s right after the Indian nuclear test, the international community has recognized the limits of political and diplomatic means to prevent overt proliferation by states and looked for ways to incorporate technical features that are inherent in NESs. As a first step, active research has been conducted to develop a methodology to evaluate PR and PP components of NESs and has now been reduced to two main R and D streams: the Generation IV International Forum (GIF) and International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). (Currently, GIF and INPRO are leading the debate as major projects for PR and PP evaluation methods.) This paper presents an overview of the R and D accomplishments during the development of PR and PP evaluation methodology. It also suggests some directions for future research.

Self-Assessment of Nuclear Security Culture in Facilities and Activities. Technical Guidance

International Nuclear Information System (INIS)

2017-01-01

The IAEA has developed a comprehensive methodology for evaluating nuclear security culture. When implemented by a State, this methodology will help to make nuclear security culture sustainable. It will also promote cooperation and the sharing of good practices related to nuclear security culture. This publication is the first guidance for assessing nuclear security culture and analysing its strengths and weaknesses within a facility or activity, or an organization. It reflects, within the context of assessment, the nuclear security culture model, principles and criteria set out in the Implementing Guide, IAEA Nuclear Security Series No. 7. This guidance will be useful for organizations and operating facilities in conducting the self-assessment of nuclear security culture by providing practical methods and tools. It will also help regulatory bodies and other competent authorities to understand the self-assessment methodology used by operators, encourage operators to start the self-assessment process or, if appropriate, conduct independent assessments of nuclear security culture.

Methodological proposal for identification and evaluation of environmental aspects and impacts of nuclear facilities of IPEN, Sao Paulo, SP, Brazil: a case study applied to the Nuclear Fuel Center

International Nuclear Information System (INIS)

Mattos, Luis Antonio Terribile de

2013-01-01

This work presents an application of Failure Mode Effect Analysis (FMEA) to the process of identification of environmental aspects and impacts as a part of implementation and maintenance of an Environmental Management System (EMS) in accordance with the NBR ISO 14001 standard. Also, it can contribute, as a complement, to the evaluation and improvement of safety of the installation focused. The study was applied to the Nuclear Fuel Center (CCN) of Nuclear and Energy Research Institute (IPEN), situated at the Campus of University of Sao Paulo, Brazil. The CCN facility has the objective of promoting scientific research and of producing nuclear fuel elements for the IEA-R1 Research Reactor. To identify the environmental aspects of the facility activities, products, and services, a systematic data collection was carried out by means of personal interviews, documents, reports and operation data records consulting. Furthermore, the processes and their interactions, failure modes, besides their causes and effects to the environment, were identified. As a result of a careful evaluation of these causes it was possible to identify and to classify the major potential environmental impacts, in order to set up and put in practice an Environmental Management System for the installation under study. The results have demonstrated the validity of the FMEA application to nuclear facility processes, identifying environmental aspects and impacts, whose controls are critical to achieve compliance with the environmental requirements of the Integrated Management System of IPEN. It was demonstrated that the methodology used in this work is a powerful management tool for resolving issues related to the conformity with applicable regulatory and legal requirements of the Brazilian Nuclear Energy Commission (CNEN) and the Brazilian Institute of Environment (IBAMA). (author)

Issues and insights of PRA methodology in nuclear and space applications

International Nuclear Information System (INIS)

Hsu, F.

2005-01-01

This paper presents some important issues and technical insights on the scope, conceptual framework, and essential elements of nuclear power plant Probabilistic Risk Assessments (PRAs) and that of the PRAs in general applications of the aerospace industry, such as the Space Shuttle PRA being conducted by NASA. Discussions are focused on various lessons learned in nuclear power plant PRA applications and their potential applicability to the PRAs in the aerospace and launch vehicle systems. Based on insights gained from PRA projects for nuclear power plants and from the current Space Shuttle PRA effort, the paper explores the commonalities and the differences between the conduct of the different PRAs and the key issues and risk insights derived from extensive modeling practices in both industries of nuclear and space. (author)

A Study on the Improvement of the INPRO Proliferation Resistance Assessment Methodology

International Nuclear Information System (INIS)

Ko, Won Il; Chang, Hong Lae

2010-07-01

Within the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), a methodology for evaluating proliferation resistance (INPRO PR methodology) has been developed. However, User Requirement (UR) 4 regarding multiplicity and robustness of barriers against proliferation ('innovative nuclear energy systems should incorporate multiple proliferation resistance features and measures') remains to be developed. Because the development of a methodology for evaluating User Requirement 4 requires an acquisition/diversion pathway analysis, a systematic approach was developed for the identification and analysis of pathways for the acquisition of weapons-useable nuclear material. This approach was applied to the DUPIC fuel cycle which identified several proliferation target materials and plausible acquisition/diversion pathways. Based on these results, proliferation strategies that a proliferant State could adopt for undeclared removal of nuclear material from the DUPIC fuel cycle have been developed based on the objectives of the proliferation of the State, the quality and quantity of the target material, the time required to acquire the material for the proliferation, and the technical and financial capabilities of the potential proliferant State. The diversion pathway for fresh DUPIC fuel was analyzed using the INPRO User Requirements 1, 2 and 3, and based on these results an assessment procedure and metrics for evaluating the multiplicity and robustness of proliferation barriers has been developed. In conclusion, the multiplicity and robustness of proliferation barriers is not a function of the number of barriers, or of their individual characteristics but is an integrated function of the whole. The robustness of proliferation barriers is measured by determining whether the safeguards goals can be met. The harmonization of INPRO PR methodology with the GIF PR and PP methodology was also considered. It was suggested that, as also confirmed by IAEA

Economic Analysis of Nuclear Energy

International Nuclear Information System (INIS)

Lee, Man Ki; Moon, K. H.; Kim, S. S.; Lim, C. Y.; Oh, K. B.

2006-12-01

It has been well recognized that securing economic viabilities along with technologies are very important elements in the successful implementation of nuclear R and D projects. The objective of the Project is to help nuclear energy to be utilized in an efficient way by analyzing major issues related with nuclear economics. The study covers following subjects: the role of nuclear in the future electric supply system, economic analysis of nuclear R and D project, contribution to the regional economy from nuclear power. In addition, the study introduces the international cooperation in the methodological area of efficient use of nuclear energy by surveying the international activities related with nuclear economics

Economic Analysis of Nuclear Energy

Energy Technology Data Exchange (ETDEWEB)

Lee, Man Ki; Moon, K. H.; Kim, S. S.; Lim, C. Y.; Oh, K. B

2006-12-15

It has been well recognized that securing economic viabilities along with technologies are very important elements in the successful implementation of nuclear R and D projects. The objective of the Project is to help nuclear energy to be utilized in an efficient way by analyzing major issues related with nuclear economics. The study covers following subjects: the role of nuclear in the future electric supply system, economic analysis of nuclear R and D project, contribution to the regional economy from nuclear power. In addition, the study introduces the international cooperation in the methodological area of efficient use of nuclear energy by surveying the international activities related with nuclear economics.

New linkage of P and T (Partitioning and Transmutation) treatment with methodology of geologic disposal. A possible breakthrough for nuclear technology in tomorrow

International Nuclear Information System (INIS)

Kitamoto, Asashi

1999-01-01

A possibility of a safe, reliable, transparent and economical high-level radioactive waste disposal method is proposed by combining partitioning of waste materials and transmutation of long-life nuclides with geologic disposal. The paper first discusses the environment surrounding nuclear energy and the conditions for social acceptance of nuclear energy. Then, the paper talks about the soundness of geologic disposal as most extensively studied method of radioactive waste, including environment, safety assessment model, unpredictable uncertainty, and macro image and its problems. Thirdly, the paper describes partitioning and transmutation, the latter being reduction of the lives of long-life nuclides by nuclear fission and conversion and the former being methodology to achieve it by rational means. Radionuclides are separated into six groups by three selection rules of transmutation and two selection rules of geologic disposal. The separation can greatly reduce the decay-heat and weight of the waste materials. The paper last explains the new concept of fuel cycle with some comments on important points in developing the new process (M.M.)

Nuclear forensics: a comprehensive model action plan for Nuclear Forensics Laboratory in India

International Nuclear Information System (INIS)

Deshmukh, A.V.; Nyati, S.; Fatangre, N.M.; Raghav, N.K.; Reddy, P.G.

2013-01-01

Nuclear forensic is an emerging and highly specialized discipline which deals with nuclear investigation and analysis of nuclear or radiological/radioactive materials. Nuclear Forensic analysis includes various methodology and analytical methods along with morphology, physical, chemical, elemental and isotopic analysis to characterize and develop nuclear database for the identification of unknown nuclear or radiological/radioactive material. The origin, source history, pathway and attribution of unknown radioactive/nuclear material is possible with certainty through Nuclear Forensics. Establishment of Nuclear Forensic Laboratory and development of expertise for nuclear investigation under one roof by developing the nuclear data base and laboratory network is need of the hour to ably address the problems of all the law enforcement and nuclear agencies. The present study provides insight in Nuclear Forensics and focuses on an urgent need for a comprehensive plan to set up Nuclear Forensic Laboratory across India. (author)

Pensamento, Teoria e Estudos Latino-americanos

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Jacques de Novion

2014-12-01

Full Text Available RESUMO O presente trabalho configura como artigo inicial do Dossiê Especial – Pensamento, Teoria e Estudos Latino-americanos, organizado conjuntamente por nós, a pedido da Revista de Estudos e Pesquisas sobre as Américas (CEPPAC, do Instituto de Ciências Sociais (ICS, da Universidade de Brasília (UnB. De forma breve, este artigo apresenta a importância alcançada pelo Pensamento, pela Teoria, e, sobre tudo, pelos Estudos Latino-americanos nas últimas décadas. Em seguida, o artigo apresenta os quatorze trabalhos e uma resenha que compõem este Dossiê, resultado da contribuição de diferentes pesquisadores de distintas localidades da região, organizados em três blocos: Ciências Sociais Latino-americanas, Pensamento e Estudos. PALAVRAS CHAVE: Ciências Sociais Latino-americanas; Pensamento Latino-americanos; Teoria Latino-americana; Estudos Latino-americanos. --- RESUMEN El presente trabajo configura como articulo inicial del Dossier Especial – Pensamiento Teoría y Estudios Latinoamericanos, organizado conjuntamente por nosotros, a pedido de la Revista de Estudos e Pesquisas sobre as Américas (CEPPAC, del Instituto de Ciências Sociais (ICS, de la Universidade de Brasília (UnB. De forma breve, este articulo presenta la importancia alcanzada por el Pensamiento, por la Teoría, y, sobre todo, por los Estudios Latinoamericanos en las últimas décadas. En seguida, el articulo presenta los catorce trabajos e una reseña que componen este Dossier, resultado de la contribución de diferentes investigadores de distintas localidades de la región, organizados en tres bloques: Ciencias Sociales Latinoamericanas, Pensamiento y Estudios. PALABRAS CLAVE: Ciencias Sociales Latinoamericanas; Pensamiento Latinoamericano; Teoría Latinoamericana; Estudios Latinoamericanos. --- ABSTRACT This paper is set up as the initial article of this Special Dossier - Thought, Theory and Latin American Studies, which we organized collectively, at the request

Calculating the cost of research and Development in nuclear and radiation safety

International Nuclear Information System (INIS)

Matsulevich, N.Je.; Nosovs'ka, A.A.

2010-01-01

Methodological support assessing the cost of research and development in the area of nuclear and radiation safety regulation is considered. Basic methodological recommendations for determining labor expenditures for research and development in nuclear and radiation safety are provided.

Study of a methodology of identifying important research problems by the PIRT process

International Nuclear Information System (INIS)

Aoki, Takayuki; Takagi, Toshiyuki; Urayama, Ryoichi; Komura, Ichiro; Furukawa, Takashi; Yusa, Noritaka

2014-01-01

In this paper, we propose a new methodology of identifying important research problems to be solved to improve the performance of some specific scientific technologies by the phenomena identification and ranking table (PIRT) process which has been used as a methodology for demonstrating the validity of the best estimate simulation codes in US Nuclear Regulatory Commission (USNRC) licensing of nuclear power plants. The new methodology makes it possible to identify important factors affecting the performance of the technologies from the viewpoint of the figure of merit and problems associated with them while it keeps the fundamental concepts of the original PIRT process. Also in this paper, we demonstrate the effectiveness of the new methodology by applying it to a task of extracting research problems for improving an inspection accuracy of ultrasonic testing or eddy current testing in the inspection of objects having cracks due to fatigue or stress corrosion cracking. (author)

Active methodologies and the nurturing of students’ autonomy As metodologias ativas e a promoção da autonomia de estudantes

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Neusi Aparecida Navas Berbel

2011-07-01

Full Text Available In this article, a literature-based reflection is registered, taking studies aimed at the nurturing of students’ autonomy and the potential of the pedagogic area with active methodologies as interface to achieve results in the same direction. The main objective of the text is to identify converging points between these two study areas and share them with educators and their professors, inciting critical thinking and possible experiments in order to increase the amount of data as well as discussions about the quality of teaching. Methodological alternatives are exemplified in their essential characteristics, emphasizing the problematization methodology within Maguerez´s Arch to guide students to autonomy learning as well as the studies that have been used.  Com este artigo, registra-se uma reflexão respaldada na literatura, tomando como interface estudos voltados para a promoção da autonomia de alunos e o potencial da área pedagógica, com o uso de metodologias ativas, para a obtenção de resultados na mesma direção. O objetivo maior da elaboração do texto é o de, ao identificar pontos de convergência entre essas duas linhas de estudos, compartilhá-los com educadores e seus formadores, provocando uma reflexão crítica e possíveis experimentos, no sentido de ampliar registros e discussões com vistas à qualidade do ensino. São exemplificadas alternativas metodológicas com suas características essenciais, com ênfase na metodologia da problematização com o arco de Maguerez, pelo potencial de levar alunos a aprendizagens para a autonomia, assim como estudos que a utilizaram. 

Risk Informed Approach for Nuclear Security Measures for Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide

International Nuclear Information System (INIS)

2015-01-01

This publication provides guidance to States for developing a risk informed approach and for conducting threat and risk assessments as the basis for the design and implementation of sustainable nuclear security systems and measures for prevention of, detection of, and response to criminal and intentional unauthorised acts involving nuclear and other radioactive material out of regulatory control. It describes concepts and methodologies for a risk informed approach, including identification and assessment of threats, targets, and potential consequences; threat and risk assessment methodologies, and the use of risk informed approaches as the basis for informing the development and implementation of nuclear security systems and measures. The publication is an Implementing Guide within the IAEA Nuclear Security Series and is intended for use by national policy makers, law enforcement agencies and experts from competent authorities and other relevant organizations involved in the establishment, implementation, maintenance or sustainability of nuclear security systems and measures related to nuclear and other radioactive material out of regulatory control

Methodology Declassification of Impacted Buildings. Application of Technology MARSSIM

International Nuclear Information System (INIS)

Vico, A.M.; Álvarez, A.; Gómez, J.M.; Quiñones, J.

2015-01-01

This work describes the material measurement methodology to assure the absence of contamination on impacted buildings due to processes related to the first part of the nuclear fuel cycle performed at the former Junta de Energía Nuclear, JEN, currently Centro de Investigaciones Energéticas Medioambientales y Tecnológicas, CIEMAT. The first part of the work encloses the identification and quantification of natural isotopes and its proportion in the studied surfaces through different analytical techniques. The experimental study has involved the proper equipment selection to carry out the field measurement and the characterization of uranium isotopes and their immediate descendants. According to European Union recommendations and specifications established by CSN (Consejo de Seguridad Nuclear), Spanish Regulatory authorities, for CIEMAT, the surface activity reference level have been established, which allow to decide if a surface can be classified as a conventional surface. In order to make decisions about the compliance with the established clearance criteria, MARSSIM methodology is applied by using the results obtained from field measurements (impacted and non impacted surfaces).

A human error analysis methodology, AGAPE-ET, for emergency tasks in nuclear power plants and its application

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Whan; Jung, Won Dea [Korea Atomic Energy Research Institute, Taejeon (Korea)

2002-03-01

This report presents a procedurised human reliability analysis (HRA) methodology, AGAPE-ET (A Guidance And Procedure for Human Error Analysis for Emergency Tasks), for both qualitative error analysis and quantification of human error probability (HEP) of emergency tasks in nuclear power plants. The AGAPE-ET is based on the simplified cognitive model. By each cognitive function, error causes or error-likely situations have been identified considering the characteristics of the performance of each cognitive function and influencing mechanism of PIFs on the cognitive function. Then, error analysis items have been determined from the identified error causes or error-likely situations to help the analysts cue or guide overall human error analysis. A human error analysis procedure based on the error analysis items is organised. The basic scheme for the quantification of HEP consists in the multiplication of the BHEP assigned by the error analysis item and the weight from the influencing factors decision tree (IFDT) constituted by cognitive function. The method can be characterised by the structured identification of the weak points of the task required to perform and the efficient analysis process that the analysts have only to carry out with the necessary cognitive functions. The report also presents the the application of AFAPE-ET to 31 nuclear emergency tasks and its results. 42 refs., 7 figs., 36 tabs. (Author)

An Improved Setpoint Determination Methodology for the Plant Protection System Considering Beyond Design Basis Events

International Nuclear Information System (INIS)

Lee, C.J.; Baik, K.I.; Baek, S.M.; Park, K.-M.; Lee, S.J.

2013-06-01

According to the nuclear regulations and industry standards, the trip setpoint and allowable value for the plant protection system have been determined by considering design basis events. In order to improve the safety of a nuclear power plant, an attempt has been made to develop an improved setpoint determination methodology for the plant protection system trip parameter considering not only a design basis event but also a beyond design basis event. The results of a quantitative evaluation performed for the Advanced Power Reactor 1400 nuclear power plant in Korea are presented herein. The results confirmed that the proposed methodology is able to improve the nuclear power plant's safety by determining more reasonable setpoints that can cover beyond design basis events. (authors)

Nuclear energy technology: theory and practice of commercial nuclear power

International Nuclear Information System (INIS)

Knief, R.A.

1982-01-01

Reviews Nuclear Energy Technology: Theory and Practice of Commercial Nuclear Power by Ronald Allen Knief, whose contents include an overview of the basic concepts of reactors and the nuclear fuel cycle; the basics of nuclear physics; reactor theory; heat removal; economics; current concerns at the front and back ends of the fuel cycle; design descriptions of domestic and foreign reactor systems; reactor safety and safeguards; Three Mile Island; and a brief overview of the basic concepts of nuclear fusion. Both magnetic and inertial confinement techniques are clearly outlined. Also reviews Nuclear Fuel Management by Harry W. Graves, Jr., consisting of introductory subjects (e.g. front end of fuel cycle); core physics methodology required for fuel depletion calculations; power capability evaluation (analyzes physical parameters that limit potential core power density); and fuel management topics (economics, loading arrangements and core operation strategies)

Study on the methodology for predicting and preventing errors to improve reliability of maintenance task in nuclear power plant

International Nuclear Information System (INIS)

Hanafusa, Hidemitsu; Iwaki, Toshio; Embrey, D.

2000-01-01

The objective of this study was to develop and effective methodology for predicting and preventing errors in nuclear power plant maintenance tasks. A method was established by which chief maintenance personnel can predict and reduce errors when reviewing the maintenance procedures and while referring to maintenance supporting systems and methods in other industries including aviation and chemical plant industries. The method involves the following seven steps: 1. Identification of maintenance tasks. 2. Specification of important tasks affecting safety. 3. Assessment of human errors occurring during important tasks. 4. Identification of Performance Degrading Factors. 5. Dividing important tasks into sub-tasks. 6. Extraction of errors using Predictive Human Error Analysis (PHEA). 7. Development of strategies for reducing errors and for recovering from errors. By way of a trial, this method was applied to the pump maintenance procedure in nuclear power plants. This method is believed to be capable of identifying the expected errors in important tasks and supporting the development of error reduction measures. By applying this method, the number of accidents resulting form human errors during maintenance can be reduced. Moreover, the maintenance support base using computers was developed. (author)

A methodology for assessing the effect of countermeasures against a nuclear accident using fuzzy set theory

International Nuclear Information System (INIS)

Han, M.H.; Hwang, W.T.; Kim, E.H.; Suh, K.S.; Choi, Y.G.

2000-01-01

A methodology for assessing the effectiveness of countermeasures against a nuclear accident has been designed by means of the concept of fuzzy set theory. In most of the existing countermeasure models in actions under radiological emergencies, the large variety of possible features is simplified by a number of rough assumptions. During this simplification procedure, a lot of information is lost which results in much uncertainty concerning the output of the countermeasure model. Furthermore, different assumptions should be used for different sites to consider the site specific conditions. In this study, the diversity of each variable related to protective action has been modelled by the linguistic variable. The effectiveness of sheltering and evacuation has been estimated using the proposed method. The potential advantage of the proposed method is in reducing the loss of information by incorporating the opinions of experts and by introducing the linguistic variables which represent the site specific conditions. (author)

Gender and Feminist Studies in Brazil: An Analysis of Revista Estudos Feministas

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Debora Diniz

2004-01-01

Full Text Available Revista Estudos Feministas (REF is one of the most important gender and feminist journals in Brazil. This article describes the author background and the subjects of the articles published in REF from 1992 to 2002. It was analysed the title, abstracts and keywords of the articles and the topics of the dossier, totalising 20 editorials, 105 articles and 20 dossiers. The classification and indexation of the material was guided by the controlled vocabulary of the “Tesauro para Estudos de Gênero e sobre Mulheres”, from Fundação Carlos Chagas. The results show that 95% of the authors are women, and that 54% are from Socials Sciences. There are articles in all thematic areas suggested by the Tesauro except on “Science and Technology” and “Education”, with a concentration on the following thematic areas: “Socials Sciences and Culture” (26%, “Language, Literature, Religion and Philosophy” (17% and “History and Social Transformation” (17%. The most discussed topics were in this order: sexual division of work, literary analysis, reproduction, and feminist theory. The analysis of REF suggests that gender and feminist research is a solitary activity, with a few number of articles published in partnership. There is a strong preference for qualitative methodologies (92%. This article aims to facilitate the process of identification some marginal areas in the gender and feminist studies in Brazil, empowering the educational and political work of the journal.

Sintomas depressivos em crianças: estudos com duas versões do CDI

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Miriam Cruvinel

Full Text Available O objetivo deste estudo foi identificar o número de crianças com sintomas depressivos em duas amostras de estudantes da cidade de campinas. Utilizou-se, no estudo 1, a versão brasileira do Inventário de Depressão Infantil (CDI e, no estudo 2, a versão original. Do estudo 1, realizado em 2001, participaram 169 estudantes de 3ª, 4ª e 5ª séries, e, do estudo 2, conduzido em 2005, 157 alunos de 3ª e 4ª séries. A prevalência de sintomatologia depressiva no estudo 1 foi de 3,55%, e, no estudo 2, de 17%. Em ambos os estudos, não foram encontradas diferenças significativas entre a média no CDI em relação às variáveis demográficas. conclui-se pela necessidade de mais estudos nacionais de prevalência no ensino fundamental e de esforços direcionados não só para a identificação dos fatores de risco, de proteção e das variáveis associadas mas também do refinamento dos instrumentos de medidas da depressão infantil.

The radiological safety in the use of nuclear technique -activities developed by Centro de Desenvolvimento da Tecnologia Nuclear - CNEN

International Nuclear Information System (INIS)

Wakabayashi, T.; Pereira, E.G.; Hirayama, T.

1991-01-01

The activities developed by the Centro de Desenvolvimento da Tecnologia Nuclear - CDTN supporting the users of nuclear techniques are described. The methodology used and future plans for the group are shown. (E.G.)

Scenario aggregation and analysis via Mean-Shift Methodology

International Nuclear Information System (INIS)

Mandelli, D.; Yilmaz, A.; Metzroth, K.; Aldemir, T.; Denning, R.

2010-01-01

A new generation of dynamic methodologies is being developed for nuclear reactor probabilistic risk assessment (PRA) which explicitly account for the time element in modeling the probabilistic system evolution and use numerical simulation tools to account for possible dependencies between failure events. The dynamic event tree (DET) approach is one of these methodologies. One challenge with dynamic PRA methodologies is the large amount of data they produce which may be difficult to analyze without appropriate software tools. The concept of 'data mining' is well known in the computer science community and several methodologies have been developed in order to extract useful information from a dataset with a large number of records. Using the dataset generated by the DET analysis of the reactor vessel auxiliary cooling system (RVACS) of an ABR-1000 for an aircraft crash recovery scenario and the Mean-Shift Methodology for data mining, it is shown how clusters of transients with common characteristics can be identified and classified. (authors)

Insights from implementation of a risk management methodology

International Nuclear Information System (INIS)

Mahn, J.A.; Germann, R.P.; Jacobs, R.R.

1992-01-01

In 1988, GPU Nuclear (GPUN) Corporation embarked on a research effort to identify or develop an appropriate methodology for proactively managing risks. The objective of this effort was to increase its ability to identify potential risks and to aid resource allocation decision making for risk control. Such a methodology was presented at a risk management symposium sponsored by GPUN in September of 1989. A pilot project based on this methodology has been conducted at GPUN to test and validate the elements of the methodology and to compare the results of its application with current corporate methods for guiding risk decision making. The pilot project also led to a follow-up policy-capturing study to elicit information about the various risk decision-making models of GPUN decision makers. The combination of these endeavors provided an opportunity to gain numerous insights with respect to understanding the real value of a risk management process, obtaining acceptance of and commitment to risk management and improving operational aspects of the methodology

Proceedings of 1. Regional Meeting on Nuclear Applications

International Nuclear Information System (INIS)

1990-01-01

This Meeting describes nuclear methods and techniques, emphasizing the development or adaptation of methodologies and instrumentations for national conditions. The works present here comprise several field of nuclear application as agronomy; industry; nuclear medicine; dosimetry; radiological protection and instrumentation. (C.G.C.)

Earnings management: estudo de caso do Banco Nacional Earnings management: Central Bank's case study

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César Medeiros Cupertino

2006-08-01

Full Text Available Este artigo promove um estudo de caso de uma das maiores instituições financeiras brasileiras da década de 90: o Banco Nacional S.A. (BNSA. O BNSA teve sua intervenção decretada pelo Banco Central do Brasil em 1995, após ser identificada a existência de ativos insolventes, originados por gerenciamento fraudulento dos lucros da entidade. O estudo visa investigar a gestão fraudulenta de lucros do Banco Nacional S.A., tanto nos seus aspectos motivadores, quanto em relação aos seus efeitos na composição patrimonial da entidade. A abordagem metodológica contempla: (i pesquisa explicativa, quanto aos objetivos do estudo; (ii estudo de caso, quanto aos procedimentos aplicados e (iii pesquisa qualitativa, quanto à abordagem do problema. Constatou-se que pode haver interesses inconciliáveis entre o agente e o principal, conforme disciplinado pela teoria da agência. O artigo, ainda, ressalta a importância do conhecimento dos dados financeiros na identificação dos fatos de interesse, dos ajustes pertinentes e da correta evidenciação da situação patrimonial da entidade.This paper features a case study of one of the main Brazilian banks of the 90's: Banco Nacional S/A (BNSA. The bank had its intervention decreed by Central Bank of Brazil in 1995, after the existence of insolvent assets, originated by fraudulent earnings management, were identified. The study aims to investigate the fraudulent earnings management of BNSA, both in motivational aspects and in relation of the effects in its balance sheet structure. The methodological approach of the study encompasses: (i an explanatory research, regarding the intended aim of the study; (ii case study, regarding the applied procedures; and (iii a qualitative research, regarding the approach to the problem. It was concluded that irreconcilable conflicts of interest might occur between the agent and the principal, according to the Agency Theory. The paper also emphasizes the importance of

estudo comparativo

OpenAIRE

Álvaro, Rocha

2005-01-01

O sítio web é um importante meio de comunicação e competitividade das universidades. Há diferentes razões para acreditar que os sítios possam variar entre universidades, mas contudo há certeza da existência de requisitos de qualidade comuns e transversais a todas. Este estudo visou avaliar, de forma quantitativa e objectiva, o cumprimento de requisitos de qualidade pelos sítios web das Universidades Portuguesas, com base nas características de alto nível da norma ISO 9126-1 que interessam aos...

Simplified methodology for Angra 1 containment analysis

International Nuclear Information System (INIS)

Neves Conti, T. das; Souza, A.L. de; Sabundjian, G.

1991-08-01

A simplified methodology of analysis was developed to simulate a Large Break Loss of Coolant Accident in the Angra 1 Nuclear Power Station. Using the RELAP5/MOD1, RELAP4/MOD5 and CONTEMPT-LT Codes, the time variation of pressure and temperature in the containment was analysed. The obtained data was compared with the Angra 1 Final Safety Analysis Report, and too those calculated by a Detailed Model. The results obtained by this new methodology such as the small computational time of simulation, were satisfactory when getting the preliminary evaluation of the Angra 1 global parameters. (author)

Methodology for the interactive graphic simulator construction

International Nuclear Information System (INIS)

Milian S, Idalmis; Rodriguez M, Lazaro; Lopez V, Miguel A.

1997-01-01

The PC-supported Interactive Graphic Simulators (IGS) have successfully been used for industrial training programs in many countries. This paper is intended to illustrate the general methodology applied by our research team for the construction of this kind of conceptual or small scale simulators. The information and tools available to achieve this goal are also described. The applicability of the present methodology was confirmed with the construction of a set of IGS for nuclear power plants operators training programs in Cuba. One of them, relating reactor kinetics, is shown and briefly described in this paper. (author). 11 refs., 3 figs

Status of the Gen-IV Proliferation Resistance and Physical Protection (PRPP) Evaluation Methodology

International Nuclear Information System (INIS)

Whitlock, J.; Bari, R.; Peterson, P.; Padoani, F.; Cojazzi, G.G.M.; Renda, G.; ); Cazalet, J.; Haas, E.; Hori, K.; Kawakubo, Y.; Chang, S.; Kim, H.; Kwon, E.-H.; Yoo, H.; Chebeskov, A.; Pshakin, G.; Pilat, J.F.; Therios, I.; Bertel, E.

2015-01-01

Methodologies have been developed within the Generation IV International Forum (GIF) to support the assessment and improvement of system performance in the areas safeguards, security, economics and safety. Of these four areas, safeguards and security are the subjects of the GIF working group on Proliferation Resistance and Physical Protection (PRPP). Since the PRPP methodology (now at Revision 6) represents a mature, generic, and comprehensive evaluation approach, and is freely available on the GIF public website, several non-GIF technical groups have chosen to utilize the PRPP methodology for their own goals. Indeed, the results of the evaluations performed with the methodology are intended for three types of generic users: system designers, programme policy makers, and external stakeholders. The PRPP Working Group developed the methodology through a series of demonstration and case studies. In addition, over the past few years various national and international groups have applied the methodology to inform nuclear energy system designs, as well as to support the development of approaches to advanced safeguards. A number of international workshops have also been held which have introduced the methodology to design groups and other stakeholders. In this paper we summarize the technical progress and accomplishments of the PRPP evaluation methodology, including applications outside GIF, and we outline the PRPP methodology's relationship with the IAEA's INPRO methodology. Current challenges with the efficient implementation of the methodology are outlined, along with our path forward for increasing its accessibility to a broader stakeholder audience - including supporting the next generation of skilled professionals in the nuclear non-proliferation field. (author)

A survey of dynamic methodologies for probabilistic safety assessment of nuclear power plants

International Nuclear Information System (INIS)

Aldemir, Tunc

2013-01-01

Highlights: ► Dynamic methodologies for probabilistic safety assessment (PSA) are surveyed. ► These methodologies overcome the limitations of the traditional approach to PSA. ► They are suitable for PSA using a best estimate plus uncertainty approach. ► They are highly computation intensive and produce very large number of scenarios. ► Use of scenario clustering can assist the analysis of the results. -- Abstract: Dynamic methodologies for probabilistic safety assessment (PSA) are defined as those which use a time-dependent phenomenological model of system evolution along with its stochastic behavior to account for possible dependencies between failure events. Over the past 30 years, numerous concerns have been raised in the literature regarding the capability of the traditional static modeling approaches such as the event-tree/fault-tree methodology to adequately account for the impact of process/hardware/software/firmware/human interactions on the stochastic system behavior. A survey of the types of dynamic PSA methodologies proposed to date is presented, as well as a brief summary of an example application for the PSA modeling of a digital feedwater control system of an operating pressurized water reactor. The use of dynamic methodologies for PSA modeling of passive components and phenomenological uncertainties are also discussed.

Effects of creatine supplementation on high-intensity intermittent exercise: discrepancies and methodological appraisals

Directory of Open Access Journals (Sweden)

Patrícia Chackur Brum

2008-04-01

Full Text Available After a brief review of the literature on the effects of creatine supplementation on high-intensity intermittent exercise performance, the main aim of this study was to discuss methodological differences between studies which could explain the discrepancies observed in the literature. The effects of creatine supplementation on high-intensity intermittent exercise performance have been investigated in depth. Although the results of much research demonstrates the effi cacy of this supplement, there is just as much evidence that does not support this ergogenic effect. The explanation for this divergence appears to be multifactorial, although it is always linked to methodological characteristics. Study design (crossover or parallel groups, individual variability of muscular creatine content, chronic high meat intake, sample size, exercise protocol characteristics (body weight dependence and time between series, and gender and age all differ between studies and are potentially the variables responsible, to differing extents, for the discrepancies observed in the literature. Studies involving young males, with parallel group design, adequate statistical power, control of the incorporation of creatine into muscles, food intake assessment and intermittent exercise protocols in which performance is independent of body weight and with rest-recovery intervals of 1 to 6 minutes, usually produce positive results. The many methodological factors which can contribute to divergence on the ergogenic effects of creatine should be considered in futures studies, as well as when prescribing creatine supplementation. Resumo Após breve revisão da literatura existente acerca dos efeitos da suplementação de creatina no rendimento em atividades intermitentes de alta intensidade, o objetivo principal dessa revisão foi discutir diferenças metodológicas dos estudos que possam explicar a divergência encontrada na literatura. Os efeitos da suplementação de creatina

Activities of Brazilian Nuclear Energy Commission in the field of nuclear power plant licesing

International Nuclear Information System (INIS)

Alves, R.N.

1986-01-01

The objectives, the procedures and the ways of implementation of measures aiming at safety use of nuclear energy are presented. The juridical aspects in the licensing area and the regulatory activities used by CNEN. The description of nuclear power plants and the methodology used in studies of environmental protection and radiation protection are presented [pt

Nuclear power and public policy

International Nuclear Information System (INIS)

Shrader-Frechette, K.S.

1980-01-01

The authors' purpose is to raise some of the social, political, and ethical issues which for so long have been ignored in making government assessments of nuclear power. In particular she asks whether current policy (governing admissible releases of radioactivity during electricity generation) is based on sound ethical premises. She argues that it is ethically reprehensible to generate long-lived nuclear wastes without knowing whether they can be safety stored. An ethical and methodological assessment of public policy is presented based on the presupposition that a core melt accident is improbable. It is then argued that the alleged cost-effectiveness of fission generated electricity is based on economical methodology which is both illogical and unethical. Finally, an outline of the sorts of policy-making procedures which ought to be followed in dealing with nuclear technology is given. (Auth.)

Estudo fitoquímico das partes aéreas de Aristolochia birostris Ducht. (Aristolochiaceae

Directory of Open Access Journals (Sweden)

Vanusia C. França

Full Text Available A família Aristolochiaceae apresenta entre seus constituintes terpenóides, alcalóides e lignóides. Papo-de-peru, jarrinha, mil-homens e capivara são nomes populares da espécie Aristolochia birostris, a qual é utilizada na medicina popular como antiofídica, sudorífica, anticatarral e abortiva. Um estudo fitoquímico anterior com as partes aéreas desta espécie reportou o isolamento de quatro terpenóides, um lignóide e uma antraquinona. Dando continuidade a esse estudo, este trabalho relata a identificação de 4 lignóides, sendo dois do tipo ariloxiarilpropânico (4-metilenodioxi-5,3',5' -trimetoxi-1'-alil-8.O.4'-neolignana e 3,4,5,3',5'-pentametoxi-1'-alil-8.O.4'-neolignana, um do tipo tetraidrofurano (grandisina e uma lignana dibenzilbutirolactônica [(--hinoquinina], além de vanilina. As estruturas foram estabelecidas através de métodos espectroscópicos de infravermelho e ressonância magnética nuclear uni e bidimensionais. Os lignóides foram avaliados quanto a atividade antimicrobiana frente a algumas cepas de bactérias, fungos e leveduras, entretanto foram inativos.

Study on GIF PR/PP evaluation methodology

Energy Technology Data Exchange (ETDEWEB)

Lee, B. H.; Kwon, E. H.; Kim, H. D. [KAERI, Daejeon (Korea, Republic of)

2012-10-15

Proliferation resistance (PR) and physical protection (PP) is one of the four technology goals of generation IV nuclear energy systems (NESs). The PR component of the goal focuses on providing strong assurance that generation IV NESs are the least desirable sources for the diversion or undeclared production of nuclear materials, whereas the PP portion of the goal ensures that generation IV NESs are robust against theft and sabotage. In 2002, the road map of the Generation IV International Forum (GIF) envisioned that the R and D program for PR and PP would have three areas: 1) safeguards and physical protection technology R and D for each GIF system; 2) formulation of PR and PP criteria and metrics; and 3) evaluation of the criteria and metrics. To cover these R and D items, the PR and PP Working Group (PRPPWG) was formed in late 2002 and has since developed a methodology for PR and PP evaluation. In a succession of revisions beginning in 2004, consensus was achieved amongst all participating GIF countries and related organizations (i.e., IAEA and EU), and Revision 6 of the methodology report was approved by GIF for open distribution in 2011. The paper describes in detail the methodology developed by the PRPPWG and discusses its applicability to the sodium-cooled fast reactor (SFR) fuel cycle with pyro processing currently under development in Korea.

Methodology for the Systematic Assessment of the Regulatory Competence Needs (SARCoN) for Regulatory Bodies of Nuclear Installations

International Nuclear Information System (INIS)

2015-03-01

A regulatory body’s competence is dependent, among other things, on the competence of its staff. A necessary, but not sufficient, condition for a regulatory body to be competent is that its staff can perform the tasks related to the functions of the regulatory body. In 2001, the IAEA published TECDOC 1254, Training the Staff of the Regulatory Body for Nuclear Facilities: A Competency Framework, which examines the manner in which the recognized regulatory functions of a nuclear regulatory body results in competence needs. Using the internationally recognized systematic approach to training, TECDOC 1254 provides a framework for regulatory bodies for managing training and developing, and maintaining the competence of its staff. It has been successfully used by many regulatory bodies all over the world, including States embarking on a nuclear power programme. The IAEA has also introduced a methodology and an assessment tool — Guidelines for Systematic Assessment of Regulatory Competence Needs (SARCoN) — which provides practical guidance on analysing the training and development needs of a regulatory body and, through a gap analysis, guidance on establishing competence needs and how to meet them. In 2013, the IAEA published Safety Reports Series No. 79, Managing Regulatory Body Competence, which provides generic guidance based on IAEA safety requirements in the development of a competence management system within a regulatory body’s integrated management system. An appendix in the Safety Report deals with the special case of building up the competence of regulatory bodies as part of the overall process of establishing an embarking State’s regulatory system. This publication provides guidance for the analysis of required and existing competences to identify those required by the regulatory body to perform its functions and therefore associated needs for acquiring competences. Hence, it is equally applicable to the needs of States embarking on nuclear power

An overview of performance assessment methodology

International Nuclear Information System (INIS)

Hongnian Jow

2010-01-01

The definition of performance assessment (PA) within the context of a geologic repository program is a post-closure safety assessment; a system analysis of hazards associated with the facility and the ability of the site and the design of the facility to provide for the safety functions. For the last few decades, PA methodology bas been developed and applied to different waste disposal programs around the world. PA has been used in the safety analyses for waste disposal repositories for low-level waste, intermediate level waste, and high-level waste including spent nuclear fuels. This paper provides an overview of the performance assessment methodology and gives examples of its applications for the Yucca Mountain Project. (authors)

Nuclear Energy Cost Data Base: A reference data base for nuclear and coal-fired powerplant power generation cost analysis

International Nuclear Information System (INIS)

Delene, J.G.; Bowers, H.I.

1986-12-01

A reference data base and standard methodology are needed for performing comparative nuclear and fossil power generation cost analyses for the Department of Energy, Office of Nuclear Energy. This report contains such a methodology together with reference assumptions and data to be used with the methodology. It is intended to provide basic guidelines or a starting point for analyses and to serve as a focal point in establishing parameters and methods to be used in economic comparisons of nuclear systems with alternatives. The data base is applicable for economic comparisons of new base load light-water reactors on either the current once-through cycle or self-generated recycle, high- and low-sulfur coal-fired plants, and oil- and natural gas-fired electric generating plants coming on line around the turn of the century. In additions to light-water reactors and fossil fuel-fired plants, preliminary cost information is also presented on liquid metal reactor plants. This report includes a data base containing proposed technical and economic assumptions to be used in analyses, discussions of recommended methodology to be used in calculating power generation costs, and a sample calculation for illustrative benchmark purposes

Nuclear Energy Cost Data Base: a reference data base for nuclear and coal-fired powerplant power generation cost analysis

International Nuclear Information System (INIS)

1985-06-01

A reference data base and standard methodology are needed for performing comparative nuclear and fossil power generation cost analyses for the Department of Energy, Office of Nuclear Energy. This report contains such a methodology together with reference assumptions and data to be used with the methodology. It is intended to provide basic guidelines or a starting point for analyses and to serve as a focal point in establishing parameters and methods to be used in economic comparisons of nuclear systems with alternatives. The data base is applicable for economic comparisons of new base load light-water reactors on either the current once-through cycle or self-generated recycle, high- and low-sulfur coal-fired plants, and oil- and natural gas-fired electric generating plants coming on line in the last decade of this century. In addition to light-water reactors and fossil fuel-fired plants, preliminary cost information is also presented on liquid metal reactor plants. This report includes a data base containing proposed technical and economic assumptions to be used in analyses, discussions of a recommended methodology to be used in calculating power generation costs, and a sample calculation for illustrative and benchmark purposes

Verification of Fault Tree Models with RBDGG Methodology

International Nuclear Information System (INIS)

Kim, Man Cheol

2010-01-01

Currently, fault tree analysis is widely used in the field of probabilistic safety assessment (PSA) of nuclear power plants (NPPs). To guarantee the correctness of fault tree models, which are usually manually constructed by analysts, a review by other analysts is widely used for verifying constructed fault tree models. Recently, an extension of the reliability block diagram was developed, which is named as RBDGG (reliability block diagram with general gates). The advantage of the RBDGG methodology is that the structure of a RBDGG model is very similar to the actual structure of the analyzed system and, therefore, the modeling of a system for a system reliability and unavailability analysis becomes very intuitive and easy. The main idea of the development of the RBDGG methodology is similar to that of the development of the RGGG (Reliability Graph with General Gates) methodology. The difference between the RBDGG methodology and RGGG methodology is that the RBDGG methodology focuses on the block failures while the RGGG methodology focuses on the connection line failures. But, it is also known that an RGGG model can be converted to an RBDGG model and vice versa. In this paper, a new method for the verification of the constructed fault tree models using the RBDGG methodology is proposed and demonstrated

Methodology for reliability based condition assessment

International Nuclear Information System (INIS)

Mori, Y.; Ellingwood, B.

1993-08-01

Structures in nuclear power plants may be exposed to aggressive environmental effects that cause their strength to decrease over an extended period of service. A major concern in evaluating the continued service for such structures is to ensure that in their current condition they are able to withstand future extreme load events during the intended service life with a level of reliability sufficient for public safety. This report describes a methodology to facilitate quantitative assessments of current and future structural reliability and performance of structures in nuclear power plants. This methodology takes into account the nature of past and future loads, and randomness in strength and in degradation resulting from environmental factors. An adaptive Monte Carlo simulation procedure is used to evaluate time-dependent system reliability. The time-dependent reliability is sensitive to the time-varying load characteristics and to the choice of initial strength and strength degradation models but not to correlation in component strengths within a system. Inspection/maintenance strategies are identified that minimize the expected future costs of keeping the failure probability of a structure at or below an established target failure probability during its anticipated service period

Ground acceleration in a nuclear power plant; Aceleracion del suelo en una central nuclear

Energy Technology Data Exchange (ETDEWEB)

Pena G, P.; Balcazar, M.; Vega R, E., E-mail: pablo.pena@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2015-09-15

A methodology that adopts the recommendations of international organizations for determining the ground acceleration at a nuclear power plant is outlined. Systematic presented here emphasizes the type of geological, geophysical and geotechnical studies in different areas of influence, culminating in assessments of Design Basis earthquake and the earthquake Operating Base. The methodology indicates that in regional areas where the site of the nuclear power plant is located, failures are identified in geological structures, and seismic histories of the region are documented. In the area of detail geophysical tools to generate effects to determine subsurface propagation velocities and spectra of the induced seismic waves are used. The mechanical analysis of drill cores allows estimating the efforts that generate and earthquake postulate. Studies show that the magnitude of the Fukushima earthquake, did not affect the integrity of nuclear power plants due to the rocky settlement found. (Author)

Nuclear Targeting Terms for Engineers and Scientists

Energy Technology Data Exchange (ETDEWEB)

St Ledger, John W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-02-01

The Department of Defense has a methodology for targeting nuclear weapons, and a jargon that is used to communicate between the analysts, planners, aircrews, and missile crews. The typical engineer or scientist in the Department of Energy may not have been exposed to the nuclear weapons targeting terms and methods. This report provides an introduction to the terms and methodologies used for nuclear targeting. Its purpose is to prepare engineers and scientists to participate in wargames, exercises, and discussions with the Department of Defense. Terms such as Circular Error Probable, probability of hit and damage, damage expectancy, and the physical vulnerability system are discussed. Methods for compounding damage from multiple weapons applied to one target are presented.

Training programs for the systems approach to nuclear security

International Nuclear Information System (INIS)

Ellis, D.

2005-01-01

Full text: In support of United States Government (USG) and International Atomic Energy Agency (IAEA) nuclear security programs, Sandia National Laboratories (SNL) has advocated and practiced a risk-based, systematic approach to nuclear security. The risk equation has been developed and implemented as the basis for a performance-based methodology for the design and evaluation of physical protection systems against a design basis threat (DBT) for theft and sabotage of nuclear and/or radiological materials. Integrated systems must include technology, people, and the man-machine interface. A critical aspect of the human element is training on the systems-approach for all the stakeholders in nuclear security. Current training courses and workshops have been very beneficial but are still rather limited in scope. SNL has developed two primary international classes - the international training course on the physical protection of nuclear facilities and materials, and the design basis threat methodology workshop. SNL is also completing the development of three new courses that will be offered and presented in the near term. They are vital area identification methodology focused on nuclear power plants to aid in their protection against radiological sabotage, insider threat analysis methodology and protection schemes, and security foundations for competent authority and facility operator stakeholders who are not security professionals. In the long term, we envision a comprehensive nuclear security curriculum that spans policy and technology, regulators and operators, introductory and expert levels, classroom and laboratory/field, and local and offsite training options. This training curriculum will be developed in concert with a nuclear security series of guidance documents that is expected to be forthcoming from the IAEA. It is important to note that while appropriate implementation of systems based on such training and documentation can improve the risk reduction, such a

New build methodology approach by Iberdrola Ingenieria y Construccion

International Nuclear Information System (INIS)

Zornoza Garcia-Andrade, Javier; Ignacio Diaz Prade, Jose; Martinez Gozalo, Ignacio; Merino Teillet, Alejandro

2014-01-01

Iberdrola Ingenieria y Construccion (hereinafter IEC) has developed a significant number of projects in several nuclear plants worldwide. Some of these plants are under operation, while others are under construction. Nowadays, IEC is actively participating in the design and construction of some safety and non-safety class systems of Flamanville 3, for EDF, has actively participated for OL4 (Finland) in one of the Nuclear Island (NI) proposal development covering for example complete NI supply chain and Licence Feasibility Study stages. Also, in the UK IEC has developed site characterization, licensing and heat sink analysis and supply chain development activities for NUGEN and is performing support engineering activities for HGNE for Wylfa. In addition, IEC performed the project for the refurbishment of Laguna Verde 1 and 2 turbine islands in Mexico, with a budget above 600 M USD. Nowadays, successful development of a new nuclear plant project in Europe, with stringent regulatory requirements for licensing and permitting which directly impact in the development of design, supply, construction and commissioning, requires successful integration of these processes by Regulatory Authority, Customer, Main Supplier and its entire supply chain. The soft integration of design, supply chain, construction and commissioning in the entire project development, will permit the application of advanced construction and engineering methodologies, as for example 'Open Top' construction or modular design, while minimizing regulatory delays. This integration represents one of the main challenges to minimize nuclear projects risk in order to successfully develop the project of a new plant considering a construction period of less than 5 year. Current paper provides a short description of proposed methodology and experiences of IEC, exposing several examples taken from actual experience in the design, supply and installation of systems in Flamanville 3 and from Olkiluoto 4

Radiation protection optimization using a knowledge based methodology