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Sample records for nuclear attraction integrals

  1. Integrating body movement into attractiveness research.

    Science.gov (United States)

    Fink, Bernhard; Weege, Bettina; Neave, Nick; Pham, Michael N; Shackelford, Todd K

    2015-01-01

    People judge attractiveness and make trait inferences from the physical appearance of others, and research reveals high agreement among observers making such judgments. Evolutionary psychologists have argued that interest in physical appearance and beauty reflects adaptations that motivate the search for desirable qualities in a potential partner. Although men more than women value the physical appearance of a partner, appearance universally affects social perception in both sexes. Most studies of attractiveness perceptions have focused on third party assessments of static representations of the face and body. Corroborating evidence suggests that body movement, such as dance, also conveys information about mate quality. Here we review evidence that dynamic cues (e.g., gait, dance) also influence perceptions of mate quality, including personality traits, strength, and overall attractiveness. We recommend that attractiveness research considers the informational value of body movement in addition to static cues, to present an integrated perspective on human social perception.

  2. Attracting and Retaining Talent in the Global Nuclear Industry

    International Nuclear Information System (INIS)

    Thomas, C.

    2014-01-01

    Recruiting 'non-nuclear' candidates: → Analysis of supply and demand; → Identify differentiators (longevity of project, interesting nature of work etc); → Online and offline recruitment (local and international) managed by recruiters; → Efficient and timely interview process; → Time and cost advantages through volume. Recruiting 'nuclear experts': → Detailed job descriptions written by nuclear experts; → People with strong nuclear knowledge involved throughout recruitment process (internal and external) - 'Excellence attracts exellence'; → 'Best Athlete' recruitment approach - passive and active candidates; → International search; → Higher investment in each case

  3. Evaluating the attractiveness of nuclear material for proliferation-resistance and nuclear security

    International Nuclear Information System (INIS)

    Choi, Jor-Shan; Ikegame, Kou; Kuno, Yusuke

    2011-01-01

    The attractiveness of nuclear material, defined as a function of the isotopic composition of the nuclear material in formulas expressing the material's intrinsic properties, is of considerably debate in recent developments of proliferation-resistance measures of a nuclear energy system. A reason for such debate arises from the fact that the concept of nuclear material attractiveness can be confusing because the desirability of a material for nuclear explosive use depends on many tangible and intangible factors including the intent and capability of the adversary. In addition, a material that is unattractive to an advanced nation (in the case of proliferation) may be very attractive to a terrorist (in the case of physical protection and nuclear security). Hence, the concept of 'Nuclear Material Attractiveness' for different nuclear materials must be considered in the context of safeguards and security. The development of a ranking scheme on the attractiveness of nuclear materials could be a useful concept to start-off the strategies for safeguards and security on a new footing (i.e., why and how nuclear material is attractive, and what are the quantifiable basis). Japan may benefit from such concept regarding the attractiveness of nuclear materials when recovering nuclear materials from the damaged cores in Fukushima because safety, security, and safeguards (3S) would be a prominent consideration for the recovery operation, and it would be the first time such operation is performed in a non-nuclear weapons state. (author)

  4. Nuclear material attractiveness: an assessment of used-fuel assemblies

    International Nuclear Information System (INIS)

    Bathke, Charles Gary; Edelman, Paul G.; Hase, Kevin R.; Ebbinghaus, Bartley B.; Sleaford, Brad W.; Robel, Martin; Collins, B.A.; Prichard, Andrew W.; Smith, B Brian W.

    2011-01-01

    This paper examines the material attractiveness of used-fuel assemblies in a hypothetical scenario in which terrorists steal one or more assemblies in order to use the special nuclear materials (SNM) within an assembly in a nuclear explosive device. For assessing material attractiveness, this paper uses the Figure of Merit (FOM) that was used in earlier studies to examine the attractiveness of the SNM associated with the reprocessing of used light water reactor (LWR) fuel by various reprocessing schemes. However, for a theft scenario the mass used in the Acquisition Factor of the FOM is the mass of the stolen object conta ining SNM ; whereas the mass used for analyzing the material attractiveness of the products of various reprocessing schemes in the earlier studies was a fraction of the bare critical mass in recognition that a successful proliferator must avoid a criticality accident. This paper will indicate how long after discharge the radiation emanating from a cooling assembly is no longer self-protecting. Additionally, this paper will give the time scale for the SNM within the assembly to become more attractive. These studies were performed at the request of the United States Department of Energy (DOE), and are based on the calculation of ''attractiveness levels'' that has been couched in terms chosen for consistency with those normally used for nuclear materials in DOE nuclear facilities. The methodology and key findings will be presented. Additionally, this paper discusses how the results presented herein impact the application of safeguards and the securitization of SNM, and how they could be used to help inform policy makers.

  5. Integrated Nuclear Recycle Plant

    International Nuclear Information System (INIS)

    Patodi, Anuj; Parashar, Abhishek; Samadhiya, Akshay K.; Ray, Saheli; Dey, Mitun; Singh, K.K.

    2017-01-01

    Nuclear Recycle Board (NRB), Tarapur proposes to set up an 'Integrated Nuclear Recycle Plant' at Tarapur. This will be located in the premises of BARC facilities. The project location is at coastal town of Tarapur, 130 Km north of Mumbai. Project area cover of INRP is around 80 hectares. The plant will be designed to process spent fuel received from Pressurized Heavy Water Reactors (PHWRs). This is the first large scale integrated plant of the country. INRP will process spent fuel obtained from indigenous nuclear power plants and perform left over nuclear waste disposal

  6. Microbial and viral chitinases: Attractive biopesticides for integrated pest management.

    Science.gov (United States)

    Berini, Francesca; Katz, Chen; Gruzdev, Nady; Casartelli, Morena; Tettamanti, Gianluca; Marinelli, Flavia

    2018-01-04

    The negative impact of the massive use of synthetic pesticides on the environment and on human health has stimulated the search for environment-friendly practices for controlling plant diseases and pests. Among them, biocontrol, which relies on using beneficial organisms or their products (bioactive molecules and/or hydrolytic enzymes), holds the greatest promise and is considered a pillar of integrated pest management. Chitinases are particularly attractive to this purpose since they have fungicidal, insecticidal, and nematicidal activities. Here, current knowledge on the biopesticidal action of microbial and viral chitinases is reviewed, together with a critical analysis of their future development as biopesticides. Copyright © 2018 Elsevier Inc. All rights reserved.

  7. The role of women in nuclear - attracting public participation in regulatory decision-making process

    Science.gov (United States)

    Mohamad Jais, Azlina; Hassan, Najwa

    2018-01-01

    Public participation is vital in demonstrating transparency and enhancing effectiveness of a nuclear regulatory process. As such, it is necessary for nuclear practitioners to involve the public in key nuclear delivery milestones. This paper specifically discusses challenges faced in attracting public participation throughout the nuclear regulatory decision-making process, and highlights the roles of women in nuclear (WiN) in initiating the said public discourse.

  8. Attracting students to nuclear careers: INPO educational assistance program

    International Nuclear Information System (INIS)

    Dunkle, M.

    1981-01-01

    The utility industry is responding to a manpower shortage of 2000 at nuclear plants with a concerted analysis of regional training centers and educational assistance programs through the Institute of Nuclear Power Operations (INPO). University support and cooperation are generally strong. The INPO program includes undergraduate- and graduate-level scholarships and fellowships

  9. Nuclear Munitions and Missile Maintenance Officer Attraction and Retention

    Science.gov (United States)

    2009-03-24

    longer provide motivation . Job security, high pay, and good benefits fit in Maslow’s second lowest level, security or safety needs. Frederick Herzberg ...themselves about other subjects, such as nuclear deterrence theory However, a some of Cohen’s other seven motivators also yield insights relative to the 21M...GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR( S ) 5d. PROJECT NUMBER 5e. TASK NUMBER 5f. WORK UNIT NUMBER 7. PERFORMING ORGANIZATION NAME( S ) AND

  10. Accurate collision integrals for the attractive static screened Coulomb potential with application to electrical conductivity

    International Nuclear Information System (INIS)

    Macdonald, J.

    1991-01-01

    The results of accurate calculations of collision integrals for the attractive static screened Coulomb potential are presented. To obtain high accuracy with minimal computational cost, the integrals are evaluated by a quadrature method based on the Whittaker cardinal function. The collision integrals for the attractive potential are needed for calculation of the electrical conductivity of a dense fully or partially ionized plasma, and the results presented here are appropriate for the conditions in the nondegenerate envelopes of white dwarf stars. 25 refs

  11. The Application of materials attractiveness in a graded approach to nuclear materials security

    International Nuclear Information System (INIS)

    Ebbinghaus, B.; Bathke, C.; Dalton, D.; Murphy, J.

    2013-01-01

    The threat from terrorist groups has recently received greater attention. In this paper, material quantity and material attractiveness are addressed through the lens of a minimum security strategy needed to prevent the construction of a nuclear explosive device (NED) by an adversary. Nuclear materials are placed into specific security categories (3 or 4 categories) , which define a number of security requirements to protect the material. Materials attractiveness can be divided into four attractiveness levels, High, Medium, Low, and Very Low that correspond to the utility of the material to the adversary and to a minimum security strategy that is necessary to adequately protect the nuclear material. We propose a graded approach to materials attractiveness that recognizes for instance substantial differences in attractiveness between pure reactor-grade Pu oxide (High attractiveness) and fresh MOX fuel (Low attractiveness). In either case, an adversary's acquisition of a Category I quantity of plutonium would be a major incident, but the acquisition of Pu oxide by the adversary would be substantially worse than the acquisition of fresh MOX fuel because of the substantial differences in the time and complexity required of the adversary to process the material and fashion it into a NED

  12. The Application of materials attractiveness in a graded approach to nuclear materials security

    Energy Technology Data Exchange (ETDEWEB)

    Ebbinghaus, B. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94551 (United States); Bathke, C. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States); Dalton, D.; Murphy, J. [National Nuclear Security Administration, US Department of Energy, 1000 Independent Ave., S. W. Washington, DC 20585 (United States)

    2013-07-01

    The threat from terrorist groups has recently received greater attention. In this paper, material quantity and material attractiveness are addressed through the lens of a minimum security strategy needed to prevent the construction of a nuclear explosive device (NED) by an adversary. Nuclear materials are placed into specific security categories (3 or 4 categories) , which define a number of security requirements to protect the material. Materials attractiveness can be divided into four attractiveness levels, High, Medium, Low, and Very Low that correspond to the utility of the material to the adversary and to a minimum security strategy that is necessary to adequately protect the nuclear material. We propose a graded approach to materials attractiveness that recognizes for instance substantial differences in attractiveness between pure reactor-grade Pu oxide (High attractiveness) and fresh MOX fuel (Low attractiveness). In either case, an adversary's acquisition of a Category I quantity of plutonium would be a major incident, but the acquisition of Pu oxide by the adversary would be substantially worse than the acquisition of fresh MOX fuel because of the substantial differences in the time and complexity required of the adversary to process the material and fashion it into a NED.

  13. The application of a figure of merit for nuclear explosive utility as a metric for material attractiveness in a nuclear material theft scenario

    International Nuclear Information System (INIS)

    King, Wayne E.; Bradley, Keith; Jones, Edwin D.; Kramer, Kevin J.; Latkowski, Jeffery F.; Robel, Martin; Sleaford, Brad W.

    2010-01-01

    Effective integration of nonproliferation management into the design process is key to the broad deployment of advanced nuclear energy systems, and is an explicit goal of the Laser Inertial Fusion Energy (LIFE) project at Lawrence Livermore National Laboratory. The nuclear explosives utility of a nuclear material to a state (proliferator) or sub-state (terrorist) is a critical factor to be assessed and is one aspect of material attractiveness. In this work, we approached nuclear explosives utility through the calculation of a 'figure of merit' (FOM) that has recently been developed to capture the relative viability and difficulty of constructing nuclear explosives starting from various nuclear material forms and compositions. We discuss the integration of the figure of merit into an assessment of a nuclear material theft scenario and its use in the assessment. This paper demonstrates that material attractiveness is a multidimensional concept that embodies more than the FOM. It also seeks to propose that other attributes may be able to be quantified through analogous FOMs (e.g., transformation) and that, with quantification, aggregation may be possible using concepts from the risk community.

  14. The application of a figure of merit for nuclear explosive utility as a metric for material attractiveness in a nuclear material theft scenario

    Energy Technology Data Exchange (ETDEWEB)

    King, Wayne E., E-mail: weking@llnl.go [Physical and Life Sciences Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Bradley, Keith [Global Security Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Jones, Edwin D. [Physical and Life Sciences Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Kramer, Kevin J.; Latkowski, Jeffery F. [Engineering Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Robel, Martin [Physical and Life Sciences Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Sleaford, Brad W. [Engineering Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States)

    2010-11-15

    Effective integration of nonproliferation management into the design process is key to the broad deployment of advanced nuclear energy systems, and is an explicit goal of the Laser Inertial Fusion Energy (LIFE) project at Lawrence Livermore National Laboratory. The nuclear explosives utility of a nuclear material to a state (proliferator) or sub-state (terrorist) is a critical factor to be assessed and is one aspect of material attractiveness. In this work, we approached nuclear explosives utility through the calculation of a 'figure of merit' (FOM) that has recently been developed to capture the relative viability and difficulty of constructing nuclear explosives starting from various nuclear material forms and compositions. We discuss the integration of the figure of merit into an assessment of a nuclear material theft scenario and its use in the assessment. This paper demonstrates that material attractiveness is a multidimensional concept that embodies more than the FOM. It also seeks to propose that other attributes may be able to be quantified through analogous FOMs (e.g., transformation) and that, with quantification, aggregation may be possible using concepts from the risk community.

  15. Integral nuclear fuel element assembly

    International Nuclear Information System (INIS)

    Schluderberg, D. C.

    1985-01-01

    An integral nuclear fuel element assembly utilizes longitudinally finned fuel pins. The continuous or interrupted fins of the fuel pins are brazed to fins of juxtaposed fuel pins or directly to the juxtaposed fuel pins or both. The integrally brazed fuel assembly is designed to satisfy the thermal and hydraulic requirements of a fuel assembly lattice having moderator to fuel atom ratios required to achieve high conversion and breeding ratios

  16. The Attractiveness of Materials in Advanced Nuclear Fuel Cycles for Various Proliferation and Theft Scenarios

    International Nuclear Information System (INIS)

    Bathke, C.G.; Wallace, R.K.; Ireland, J.R.; Johnson, M.W.; Hase, Kevin R.; Jarvinen, G.D.; Ebbinghaus, B.B.; Sleaford, Brad W.; Bradley, Keith S.; Collins, Brian A.; Smith, Brian W.; Prichard, Andrew W.

    2010-01-01

    This paper is an extension to earlier studies that examined the attractiveness of materials mixtures containing special nuclear materials (SNM) and alternate nuclear materials (ANM) associated with the PUREX, UREX, COEX, THOREX, and PYROX reprocessing schemes. This study extends the figure of merit (FOM) for evaluating attractiveness to cover a broad range of proliferant state and sub-national group capabilities. The primary conclusion of this study is that all fissile material needs to be rigorously safeguarded to detect diversion by a state and provided the highest levels of physical protection to prevent theft by sub-national groups; no 'silver bullet' has been found that will permit the relaxation of current international safeguards or national physical security protection levels. This series of studies has been performed at the request of the United States Department of Energy (DOE) and is based on the calculation of 'attractiveness levels' that are expressed in terms consistent with, but normally reserved for nuclear materials in DOE nuclear facilities. The expanded methodology and updated findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security are discussed.

  17. Nuclear material attractiveness: an assessment of material associated with a closed fuel cycle

    International Nuclear Information System (INIS)

    Bathke, C.G.; Wallace, R.K.; Hase, K.R.; Jarvinen, G.D.; Ireland, J.R.; Johnson, M.W.; Ebbinghaus, B.B.; Sleaford, B.W.; Robel, M.; Bradley, K.S.; Collins, B.A.; Prichard, A.W.; Smith, B.W.

    2010-01-01

    This paper examines the attractiveness of materials mixtures containing special nuclear materials (SNM) associated with the various processing steps required for a closed fuel cycle. This paper combines the results from earlier studies that examined the attractiveness of SNM associated with the processing of spent light water reactor (LWR) fuel by various reprocessing schemes and the recycle of plutonium as a mixed oxide (MOX) fuel in LWR with new results for the final, repeated burning of SNM in fast-spectrum reactors: fast reactors and accelerator driven systems (ADS). The results of this paper suggest that all reprocessing products evaluated so far need to be rigorously safeguarded and provided moderate to high levels of physical protection. These studies were performed at the request of the United States Department of Energy (DOE), and are based on the calculation of 'attractiveness levels' that has been couched in terms chosen for consistency with those normally used for nuclear materials in DOE nuclear facilities. The methodology and key findings will be presented. Additionally, how these attractiveness levels relate to proliferation resistance (e.g. by increasing impediments to the diversion, theft, or undeclared production of SNM for the purpose of acquiring a nuclear weapon), and how they could be used to help inform policy makers, will be discussed. (authors)

  18. Further assessments of the attractiveness of materials in advanced nuclear fuel cycles from a safeguards perspective

    International Nuclear Information System (INIS)

    Bathke, Charles G.; Jarvinen, Gordon D.; Wallace, Richard K.; Ireland, John R.; Johnson, M.W.; Sleaford, Brad W.; Ebbinghaus, Bartley B.; Bradley, Keith S.; Collins, Brian A.; Smith, Brian W.; Prichard, Andrew W.

    2010-01-01

    This paper summarises the results of an extension to an earlier study [1] that examined the attractiveness of materials mixtures containing special nuclear materials (SNM) associated with the Purex, Urex+ and COEX reprocessing schemes. This study focuses on the materials associated with the Urex, COEX, Thorex and PYROX reprocessing schemes. This study also examines what is required to render plutonium as 'unattractive.' Furthermore, combining the results of this study with those from the earlier study permits a comparison of the uranium- and thorium-based fuel cycles on the basis of the attractiveness of the SNM associated with each fuel cycle. Both studies were performed at the request of the United States Department of Energy (DOE), and are based on the calculation of 'attractiveness levels' that has been couched in terms chosen for consistency with those normally used for nuclear materials in DOE nuclear facilities [2]. The methodology and key findings will be presented. Additionally, how these attractiveness levels relate to proliferation resistance (e.g. by increasing impediments to the diversion, theft, undeclared production of SNM for the purpose of acquiring a nuclear weapon), and how they could be used to help inform policy makers, will be discussed. (authors)

  19. The attractiveness of materials in advanced nuclear fuel cycles for various proliferation and theft scenarios

    International Nuclear Information System (INIS)

    Bathke, Charles G.; Wallace, Richard K.; Ireland, John R.; Johnson, M.W.; Hase, Kevin R.; Jarvinen, Gordon D.; Ebbinghaus, Bartley B.; Sleaford, Brad A.; Bradley, Keith S.; Collins, Brian W.; Smith, Brian W.; Prichard, Andrew W.

    2009-01-01

    This paper is an extension to earlier studies that examined the attractiveness of materials mixtures containing special nuclear materials (SNM) and alternate nuclear materials (ANM) associated with the PUREX, UREX, COEX, THOREX, and PYROX reprocessing schemes. This study extends the figure of merit (FOM) for evaluating attractiveness to cover a broad range of proliferant state and sub-national group capabilities. The primary conclusion of this study is that all fissile material needs to be rigorously safeguarded to detect diversion by a state and provided the highest levels of physical protection to prevent theft by sub-national groups; no 'silver bullet' has been found that will permit the relaxation of current international safeguards or national physical security protection levels. This series of studies has been performed at the request of the United States Department of Energy (DOE) and is based on the calculation of 'attractiveness levels' that are expressed in terms consistent with, but normally reserved for nuclear materials in DOE nuclear facilities. The expanded methodology and updated findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security are discussed.

  20. Nuclear Material Attractiveness: An Assessment Of Material Associated With A Closed Fuel Cycle

    International Nuclear Information System (INIS)

    Bathke, C.G.; Ebbinghaus, B.; Sleaford, Brad W.; Wallace, R.K.; Collins, Brian A.; Hase, Kevin R.; Robel, Martin; Jarvinen, G.D.; Bradley, Keith S.; Ireland, J.R.; Johnson, M.W.; Prichard, Andrew W.; Smith, Brian W.

    2010-01-01

    This paper examines the attractiveness of materials mixtures containing special nuclear materials (SNM) associated with the various processing steps required for a closed fuel cycle. This paper combines the results from earlier studies that examined the attractiveness of SNM associated with the processing of spent light water reactor (LWR) fuel by various reprocessing schemes and the recycle of plutonium as a mixed oxide (MOX) fuel in LWR with new results for the final, repeated burning of SNM in fast-spectrum reactors: fast reactors and accelerator driven systems (ADS). The results of this paper suggest that all reprocessing products evaluated so far need to be rigorously safeguarded and provided moderate to high levels of physical protection. These studies were performed at the request of the United States Department of Energy (DOE), and are based on the calculation of 'attractiveness levels' that has been couched in terms chosen for consistency with those normally used for nuclear materials in DOE nuclear facilities. The methodology and key findings will be presented. Additionally, how these attractiveness levels relate to proliferation resistance (e.g. by increasing impediments to the diversion, theft, or undeclared production of SNM for the purpose of acquiring a nuclear weapon), and how they could be used to help inform policy makers, will be discussed.

  1. Nuclear astrophysics lessons from INTEGRAL.

    Science.gov (United States)

    Diehl, Roland

    2013-02-01

    Measurements of high-energy photons from cosmic sources of nuclear radiation through ESA's INTEGRAL mission have advanced our knowledge: new data with high spectral resolution showed that characteristic gamma-ray lines from radioactive decays occur throughout the Galaxy in its interstellar medium. Although the number of detected sources and often the significance of the astrophysical results remain modest, conclusions derived from this unique astronomical window of radiation originating from nuclear processes are important, complementing the widely-employed atomic-line based spectroscopy. We review the results and insights obtained in the past decade from gamma-ray line measurements of cosmic sources in the context of their astrophysical questions.

  2. Nuclear Plant Integrated Outage Management

    International Nuclear Information System (INIS)

    Gerstberger, C. R.; Coulehan, R. J.; Tench, W. A.

    1992-01-01

    This paper is a discussion of an emerging concept for improving nuclear plant outage performance - integrated outage management. The paper begins with an explanation of what the concept encompasses, including a scope definition of the service and descriptions of the organization structure, various team functions, and vendor/customer relationships. The evolvement of traditional base scope services to the integrated outage concept is addressed and includes discussions on changing customer needs, shared risks, and a partnership approach to outages. Experiences with concept implementation from a single service in 1984 to the current volume of integrated outage management presented in this paper. We at Westinghouse believe that the operators of nuclear power plants will continue to be aggressively challenged in the next decade to improve the operating and financial performance of their units. More and more customers in the U. S. are looking towards integrated outage as the way to meet these challenges of the 1990s, an arrangement that is best implemented through a long-term partnering with a single-source supplier of high quality nuclear and turbine generator outage services. This availability, and other important parameters

  3. Attract, Retain and Develop New Nuclear Talents Beyond Academic Curricula: the ENEN+ project

    International Nuclear Information System (INIS)

    Cizelj, Leon

    2017-01-01

    The European Nuclear Education Network, ENEN Association, is an Association established as an international non-profit association under the French law of 1901, on 22 September 2003, as a result of the “ENEN project” funded by the European Commission. Objectives of ENEN: The main objective is the preservation and further development of expertise in the nuclear fields by higher Education & Training: •Promote and further develop the collaboration in nuclear education and training of students, researchers and professionals •Ensure the quality of nuclear education and training •Increase the attractiveness for engagement in the nuclear fields for students, researchers and professionals •Promote life-long learning and career development at post-graduate or equivalent level

  4. Preparedness for Romanian Future Nuclear Industry - Methods to Attract Young Professionals

    International Nuclear Information System (INIS)

    Zaharov, Ionut; Goicea, Andrei

    2008-01-01

    'The management of nuclear knowledge has emerged as a growing challenge in recent years. The need to preserve, and transfer nuclear knowledge is compounded by recent trends such as ageing of nuclear-related field and a threat of loosing accumulated knowledge' as per IAEA said. Knowledge transfer is a very important task all over the word. In Romania we have some extra problems to attract young people to join us after graduation, to work in the nuclear field. Presently, Romania has two Candu Reactors in operation and our Government, decided to complete another two Nuclear Power Plants (two Candu 6 Reactors). As a result, more young engineers will be necessary to join us. We have to be prepared to assure that all the students know our needs and their possibilities to work in the nuclear field. The Prime Minister of Romania declared that 'is necessary to find a different site to build another Nuclear Power Plants in Romania'. That means other young engineers and also good young professionals must join us. The students must know their possibilities in the field after graduation. Romanian Association 'Nuclear Energy' - Young Generation must help nuclear industry in order to find solutions to attract in the nuclear field good quality people. A very alarmist statistic shows that in Romania, after graduation, most of the students prefer to change the domain, or prefer to work abroad. The reasons are various, but the most important is because the jobs for engineers are not paid well. The second most important reason is that, right now, in Romania the jobs offer for young engineers isn't various. What they do not know is that in the future possibilities in Romania will be more attractive for them and they will have well paid jobs. In this paper we present our strategies and methods used to communicated with students, and also what kind of problems has a young employer in Romania. Our mission is to convince them that we need them to work with us. We know that our results in

  5. Preparedness for Romanian Future Nuclear Industry - Methods to Attract Young Professionals

    Energy Technology Data Exchange (ETDEWEB)

    Zaharov, Ionut; Goicea, Andrei [Nuclearelectrica Co, 65 Polona street, Bucharest (Romania)

    2008-07-01

    'The management of nuclear knowledge has emerged as a growing challenge in recent years. The need to preserve, and transfer nuclear knowledge is compounded by recent trends such as ageing of nuclear-related field and a threat of loosing accumulated knowledge' as per IAEA said. Knowledge transfer is a very important task all over the word. In Romania we have some extra problems to attract young people to join us after graduation, to work in the nuclear field. Presently, Romania has two Candu Reactors in operation and our Government, decided to complete another two Nuclear Power Plants (two Candu 6 Reactors). As a result, more young engineers will be necessary to join us. We have to be prepared to assure that all the students know our needs and their possibilities to work in the nuclear field. The Prime Minister of Romania declared that 'is necessary to find a different site to build another Nuclear Power Plants in Romania'. That means other young engineers and also good young professionals must join us. The students must know their possibilities in the field after graduation. Romanian Association 'Nuclear Energy' - Young Generation must help nuclear industry in order to find solutions to attract in the nuclear field good quality people. A very alarmist statistic shows that in Romania, after graduation, most of the students prefer to change the domain, or prefer to work abroad. The reasons are various, but the most important is because the jobs for engineers are not paid well. The second most important reason is that, right now, in Romania the jobs offer for young engineers isn't various. What they do not know is that in the future possibilities in Romania will be more attractive for them and they will have well paid jobs. In this paper we present our strategies and methods used to communicated with students, and also what kind of problems has a young employer in Romania. Our mission is to convince them that we need them to work

  6. Attractiveness of people-centred and integrated Dutch Home Care: A nationwide survey among nurses.

    Science.gov (United States)

    Maurits, Erica E M; de Veer, Anke J E; Groenewegen, Peter P; Francke, Anneke L

    2018-03-05

    The World Health Organization is calling for a fundamental change in healthcare services delivery, towards people-centred and integrated health services. This includes providing integrated care around people's needs that is effectively co-ordinated across providers and co-produced by professionals, the patient, the family and the community. At the same time, healthcare policies aim to scale back hospital and residential care in favour of home care. This is one reason for the home-care nursing staff shortages in Europe. Therefore, this study aimed to examine whether people-centred, integrated home care appeals to nurses with different levels of education in home care and hospitals. A questionnaire survey was held among registered nurses in Dutch home-care organisations and hospitals in 2015. The questionnaire addressed the perceived attractiveness of different aspects of people-centred, integrated home care. In total 328 nurses filled in the questionnaire (54% response rate). The findings showed that most home-care nurses (70% to 97%) and 36% to 76% of the hospital nurses regard the different aspects of people-centred, integrated home care as attractive. Specific aspects that home-care nurses find attractive are promoting the patient's self-reliance and having a network in the community. Hospital nurses are mainly attracted to health-related prevention and taking control in complex situations. No clear differences between the educational levels were found. It is concluded that most home-care nurses and a minority of hospital nurses feel attracted to people-centred, integrated home care, irrespective of their educational level. The findings are relevant to policy makers and home-care organisations who aim to expand the home-care nursing workforce. © 2018 John Wiley & Sons Ltd.

  7. When does familiarity promote versus undermine interpersonal attraction? A proposed integrative model from erstwhile adversaries.

    Science.gov (United States)

    Finkel, Eli J; Norton, Michael I; Reis, Harry T; Ariely, Dan; Caprariello, Peter A; Eastwick, Paul W; Frost, Jeana H; Maniaci, Michael R

    2015-01-01

    This article began as an adversarial collaboration between two groups of researchers with competing views on a longstanding question: Does familiarity promote or undermine interpersonal attraction? As we explored our respective positions, it became clear that the limitations of our conceptualizations of the familiarity-attraction link, as well as the limitations of prior research, were masking a set of higher order principles capable of integrating these diverse conceptualizations. This realization led us to adopt a broader perspective, which focuses on three distinct relationship stages-awareness, surface contact, and mutuality-and suggests that the influence of familiarity on attraction depends on both the nature and the stage of the relationship between perceivers and targets. This article introduces the framework that emerged from our discussions and suggests directions for research to investigate its validity. © The Author(s) 2014.

  8. The gravitational attraction algorithm: a new metaheuristic applied to a nuclear reactor core design optimization problem

    International Nuclear Information System (INIS)

    Sacco, Wagner F.; Oliveira, Cassiano R.E. de

    2005-01-01

    A new metaheuristic called 'Gravitational Attraction Algorithm' (GAA) is introduced in this article. It is an analogy with the gravitational force field, where a body attracts another proportionally to both masses and inversely to their distances. The GAA is a populational algorithm where, first of all, the solutions are clustered using the Fuzzy Clustering Means (FCM) algorithm. Following that, the gravitational forces of the individuals in relation to each cluster are evaluated and this individual or solution is displaced to the cluster with the greatest attractive force. Once it is inside this cluster, the solution receives small stochastic variations, performing a local exploration. Then the solutions are crossed over and the process starts all over again. The parameters required by the GAA are the 'diversity factor', which is used to create a random diversity in a fashion similar to genetic algorithm's mutation, and the number of clusters for the FCM. GAA is applied to the reactor core design optimization problem which consists in adjusting several reactor cell parameters in order to minimize the average peak-factor in a 3-enrichment-zone reactor, considering operational restrictions. This problem was previously attacked using the canonical genetic algorithm (GA) and a Niching Genetic Algorithm (NGA). The new metaheuristic is then compared to those two algorithms. The three algorithms are submitted to the same computational effort and GAA reaches the best results, showing its potential for other applications in the nuclear engineering field as, for instance, the nuclear core reload optimization problem. (author)

  9. Proliferation attractiveness of nuclear material in a small modular pressure tube SCWR

    Energy Technology Data Exchange (ETDEWEB)

    McDonald, M.; Pencer, J., E-mail: mcdonamh@aecl.ca, E-mail: pencerj@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2013-07-01

    The SuperSafe© Reactor (SSR), has been recently proposed as a small modular version of the Canadian supercritical water cooled reactor (SCWR). This reactor is a heavy water moderated, pressure tube reactor using supercritical light water as coolant. The current SSR design is to generate 300 MWe taking advantage of the expected high thermal efficiency (assumed 45%). As one of the reactor types being considered by the Generation-IV International Forum, it is expected that this SCWR design will feature enhanced proliferation resistance over current generation technologies. Proliferation resistance assessments are wide-ranging, multidisciplinary efforts that are typically performed at a number of levels, from a state level down to a specific facility level. One small, but particularly important, sub-assessment is that of nuclear material attractiveness, that is, assessing the quality of nuclear materials throughout the fuel cycle for use in making a nuclear explosive device. The attractiveness of materials for three different SSR fuel options is examined in this work. (author)

  10. Vertical integration in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Mommsen, J.T.

    1977-01-01

    Vertical integration in the nuclear fuel cycle and its contribution to market power of integrated fuel suppliers were studied. The industry subdivision analyzed is the uranium raw materials sector. The hypotheses demonstrated are that (1) this sector of the industry is trending toward vertical integration between production of uranium raw materials and the manufacture of nuclear fuel elements, and (2) this vertical integration confers upon integrated firms a significant market advantage over non-integrated fuel manufacturers. Under microeconomic concepts the rationale for vertical integration is the pursuit of efficiency, and it is beneficial because it increases physical output and decreases price. The Market Advantage Model developed is an arithmetical statement of the relative market power (in terms of price) between non-integrated nuclear fuel manufacturers and integrated raw material/fuel suppliers, based on the concept of the ''squeeze.'' In operation, the model compares net profit and return on sales of nuclear fuel elements between the competitors, under different price and cost circumstances. The model shows that, if integrated and non-integrated competitors sell their final product at identical prices, the non-integrated manufacturer returns a net profit only 17% of the integrated firm. Also, the integrated supplier can price his product 35% below the non-integrated producer's price and still return the same net profit. Vertical integration confers a definite market advantage to the integrated supplier, and the basic source of that advantage is the cost-price differential of the raw material, uranium

  11. Accurate collision integrals for the attractive static screened Coulomb potential with application to electrical conductivity. [For white dwarf stars

    Energy Technology Data Exchange (ETDEWEB)

    Macdonald, J. (Delaware, University, Newark (USA))

    1991-05-01

    The results of accurate calculations of collision integrals for the attractive static screened Coulomb potential are presented. To obtain high accuracy with minimal computational cost, the integrals are evaluated by a quadrature method based on the Whittaker cardinal function. The collision integrals for the attractive potential are needed for calculation of the electrical conductivity of a dense fully or partially ionized plasma, and the results presented here are appropriate for the conditions in the nondegenerate envelopes of white dwarf stars. 25 refs.

  12. Financing of an integrated nuclear desalination system in developing countries

    International Nuclear Information System (INIS)

    Bouzguenda, N.; Albouy, M.; Nisan, S.

    2007-01-01

    This paper focuses on a case study of financing a project of an integrated nuclear desalination system at la Skhira site in Tunisia. More specifically, it shows the financial characteristics of this project, known as TUNDESAL, the main financing mechanisms that can be used, and the principal actions required to attract the potential investors and lenders. The paper describes the basic requirements for the deployment of nuclear energy in a developing or an emerging country, with no previous experience of nuclear power; the specific financial considerations corresponding to the particular characteristics of nuclear desalination projects: high capital costs, high level of risks and uncertainties related in particular to long construction lead times and social and environmental concerns; the main risks of these projects; the profitability study of the TUNDESAL project: application of the discounted cash flow analysis; the main financing sources for the project; the financing schemes that can be used for project implementation and comparison between these schemes in terms of benefits generated, after covering project costs and repayment of lenders and investors; the main actions to be done for making the project financially attractive in order to gain the confidence of investors and international financial institutions (optimal allocation of project risks and uncertainties, a suitable and flexible energy and water tariffs policy, etc.). The analysis has shown that in particular conditions of Tunisia, the most attractive financial scheme could be the 'project financing + leasing'. (authors)

  13. Integrated nuclear and radiation protection systems

    International Nuclear Information System (INIS)

    Oprea, I.; Oprea, M.; Stoica, V.; Cerga, V.; Pirvu, V.; Badea, E.

    1993-01-01

    A multifunctional radiation monitoring equipment, flexible and capable to meet virtually environmental radiation monitoring, activity measurement and computational requirements, for nuclear laboratories has been designed. It can be used as a radiation protection system, for radionuclide measurement in isotope laboratories, nuclear technology, health physics and nuclear medicine, nuclear power stations and nuclear industry. The equipment is able to measure, transmit and record gamma dose rate and isotope activities. Other parameters and functions are optionally available, such as: self-contained alarm level, system self-test, dose integrator, syringe volume calculation for a given dose corrected for decay, calibration factor, 99 Mo assays performing and background subtraction

  14. Integrated Nuclear Security Support Plan (INSSP)

    International Nuclear Information System (INIS)

    Moore, G.M.

    2010-01-01

    Integrated Nuclear Security Support Plan (INSSP) purposes the framework for a comprehensive approach to addressing specific national security needs. It provides means for coordinating nuclear security assistance to member states. Identifies responsible parties for completion of nuclear security activities which are necessary to build sustainable nuclear security programs. International Atomic Energy Agency INSSP development process is based on findings and recommendations from a range of nuclear security missions and other information needs assessments. Takes into account of the ongoing work activities of other bilateral assistance.

  15. Integrated nuclear radiation detector and monitor

    International Nuclear Information System (INIS)

    Biehl, B.L.; Lieberman, S.I.

    1982-01-01

    A battery powered device which can continuously monitor and detect nuclear radiation utilizing fully integrated circuitry and which is provided with an alarm which alerts persons when the radiation level exceeds a predetermined threshold

  16. Excavation of attractor modules for nasopharyngeal carcinoma via integrating systemic module inference with attract method.

    Science.gov (United States)

    Jiang, T; Jiang, C-Y; Shu, J-H; Xu, Y-J

    2017-07-10

    The molecular mechanism of nasopharyngeal carcinoma (NPC) is poorly understood and effective therapeutic approaches are needed. This research aimed to excavate the attractor modules involved in the progression of NPC and provide further understanding of the underlying mechanism of NPC. Based on the gene expression data of NPC, two specific protein-protein interaction networks for NPC and control conditions were re-weighted using Pearson correlation coefficient. Then, a systematic tracking of candidate modules was conducted on the re-weighted networks via cliques algorithm, and a total of 19 and 38 modules were separately identified from NPC and control networks, respectively. Among them, 8 pairs of modules with similar gene composition were selected, and 2 attractor modules were identified via the attract method. Functional analysis indicated that these two attractor modules participate in one common bioprocess of cell division. Based on the strategy of integrating systemic module inference with the attract method, we successfully identified 2 attractor modules. These attractor modules might play important roles in the molecular pathogenesis of NPC via affecting the bioprocess of cell division in a conjunct way. Further research is needed to explore the correlations between cell division and NPC.

  17. Nuclear power programme planning: An integrated approach

    International Nuclear Information System (INIS)

    2001-12-01

    The International Atomic Energy Agency (IAEA) has published material on different policy considerations in the introduction of nuclear power, primarily addressed to top level decision makers in government and industry in Member States. Several Member States and experts recommended to the IAEA to address the aspects of an integrated approach to nuclear power programme planning and to serve as guidance to those countries wishing to embark on a nuclear power programme. As a follow-up, the present publication is primarily intended to serve as guidance for executives and managers in Member States in planning for possible introduction of nuclear power plants in their electricity generating systems. Nuclear power programme planning, as dealt with in this publication, includes all activities that need to be carried out up to a well-founded decision to proceed with a project feasibility study. Project implementation beyond this decision is not in the scope of this publication. Although it is possible to use nuclear energy as a heat source for industrial processes, desalination and other heat applications, it is assumed in this publication that the planning is aimed towards nuclear power for electricity generation. Much of the information given would, however, also be relevant for planning of nuclear reactors for heat production. The publication was prepared within the framework of the IAEA programme on nuclear power planning, implementation and performance as a joint activity of the Nuclear Power Engineering Section and the Planning and Economic Studies Section (Division of Nuclear Power)

  18. Spent nuclear fuel project integrated schedule plan

    International Nuclear Information System (INIS)

    Squires, K.G.

    1995-01-01

    The Spent Nuclear Fuel Integrated Schedule Plan establishes the organizational responsibilities, rules for developing, maintain and status of the SNF integrated schedule, and an implementation plan for the integrated schedule. The mission of the SNFP on the Hanford site is to provide safe, economic, environmentally sound management of Hanford SNF in a manner which stages it to final disposition. This particularly involves K Basin fuel

  19. Spent nuclear fuel project integrated schedule plan

    Energy Technology Data Exchange (ETDEWEB)

    Squires, K.G.

    1995-03-06

    The Spent Nuclear Fuel Integrated Schedule Plan establishes the organizational responsibilities, rules for developing, maintain and status of the SNF integrated schedule, and an implementation plan for the integrated schedule. The mission of the SNFP on the Hanford site is to provide safe, economic, environmentally sound management of Hanford SNF in a manner which stages it to final disposition. This particularly involves K Basin fuel.

  20. Integrated Global Nuclear Materials Management Preliminary Concepts

    International Nuclear Information System (INIS)

    Jones, E; Dreicer, M.

    2006-01-01

    The world is at a turning point, moving away from the Cold War nuclear legacy towards a future global nuclear enterprise; and this presents a transformational challenge for nuclear materials management. Achieving safety and security during this transition is complicated by the diversified spectrum of threat 'players' that has greatly impacted nonproliferation, counterterrorism, and homeland security requirements. Rogue states and non-state actors no longer need self-contained national nuclear expertise, materials, and equipment due to availability from various sources in the nuclear market, thereby reducing the time, effort and cost for acquiring a nuclear weapon (i.e., manifestations of latency). The terrorist threat has changed the nature of military and national security requirements to protect these materials. An Integrated Global Nuclear Materials Management (IGNMM) approach would address the existing legacy nuclear materials and the evolution towards a nuclear energy future, while strengthening a regime to prevent nuclear weapon proliferation. In this paper, some preliminary concepts and studies of IGNMM will be presented. A systematic analysis of nuclear materials, activities, and controls can lead to a tractable, integrated global nuclear materials management architecture that can help remediate the past and manage the future. A systems approach is best suited to achieve multi-dimensional and interdependent solutions, including comprehensive, end-to-end capabilities; coordinated diverse elements for enhanced functionality with economy; and translation of goals/objectives or standards into locally optimized solutions. A risk-informed basis is excellent for evaluating system alternatives and performances, and it is especially appropriate for the security arena. Risk management strategies--such as defense-in-depth, diversity, and control quality--help to weave together various technologies and practices into a strong and robust security fabric. Effective

  1. Integrating virtual reality applications in nuclear safeguards

    International Nuclear Information System (INIS)

    Barletta, Michael; Crete, Jean-Maurice; Pickett, Susan

    2011-01-01

    Virtual reality (VR) tools have already been developed and deployed in the nuclear industry, including in nuclear power plant construction, project management, equipment and system design, and training. Recognized as powerful tools for, inter alia, integration of data, simulation of activities, design of facilities, validation of concepts and mission planning, their application in nuclear safeguards is still very limited. However, VR tools may eventually offer transformative potential for evolving the future safeguards system to be more fully information-driven. The paper focuses especially on applications in the area of training that have been underway in the Department of Safeguards of the International Atomic Energy Agency. It also outlines future applications envisioned for safeguards information and knowledge management, and information-analytic collaboration. The paper identifies some technical and programmatic pre-requisites for realizing the integrative potential of VR technologies. If developed with an orientation to integrating applications through compatible platforms, software, and models, virtual reality tools offer the long-term potential of becoming a real 'game changer,' enabling a qualitative leap in the efficiency and effectiveness of nuclear safeguards. The IAEA invites Member States, industry, and academia to make proposals as to how such integrating potential in the use of virtual reality technology for nuclear safeguards could be realized. (author)

  2. Integrated spent nuclear fuel database system

    International Nuclear Information System (INIS)

    Henline, S.P.; Klingler, K.G.; Schierman, B.H.

    1994-01-01

    The Distributed Information Systems software Unit at the Idaho National Engineering Laboratory has designed and developed an Integrated Spent Nuclear Fuel Database System (ISNFDS), which maintains a computerized inventory of all US Department of Energy (DOE) spent nuclear fuel (SNF). Commercial SNF is not included in the ISNFDS unless it is owned or stored by DOE. The ISNFDS is an integrated, single data source containing accurate, traceable, and consistent data and provides extensive data for each fuel, extensive facility data for every facility, and numerous data reports and queries

  3. Ghana's Integrated Nuclear Security Support Plan

    International Nuclear Information System (INIS)

    Dahlstrom, Danielle

    2013-01-01

    At the Korle Bu Teaching Hospital outside Accra, Pearl Lovelyn Lawson checks the records of the next patient to undergo radiotherapy and adjusts the dose settings of the teletherapy machine. It is business as usual at the facility that treats over fifty patients each day. But Lawson's routine now includes additional procedures to ensure that the highly radioactive cobalt-60 source located inside the machine remains secure. Nuclear security devices and systems such as double locks, motion sensors, and cameras that transmit images to a central alarm system have been installed to ensure that the source cannot be stolen, the facility sabotaged, or unauthorized access gained. At Korle Bu physical protection measures were upgraded as part of Ghana's Integrated Nuclear Security Support Plan (INSSP). Preventing, detecting and responding to criminal acts like the theft or illegal transfer of a radioactive source, is an international priority that could be addressed through an INSSP. As one of its key nuclear security services, the IAEA assists Member States in drafting such plans. An INSSP is developed jointly with the Member State, using a holistic approach to nuclear security capacity building. It reinforces the primary objective of a State's nuclear security regime to protect people, society, and the environment from the harmful consequences of a nuclear security event. Addressing five components - the legal and regulatory framework, prevention, detection, and sustainability - the jointly developed plan identifies the needs, responsible entities and organizations within the State, as well as the timeframe for the implementation of agreed nuclear security related activities. Ghana's INSSP, tailored to its specific needs, is based on findings and recommendations from advisory service missions carried out in Ghana, including an International Nuclear Security Advisory Service mission and an International Physical Protection Advisory Service mission. Ghana's INSSP was

  4. World Integrated Nuclear Evaluation System: Model documentation

    International Nuclear Information System (INIS)

    1991-12-01

    The World Integrated Nuclear Evaluation System (WINES) is an aggregate demand-based partial equilibrium model used by the Energy Information Administration (EIA) to project long-term domestic and international nuclear energy requirements. WINES follows a top-down approach in which economic growth rates, delivered energy demand growth rates, and electricity demand are projected successively to ultimately forecast total nuclear generation and nuclear capacity. WINES could be potentially used to produce forecasts for any country or region in the world. Presently, WINES is being used to generate long-term forecasts for the United States, and for all countries with commercial nuclear programs in the world, excluding countries located in centrally planned economic areas. Projections for the United States are developed for the period from 2010 through 2030, and for other countries for the period starting in 2000 or 2005 (depending on the country) through 2010. EIA uses a pipeline approach to project nuclear capacity for the period between 1990 and the starting year for which the WINES model is used. This approach involves a detailed accounting of existing nuclear generating units and units under construction, their capacities, their actual or estimated time of completion, and the estimated date of retirements. Further detail on this approach can be found in Appendix B of Commercial Nuclear Power 1991: Prospects for the United States and the World

  5. Integrated engineering system for nuclear facilities building

    International Nuclear Information System (INIS)

    Tomura, H.; Miyamoto, A.; Futami, F.; Yasuda, S.; Ohtomo, T.

    1995-01-01

    In the construction of buildings for nuclear facilities in Japan, construction companies are generally in charge of the building engineering work, coordinating with plant engineering. An integrated system for buildings (PROMOTE: PROductive MOdeling system for Total nuclear Engineering) described here is a building engineering system including the entire life cycle of buildings for nuclear facilities. A Three-dimensional (3D) building model (PRO-model) is to be in the core of the system (PROMOTE). Data sharing in the PROMOTE is also done with plant engineering systems. By providing these basic technical foundations, PROMOTE is oriented toward offering rational, highquality engineering for the projects. The aim of the system is to provide a technical foundation in building engineering. This paper discusses the characteristics of buildings for nuclear facilities and the outline of the PROMOTE. (author)

  6. Nuclear plants gain integrated information systems

    International Nuclear Information System (INIS)

    Villavicencio-Ramirez, A.; Rodriquez-Alvarez, J.M.

    1994-01-01

    With the objective of simplifying the complex mesh of computing devices employed within nuclear power plants, modern technology and integration techniques are being used to form centralized (but backed up) databases and distributed processing and display networks. Benefits are immediate as a result of the integration and the use of standards. The use of a unique data acquisition and database subsystem optimizes the high costs of engineering, as this task is done only once for the life span of the system. This also contributes towards a uniform user interface and allows for graceful expansion and maintenance. This article features an integrated information system, Sistema Integral de Informacion de Proceso (SIIP). The development of this system enabled the Laguna Verde Nuclear Power plant to fully use the already existing universe of signals and its related engineering during all plant conditions, namely, start up, normal operation, transient analysis, and emergency operation. Integrated systems offer many advantages over segregated systems, and this experience should benefit similar development efforts in other electric power utilities, not only for nuclear but also for other types of generating plants

  7. Attracting and Retaining Talent and Building Knowledge Networks in the Global Nuclear Industry

    International Nuclear Information System (INIS)

    Thomas, C.

    2014-01-01

    Effective recruitment strategy: → Distinctly separate strategies for Nuclear and Non-Nuclear; Engagement with nuclear communities; → Investment in the recruitment process – both time and personnel; → Selecting supply chain partners that match objectives; → Different approaches for different demographics

  8. When does familiarity promote versus undermine interpersonal attraction? A proposed integrative model from erstwhile adversaries

    NARCIS (Netherlands)

    Frost, J.H.; Finkel, E.J.; Norton, M.I.; Ariely, D.; Caprariello, P.A.; Eastwick, P.W.

    2015-01-01

    This article began as an adversarial collaboration between two groups of researchers with competing views on a longstanding question: Does familiarity promote or undermine interpersonal attraction? As we explored our respective positions, it became clear that the limitations of our

  9. Nondestructive testing of nuclear reactor components integrity

    International Nuclear Information System (INIS)

    Mala, M.; Miklos, M.

    2011-01-01

    Nuclear energy must respond to current challenges in the energy market. The significant parameters are increase of the nuclear fuel price, closed fuel cycle, reduction and safe and the final disposal of high level radioactive waste. Nowadays, the discussions on suitable energy mix are taking place not only here in Czech Republic, but also in many other European countries. It is necessary to establish an appropriate ratio among the production of electricity from conventional, nuclear and renewable energy sources. Also, it is necessary to find ways how to streamline the economy, central part of the nuclear fuel cycle and thereby to increase the competitiveness of nuclear energy. This streamlining can be carried out by improving utilization of existing nuclear fuel with maintaining a high degree of nuclear facilities safety. Increasing operational reliability and safety together with increasing utilization of nuclear fuel place increasing demands on monitoring of changes during fuel burnup. The potential fuel assembly damages in light water reactors are prevented by the introduction of new procedures and programs of the fuel assembly monitoring. One of them is the Post Irradiation Inspection Program (PIIP) which is a good tool for monitoring of chemical regime impact on the fuel assembly cladding behavior. Main nondestructive techniques that are used at nuclear power plants for the fuel assembly integrity evaluation are ultrasonic measurements, eddy current measurements, radiographic testing, acoustic techniques and others. Ultrasonic system is usual tool for leak fuel rod evaluation and it is also used at Temelin NPP. Since 2009, Temelin NPP has cooperated with Research Center Rez Ltd in frame of PIIP program at both units WWER 1000. This program was established for US VVantage6 fuel assemblies and also it continues for Russian TVSA-T fuel assemblies. (author)

  10. Integrated management systems in the nuclear field

    International Nuclear Information System (INIS)

    Beckmerhagen, I.A.; Berg, H.P.; Karapetrovic, S.V.; Willborn, W.O.

    2005-01-01

    In the last years several internationally accepted standards such as the ISO 9000 and ISO 14000 series and other function-specific management systems standards have been developed. At the same time, it has become imperative for organisations to continuously improve their overall quality, environmental and safety performance. Therefore, the need to create integrated management systems is of growing importance to enable an easier handling of the different management systems. This paper has two main objectives. The first one is to address the key issues in the underlying theory of integrated management systems including benefits and limits, the second one is to illustrate the importance of an integrated (in particular safety) management system and the experience feedback providing examples from different areas and different organisations in the nuclear field. (orig.)

  11. Bibliography of integral charged particle nuclear data

    International Nuclear Information System (INIS)

    Holden, N.E.; Burrows, T.W.

    1982-03-01

    This publication is the second supplement to the archival edition of the National Nuclear Data Center's charged-particle bibliography. This supplement contains citations to all references scanned since March 15, 1981, and all corrections and additions to previous citations, and indexes all data received in the international exchanged format (EXFOR). The primary goal of the bibliography has been to satisfy the need expressed by the Nuclear Reaction Data Center Network for a concise and comprehensive bibliography of integral charged-particle cross section data and to provide an index of data exchanged among the members. In 1980, coverage was expanded to include differential data relevant to charged-particle-induced neutron-source reactions

  12. Integration of Social Sciences in Nuclear Research

    International Nuclear Information System (INIS)

    Bovy, M.; Eggermont, G.

    2002-01-01

    In 1998, SCK-CEN initiated a programme to integrate social sciences into its scientific and technological projects. Activities were started on the following issues: (1) sustainable development; (2) ethics and decision making in nuclear waste management (transgenerational ethics/retrievability; socio-psychological aspect and local involvement); (3) law and liability (medical applications and the basic safety standards implementation); (4) decision making (emergency management); safety culture; ALARA and ethical choices in protection). Two working groups were created to discuss two broad items: (1) ethical choices in radiation protection; and (2) the role and culture of the expert. Progress and major achievements in SCK-CEN's social science programme in 2001 are summarised

  13. Development of improved attractants and their integration into fruit fly management programmes

    Energy Technology Data Exchange (ETDEWEB)

    Sookar, P.; Permalloo, S.; Alleck, M.; Seewooruthun, S.I., E-mail: ento@intnet.m, E-mail: moa-entomology@mail.gov.m [Ministry of Agro Industry and Fisheries, Reduit (Mauritius)

    2006-07-01

    Fruit flies are major constraint to fruit production in Mauritius. The peach fruit fly, Bactrocera zonata (Saunders), the natal fly, Ceratitis rosa (Karsch), the medfly, C. capitata (Wiedmann) are the main pests of fleshy fruits. Fruit fly trapping trials were conducted in backyards to find the most effective combination of attractant and lures for females. There were two separate trapping trials, carried out in two different localities during the period November 2004 to March 2005. In the first trial, the attractants in different combinations were tested in International Pheromone McPhail Trap (IPMT). The attractants were as follows: three patches containing Ammonium Acetate (AA) + Trimethylamine (TMA) + Putrescine (PT); Two patches of AA ; two patches of AA + one patch of PT ; two patches of AA + one patch of TMA; one patch of solbait; torula tablets; protein hydrolysate and GF120. Water and Triton B were used as retention device in traps baited with the patches. In the first trial, all treatments were equally effective in the capture of either female B. zonata or female C. capitata with the exception of protein hydrolysate and GF120 which trapped fewer numbers of flies. In the second trapping trial, additional trap types and lure combinations were assessed. The three component lure (AA + PT + TMA with water/Triton as retention device in IPMT) and the trap baited with Waste Brewer's Yeast captured significantly more female flies followed by IPMT with AA + PT + TMA / Sticky insert and the Easy trap. In all trials, females accounted for more than 75% of the catches. (author)

  14. Development of improved attractants and their integration into fruit fly management programmes

    International Nuclear Information System (INIS)

    Sookar, P.; Permalloo, S.; Alleck, M.; Seewooruthun, S.I.

    2006-01-01

    Fruit flies are major constraint to fruit production in Mauritius. The peach fruit fly, Bactrocera zonata (Saunders), the natal fly, Ceratitis rosa (Karsch), the medfly, C. capitata (Wiedmann) are the main pests of fleshy fruits. Fruit fly trapping trials were conducted in backyards to find the most effective combination of attractant and lures for females. There were two separate trapping trials, carried out in two different localities during the period November 2004 to March 2005. In the first trial, the attractants in different combinations were tested in International Pheromone McPhail Trap (IPMT). The attractants were as follows: three patches containing Ammonium Acetate (AA) + Trimethylamine (TMA) + Putrescine (PT); Two patches of AA ; two patches of AA + one patch of PT ; two patches of AA + one patch of TMA; one patch of solbait; torula tablets; protein hydrolysate and GF120. Water and Triton B were used as retention device in traps baited with the patches. In the first trial, all treatments were equally effective in the capture of either female B. zonata or female C. capitata with the exception of protein hydrolysate and GF120 which trapped fewer numbers of flies. In the second trapping trial, additional trap types and lure combinations were assessed. The three component lure (AA + PT + TMA with water/Triton as retention device in IPMT) and the trap baited with Waste Brewer's Yeast captured significantly more female flies followed by IPMT with AA + PT + TMA / Sticky insert and the Easy trap. In all trials, females accounted for more than 75% of the catches. (author)

  15. Attractiveness of people-centred and integrated Dutch home care: a nationwide survey among nurses.

    NARCIS (Netherlands)

    Maurits, E.E.M.; Veer, A.J.E. de; Groenewegen, P.P.; Francke, A.L.

    2018-01-01

    The World Health Organization is calling for a fundamental change in healthcare services delivery, towards people‐centred and integrated health services. This includes providing integrated care around people′s needs that is effectively co‐ordinated across providers and co‐produced by professionals,

  16. Initiatives of the Belgian SCK•CEN Academy to attract young talent in nuclear research and technology

    International Nuclear Information System (INIS)

    Coeck, Michèle

    2014-01-01

    Our aim: • Explain/refresh basics of radioactivity; • Discuss several examples of nuclear applications → In nuclear, medical, non-nuclear industry, daily life, … • Present research activities of SCK•CEN, justify why nuclear research is important, how does it contribute to well-being of society in general; • Discuss with teachers how the standard education programs can integrate a pluralistic approach to complex technical issues such as applications of radioactivity. Conclusions: • Focus on knowledge, understanding, skills, attitudes, … and show “real-life” situations = added value; • Mention the whole picture: → ALL application fields, ALL issues; • Motivate to choose for scientific or technical studies can be one aim, but equally (or more) important: discuss risks and benefits of nuclear applications in general, develop an open and critical mind in order to gain more insight in multi-facetted issues such as risks and benefits of radioactivity and nuclear technology, and contribute in serene way to the societal debate; • Contribution to critical-intellectual nuclear capacities for society

  17. Nuclear integrated database and design advancement system

    International Nuclear Information System (INIS)

    Ha, Jae Joo; Jeong, Kwang Sub; Kim, Seung Hwan; Choi, Sun Young.

    1997-01-01

    The objective of NuIDEAS is to computerize design processes through an integrated database by eliminating the current work style of delivering hardcopy documents and drawings. The major research contents of NuIDEAS are the advancement of design processes by computerization, the establishment of design database and 3 dimensional visualization of design data. KSNP (Korea Standard Nuclear Power Plant) is the target of legacy database and 3 dimensional model, so that can be utilized in the next plant design. In the first year, the blueprint of NuIDEAS is proposed, and its prototype is developed by applying the rapidly revolutionizing computer technology. The major results of the first year research were to establish the architecture of the integrated database ensuring data consistency, and to build design database of reactor coolant system and heavy components. Also various softwares were developed to search, share and utilize the data through networks, and the detailed 3 dimensional CAD models of nuclear fuel and heavy components were constructed, and walk-through simulation using the models are developed. This report contains the major additions and modifications to the object oriented database and associated program, using methods and Javascript.. (author). 36 refs., 1 tab., 32 figs

  18. Development of improved attractants and their integration into fruit fly SIT management programmes. Proceedings of a final research coordination meeting

    International Nuclear Information System (INIS)

    2007-10-01

    Information provided by trapping systems is used to assess the presence, seasonal abundance, spatial distribution, host sequence and infestation levels of fruit fly pests. This information is key for implementation of effective fruit fly control programmes. Most trapping systems commercially available are based on para-pheromones which are male specific. These male specific trapping systems have been used as the main survey tool in area-wide fruit fly control programmes. Nevertheless, in recent years, scientists and programme managers have realized that, in order to improve the efficiency of fruit fly control, it is essential to have a female specific or at least a female biased trapping system. Until the late 1990s, the only fruit fly female biased attractants were based on natural protein baits such as Torula Yeast and hydrolysate proteins. Although these attractants tend to catch more females than males (in average 60% females against 40% males), the proportion in favor of females is insufficient and the attractants are considered to be weak and non-selective. In 1999, as a result of a previous Coordinated Research Project (CRP) entitled 'Development of Female Medfly Attractant Systems for Trapping and Sterility Assessment' the first effective female biased synthetic food lure was developed for the Mediterranean fruit fly (Ceratitis capitata, Wied.) (IAEA-TECDOC-1099). This lure, with the commercial name of Biolure, is now being used in large-scale medfly control programmes worldwide. Given this background, and in order to further advance this field, the Joint FAO/IAEA Programme approved in 2000 a five year CRP entitled 'Development of Improved Attractants and their Integration into Fruit Fly SIT Management Programmes'. The research conducted under this CRP focused mainly on developing female biased trapping systems for other fruit fly species of quarantine and economic importance within the Anastrepha, Bactrocera, Ceratitis and Dacus genera and on optimization

  19. Unified analytical treatment of multicentre electron attraction, electric field and electric field gradient integrals over Slater orbitals

    International Nuclear Information System (INIS)

    Guseinov, I I

    2004-01-01

    The new central and noncentral potential functions (CPFs and NCPFs) of a molecule depending on the coordinates of the nuclei are introduced. Using complete orthonormal sets of Ψ α -exponential-type orbitals (Ψ α -ETOs) introduced by the author, the series expansion formulae for the multicentre electronic attraction (EA), electric field (EF) and electric field gradient (EFG) integrals over Slater-type orbitals (STOs) in terms of CPFs and NCPFs are derived. The relationships obtained are valid for the arbitrary location, quantum numbers and screening constants of STOs

  20. Online communication among adolescents: An integrated model on its attraction, opportunities, and risks.

    NARCIS (Netherlands)

    Valkenburg, P.M.; Peter, J.

    2011-01-01

    Adolescents far outnumber adults in their use of e-communication technologies, such as instant messaging and social network sites. In this article, we present an integrative model that helps us to understand both the appeal of these technologies and their risks and opportunities for the psychosocial

  1. Study on material attractiveness aspect of spent nuclear fuel of LWR and FBR cycles based on isotopic plutonium production

    International Nuclear Information System (INIS)

    Permana, Sidik; Suzuki, Mitsutoshi; Saito, Masaki; Novitrian,; Waris, Abdul; Suud, Zaki

    2013-01-01

    Highlights: • The paper analyzes the plutonium production of recycling nuclear fuel option. • To evaluate material attractiveness based on intrinsic feature of material barrier. • Evaluation based on isotopic plutonium composition of spent fuel LWR and FBR. • Even mass number of plutonium gives a significant contribution to material barrier, in particular Pu-238 and Pu-240. • Doping MA in FBR blanket is effective to increase material barrier from weapon grade plutonium to more than MOX fuel grade. - Abstract: Recycling minor actinide (MA) as well as used uranium and plutonium can be considered to reduce nuclear waste production as well as to increase the intrinsic aspect of nuclear nonproliferation as doping material. Plutonium production as a significant aspect of recycling nuclear fuel option, gives some advantages and challenges, such as fissile material utilization of plutonium as well as production of some even mass number plutonium. The study intends to evaluate the material attractiveness based on the intrinsic feature of material barrier such as plutonium composition, decay heat and spontaneous fission neutron components from spent fuel (SF) light water reactor (LWR) and fast breeder reactor (FBR) cycles. A significant contribution has been shown by decay heat (DH) and spontaneous fission neutron (SFN) of even mass number of plutonium isotopes to the total DH and SFN of plutonium element, in particular from isotopic plutonium Pu-238 and Pu-240 contributions. Longer decay cooling time and higher burnup are effective to increase the material barrier (DH and SFN) level from reactor grade plutonium level to MOX grade plutonium level. Material barrier of plutonium element from spent fuel (SF) FBR in the core regions has similarity to the material barrier profile of SF LWR which can be categorized as MOX fuel grade plutonium. Plutonium compositions, DH and SFN components are categorized as weapon grade plutonium level for FBR blanket regions with no

  2. Integrated living schedule for nuclear plants

    International Nuclear Information System (INIS)

    Milhiser, R.J.

    1985-01-01

    This paper addresses the change process, including decision making and a credible prioritization methodology. It is intended to result in an integrated plan being jointly accepted and defensible by the utility and the Nuclear Regulatory Commission (NRC). The program described has several advantages: the methodology is consistent with and defensible to NRC criteria; safety and economic factors are placed on a common basis for balancing; the use of valuation factors permits the utility to introduce judgements concerning the importance of any particular benefit; alternative value judgments can easily be examined; explicit indications of the level of confidence in investment outcome is provided; and a definitive framework for establishing and reviewing decision criteria and application is provided

  3. Integration of Social Sciences in Nuclear Research

    Energy Technology Data Exchange (ETDEWEB)

    Bovy, M.; Eggermont, G

    2002-04-01

    In 1998, SCK-CEN initiated a programme to integrate social sciences into its scientific and technological projects. Activities were started on the following issues: (1) sustainable development; (2) ethics and decision making in nuclear waste management (transgenerational ethics/retrievability; socio-psychological aspect and local involvement); (3) law and liability (medical applications and the basic safety standards implementation); (4) decision making (emergency management); safety culture; ALARA and ethical choices in protection). Two working groups were created to discuss two broad items: (1) ethical choices in radiation protection; and (2) the role and culture of the expert. Progress and major achievements in SCK-CEN's social science programme in 2001 are summarised.

  4. Technical Integration of Nuclear Hydrogen Production Technology

    International Nuclear Information System (INIS)

    Lee, Ki Young; Park, J. K.; Chang, J. H.

    2009-04-01

    These works focus on the development of attainment indices for nuclear hydrogen key technologies, the analysis of the hydrogen production process and the performance estimation for hydrogen production systems, and the assessment of the nuclear hydrogen production cost. For assessing the degree of attainments in comparison with the final goals of VHTR technologies in progress of researches, subdivided are the prerequisite items confirmed to the NHDD concepts. We developed and applied R and D quality management methodology to meet 'Development of Key Technologies for Nuclear Hydrogen' project. And we also distributed R and D QAM and R and D QAP to each teams and are in operation. The preconceptual flow diagrams of SI, HTSE, and HyS processes are introduced and their material and energy balances have been proposed. The hydrogen production thermal efficiencies of not only the SI process as a reference process but also the HTSE and HyS processes were also estimated. Technical feasibility assessments of SI, HTSE, and HyS processes have been carried out by using the pair-wise comparison and analytic hierarchy process, and it is revealed that the experts are considering the SI process as the most feasible process. The secondary helium pathway across the SI process is introduced. Dynamic simulation codes for the H2S04vaporizer, sulfuric acid and sulfur trioxide decomposers, and HI decomposer on the secondary helium pathway and for the primary and secondary sulfuric acid distillation columns, HIx solution distillation column, and preheater for HI vapor have been developed and integrated

  5. Online communication among adolescents: an integrated model of its attraction, opportunities, and risks.

    Science.gov (United States)

    Valkenburg, Patti M; Peter, Jochen

    2011-02-01

    Adolescents far outnumber adults in their use of e-communication technologies, such as instant messaging and social network sites. In this article, we present an integrative model that helps us to understand both the appeal of these technologies and their risks and opportunities for the psychosocial development of adolescents. We first outline how the three features (anonymity, asynchronicity, and accessibility) of online communication stimulate controllability of online self-presentation and self-disclosure among adolescents. We then review research on the risks and opportunities of online self-presentation and self-disclosure for the three components of adolescents' psychosocial development, including identity (self-unity, self-esteem), intimacy (relationship formation, friendship quality, cyberbullying), and sexuality (sexual self-exploration, unwanted sexual solicitation). Existing research suggests several opportunities of online communication, such as enhanced self-esteem, relationship formation, friendship quality, and sexual self-exploration. It also yields evidence of several risks, including cyberbullying and unwanted sexual solicitation. We discuss the shortcomings of existing research, the possibilities for future research, and the implications for educators and health care professionals. Copyright © 2011 Society for Adolescent Health and Medicine. Published by Elsevier Inc. All rights reserved.

  6. New generation nuclear power units of PWR type integral reactors

    International Nuclear Information System (INIS)

    Mitenkov, F.M.; Kurachen Kov, A.V.; Malamud, V.A.; Panov, Yu.K.; Runov, B.I.; Flerov, L.N.

    1997-01-01

    Design bases of new generation nuclear power units (nuclear power plants - NPP, nuclear co-generation plants - NCP, nuclear distract heating plants - NDHP), using integral type PWPS, developed in OKBM, Nizhny Novgorod and trends of design decisions optimization are considered in this report. The problems of diagnostics, servicing and repair of the integral reactor components in course of operation are discussed. The results of safety analysis, including the problems of several accident localization with postulated core melting and keeping corium in the reactor vessel and guard vessel are presented. Information on experimental substantiation of the suggested plant design decisions is presented. (author)

  7. Integrated control system for nuclear explosives

    Energy Technology Data Exchange (ETDEWEB)

    Ragsdale, William F [Lawrence Radiation Laboratory, University of California, Livermore, CA (United States)

    1970-05-15

    The Integrated Control System (ICS) has been developed to facilitate Plowshare nuclear detonations by following a unified system approach. This system consolidates the techniques for firing, safety program, scientific program, and communications. Maximum emphasis is placed upon control and data transmission by radio rather than hardwire or coaxial cable. The ICS consists of a Command Point (CP) Trailer, a radio repeater station, a field station (the ICE Box), and several chassis located in the explosive canister. Commands originate in the CP and are transmitted via microwave radio to the ICE Box; monitors are returned to the CP from the canister, the ICE Box, and sensors near ground zero. The system allows complete checkout and operation before shipment to the field. The explosive canister may be dry-run at the assembly area (at NTS) before shipment to the field. The basic detonation functions for every event are: 1. Arming and firing commands in the explosive canister and at surface ground zero. 2. Environmental monitors and suitable arming monitors in the explosive canister. 3. Safety monitors at the zero site for weather, RAMS (Remote Area Monitoring System), and cavity collapse. Secondary functions that may be required for a specific project are: 4. Scientific program of phenomenology measurements. 5. Explosive performance measurements. 6. Ground zero television. 7. Auxiliary communications such as local telephones, VHF radio. By combining functions that have previously been performed by separate organizations and systems, the ICS attempts a minimum cost detonation service. Economy of operation results because: 1. Operating personnel work on more than one sub-system. 2. Interfaces and interface complexity are minimized. 3. A reduced dependence upon signal cables results from a microwave-based system. 4. Pre-fabrication allows test operation before shipment to the field and minimizes setup time in the field. The ICS is in use on the Sturtevant event and is

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

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  9. Financial study of an integrated nuclear desalination system in Tunisia: the Tundesal Project

    International Nuclear Information System (INIS)

    Bouzguenda Benzarti, Neila; Albouy, Michel; Nisan, Simon

    2006-01-01

    This paper focuses on a case study of financing an integrated nuclear desalination system at la Skhira site in Tunisia. More specifically, it shows the financial characteristics of the study, known as the TUNDESAL project, the main financing mechanisms that can be used, and the principal actions required to attract the potential investors and lenders. The paper describes: - The specific financial considerations corresponding to the particular characteristics of nuclear desalination projects: high capital costs, high level of risks and uncertainties, relatively long construction lead times and social and environmental concerns; - The main risks involved in nuclear energy projects; - The profitability study of the TUNDESAL project with the application of the Discounted Cash Flow Analysis; - The main financing sources for the project; - The financing schemes that can be used for project implementation and comparison between these schemes in terms of benefits generated, after covering project costs and repayment of lenders and investors; - The main actions to be done for making the project financially attractive in order to gain the confidence of investors and international financial institutions (optimal allocation of project risks and uncertainties, a suitable and flexible energy and water tariffs policy). Analysis has shown that in particular conditions of Tunisia, the most attractive financial scheme could be the 'project financing + leasing'. (authors)

  10. Systems integration processes for space nuclear electric propulsion systems

    International Nuclear Information System (INIS)

    Olsen, C.S.; Rice, J.W.; Stanley, M.L.

    1991-01-01

    The various components and subsystems that comprise a nuclear electric propulsion system should be developed and integrated so that each functions ideally and so that each is properly integrated with the other components and subsystems in the optimum way. This paper discusses how processes similar to those used in the development and intergration of the subsystems that comprise the Multimegawatt Space Nuclear Power System concepts can be and are being efficiently and effectively utilized for these purposes. The processes discussed include the development of functional and operational requirements at the system and subsystem level; the assessment of individual nuclear power supply and thruster concepts and their associated technologies; the conduct of systems integration efforts including the evaluation of the mission benefits for each system; the identification and resolution of concepts development, technology development, and systems integration feasibility issues; subsystem, system, and technology development and integration; and ground and flight subsystem and integrated system testing

  11. Strategic disruption of nuclear pores structure, integrity and barrier for nuclear apoptosis.

    Science.gov (United States)

    Shahin, Victor

    2017-08-01

    Apoptosis is a programmed cell death playing key roles in physiology and pathophysiology of multi cellular organisms. Its nuclear manifestation requires transmission of the death signals across the nuclear pore complexes (NPCs). In strategic sequential steps apoptotic factors disrupt NPCs structure, integrity and barrier ultimately leading to nuclear breakdown. The present review reflects on these steps. Copyright © 2017 Elsevier Ltd. All rights reserved.

  12. Development of integrated systems dynamics models for the sustainability assessment of nuclear energy

    International Nuclear Information System (INIS)

    Van Den Durpel, Luc; Yacout, Abdellatif; Wade, Dave

    2005-01-01

    Nuclear energy is increasingly perceived as an attractive mature energy generation technology that can deliver an answer to the worldwide increasing energy demand while respecting environmental concerns as well as contributing to a reduced dependence on fossil fuel. Advancing nuclear energy deployment demands an assessment of nuclear energy with respect to all sustainability dimensions allowing full stakeholder involvement in deciding on the role of nuclear energy as part of a sustainable energy generation mix in the future. Integrated system dynamics models of nuclear energy systems are interesting tools for such assessment studies allowing performing material flow accounting, environmental impact, economic competitiveness and socio-political analysis and this for time-evolving nuclear energy systems. No single tool today is capable of covering all the dimensions for such integrated assessment while various developments are ongoing in different places around the world to make such tools available in the nearby future. Argonne National Laboratory has embarked on such tool development since the year 2000 and has developed various tools among which the DANESS-code shall be described in some more detail in this paper. (author)

  13. National Options for a Sustainable Nuclear Energy System: MCDM Evaluation Using an Improved Integrated Weighting Approach

    Directory of Open Access Journals (Sweden)

    Ruxing Gao

    2017-12-01

    Full Text Available While the prospects look bright for nuclear energy development in China, no consensus about an optimum transitional path towards sustainability of the nuclear fuel cycle has been achieved. Herein, we present a preliminary study of decision making for China’s future nuclear energy systems, combined with a dynamic analysis model. In terms of sustainability assessment based on environmental, economic, and social considerations, we compared and ranked the four candidate options of nuclear fuel cycles combined with an integrated evaluation analysis using the Multi-Criteria Decision Making (MCDM method. An improved integrated weighting method was first applied in the nuclear fuel cycle evaluation study. This method synthesizes diverse subjective/objective weighting methods to evaluate conflicting criteria among the competing decision makers at different levels of expertise and experience. The results suggest that the fuel cycle option of direct recycling of spent fuel through fast reactors is the most competitive candidate, while the fuel cycle option of direct disposal of all spent fuel without recycling is the least attractive for China, from a sustainability perspective. In summary, this study provided a well-informed decision-making tool to support the development of national nuclear energy strategies.

  14. Integrated project risk management of nuclear power projects

    International Nuclear Information System (INIS)

    Wang Xiaohui; Xu Yuanhui

    2001-01-01

    The concept and the features of risks in nuclear power projects are introduced, and in terms of nuclear power projects' own features, the Nuclear Power Project Integrated Risk Management Model is presented. The identification, estimation, evaluation, response plan development, control of risks and the theoretical basis of risk management are discussed. The model has feedback and control functions in order to control and manage the risks dynamically

  15. Romanian network for structural integrity assessment of nuclear components

    International Nuclear Information System (INIS)

    Roth, Maria; Constantinescu, Dan Mihai; Brad, Sebastian; Ducu, Catalin

    2008-01-01

    Full text: Based of the Romanian option to develop and operate nuclear facilities, using as model the networks created at European level and taking into account the international importance of the structural integrity assessments for lifetime extension of the nuclear components, a national Project started since 2005 in the framework of the National Program 'Research of Excellence', Modulus I 2006-2008, managed by the Ministry of Education and Research. Entitled 'Integrated Network for Structural Integrity Monitoring of Critical Components in Nuclear Facilities', with the acronym RIMIS, the Project had two main objectives: - to elaborate a procedure applicable to the structural integrity assessment of the critical components used in Romanian nuclear facilities; - to integrate the national networking in a similar one, at European level, to enhance the scientific significance of Romanian R and D organizations as well as to increase the contribution to solving one of the major issue of the nuclear field. The paper aimed to present the activities performed in the Romanian institutes, involved in the Project, the final results obtained as part of the R and D activities, including experimental, theoretical and modeling ones regarding structural integrity assessment of nuclear components employed in CANDU type reactors. Also the activity carried out in the framework of the NULIFE network, created at European level of the FP6 Program and sustained by the RIMIS network will be described. (authors)

  16. Integrating cardiology for nuclear medicine physicians. A guide to nuclear medicine physicians

    International Nuclear Information System (INIS)

    Movahed, Assad; Gnanasegaran, Gopinath; Buscombe, John R.; Hall, Margaret

    2009-01-01

    Nuclear cardiology is no longer a medical discipline residing solely in nuclear medicine. This is the first book to recognize this fact by integrating in-depth information from both the clinical cardiology and nuclear cardiology literature, and acknowledging cardiovascular medicine as the fundamental knowledge base needed for the practice of nuclear cardiology. The book is designed to increase the practitioner's knowledge of cardiovascular medicine, thereby enhancing the quality of interpretations through improved accuracy and clinical relevance.The text is divided into four sections covering all major topics in cardiology and nuclear cardiology: -Basic Sciences and Cardiovascular Diseases; -Conventional Diagnostic Modalities; -Nuclear Cardiology; -Management of Cardiovascular Diseases. (orig.)

  17. Integrated approach to economical, reliable, safe nuclear power production

    International Nuclear Information System (INIS)

    1982-06-01

    An Integrated Approach to Economical, Reliable, Safe Nuclear Power Production is the latest evolution of a concept which originated with the Defense-in-Depth philosophy of the nuclear industry. As Defense-in-Depth provided a framework for viewing physical barriers and equipment redundancy, the Integrated Approach gives a framework for viewing nuclear power production in terms of functions and institutions. In the Integrated Approach, four plant Goals are defined (Normal Operation, Core and Plant Protection, Containment Integrity and Emergency Preparedness) with the attendant Functional and Institutional Classifications that support them. The Integrated Approach provides a systematic perspective that combines the economic objective of reliable power production with the safety objective of consistent, controlled plant operation

  18. Nuclear Fuel Cycle Analysis by Integrated AHP and TOPSIS Method Using an Equilibrium Model

    International Nuclear Information System (INIS)

    Yoon, S. R.; Choi, S. Y.; Koc, W. I.

    2015-01-01

    Determining whether to break away from domestic conflict surrounding nuclear power and step forward for public consensus can be identified by transparent policy making considering public acceptability. In this context, deriving the best suitable nuclear fuel cycle for Korea is the key task in current situation. Assessing nuclear fuel cycle is a multicriteria decision making problem dealing with multiple interconnected issues on efficiently using natural uranium resources, securing an environment friendliness to deal with waste, obtaining the public acceptance, ensuring peaceful uses of nuclear energy, maintaining economic competitiveness compared to other electricity sources, and assessing technical feasibility of advanced nuclear energy systems. This paper performed the integrated AHP and TOPSIS analysis on three nuclear fuel cycle options against 5 different criteria including U utilization, waste management, material attractiveness, economics, and technical feasibility. The fuel cycle options analyzed in this paper are three different fuel cycle options as follows: PWR-Once through cycle(PWR-OT), PWR-MOX cycle, Pyro- SFR cycle. These fuel cycles are most likely to be adopted in the foreseeable future. Analytic Hierarchy Process (AHP) and TOPSIS (Technique for Order of Preference by Similarity to Ideal Solution). The analyzed nuclear fuel cycle options include the once-through cycle, the PWR-MOX recycle, and the Pyro-SFR recycle

  19. Nuclear Fuel Cycle Analysis by Integrated AHP and TOPSIS Method Using an Equilibrium Model

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, S. R. [University of Science and Technology, Daejeon (Korea, Republic of); Choi, S. Y. [UNIST, Ulju (Korea, Republic of); Koc, W. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Determining whether to break away from domestic conflict surrounding nuclear power and step forward for public consensus can be identified by transparent policy making considering public acceptability. In this context, deriving the best suitable nuclear fuel cycle for Korea is the key task in current situation. Assessing nuclear fuel cycle is a multicriteria decision making problem dealing with multiple interconnected issues on efficiently using natural uranium resources, securing an environment friendliness to deal with waste, obtaining the public acceptance, ensuring peaceful uses of nuclear energy, maintaining economic competitiveness compared to other electricity sources, and assessing technical feasibility of advanced nuclear energy systems. This paper performed the integrated AHP and TOPSIS analysis on three nuclear fuel cycle options against 5 different criteria including U utilization, waste management, material attractiveness, economics, and technical feasibility. The fuel cycle options analyzed in this paper are three different fuel cycle options as follows: PWR-Once through cycle(PWR-OT), PWR-MOX cycle, Pyro- SFR cycle. These fuel cycles are most likely to be adopted in the foreseeable future. Analytic Hierarchy Process (AHP) and TOPSIS (Technique for Order of Preference by Similarity to Ideal Solution). The analyzed nuclear fuel cycle options include the once-through cycle, the PWR-MOX recycle, and the Pyro-SFR recycle.

  20. An integrated reliability management system for nuclear power plants

    International Nuclear Information System (INIS)

    Kimura, T.; Shimokawa, H.; Matsushima, H.

    1998-01-01

    The responsibility in the nuclear field of the Government, utilities and manufactures has increased in the past years due to the need of stable operation and great reliability of nuclear power plants. The need to improve the reliability is not only for the new plants but also for those now running. So, several measures have been taken to improve reliability. In particular, the plant manufactures have developed a reliability management system for each phase (planning, construction, maintenance and operation) and these have been integrated as a unified system. This integrated reliability management system for nuclear power plants contains information about plant performance, failures and incidents which have occurred in the plants. (author)

  1. Integrated project management information systems: the French nuclear industry experience

    International Nuclear Information System (INIS)

    Jacquin, J.-C.; Caupin, G.-M.

    1990-01-01

    The article discusses the desirability of integrated project management systems within the French nuclear power industry. Change in demand for nuclear generation facilities over the last two decades has necessitated a change of policy concerning organization, cost and planning within the industry. Large corporate systems can benefit from integrating equipment and bulk materials tracking. Project management for the nuclear industry will, in future, need to incorporate computer aided design tools and project management information systems data bases as well as equipment and planning data. (UK)

  2. Integrated project management information systems: the French nuclear industry experience

    Energy Technology Data Exchange (ETDEWEB)

    Jacquin, J.-C.; Caupin, G.-M.

    1990-03-01

    The article discusses the desirability of integrated project management systems within the French nuclear power industry. Change in demand for nuclear generation facilities over the last two decades has necessitated a change of policy concerning organization, cost and planning within the industry. Large corporate systems can benefit from integrating equipment and bulk materials tracking. Project management for the nuclear industry will, in future, need to incorporate computer aided design tools and project management information systems data bases as well as equipment and planning data. (UK).

  3. Nuclear Safeguards Infrastructure Development and Integration with Safety and Security

    International Nuclear Information System (INIS)

    Kovacic, Donald N.; Raffo-Caiado, Ana Claudia; McClelland-Kerr, John; Van sickle, Matthew; Bissani, Mo

    2009-01-01

    Faced with increasing global energy demands, many developing countries are considering building their first nuclear power plant. As a country embarks upon or expands its nuclear power program, it should consider how it will address the 19 issues laid out in the International Atomic Energy Agency (IAEA) document Milestones in Development of a National Infrastructure for Nuclear Power. One of those issues specifically addresses the international nonproliferation treaties and commitments and the implementation of safeguards to prevent diversion of nuclear material from peaceful purposes to nuclear weapons. Given the many legislative, economic, financial, environmental, operational, and other considerations preoccupying their planners, it is often difficult for countries to focus on developing the core strengths needed for effective safeguards implementation. Typically, these countries either have no nuclear experience or it is limited to the operation of research reactors used for radioisotope development and scientific research. As a result, their capacity to apply safeguards and manage fuel operations for a nuclear power program is limited. This paper argues that to address the safeguards issue effectively, a holistic approach must be taken to integrate safeguards with the other IAEA issues including safety and security - sometimes referred to as the '3S' concept. Taking a holistic approach means that a country must consider safeguards within the context of its entire nuclear power program, including operations best practices, safety, and security as well as integration with its larger nonproliferation commitments. The Department of Energy/National Nuclear Security Administration's International Nuclear Safeguards and Engagement Program (INSEP) has been involved in bilateral technical cooperation programs for over 20 years to promote nonproliferation and the peaceful uses of nuclear energy. INSEP is currently spearheading efforts to promote the development of

  4. Planning construction of integrative schedule management for nuclear power project

    International Nuclear Information System (INIS)

    Zeng Zhenglin; Wang Wenying; Peng Fei

    2012-01-01

    This paper introduces the planning construction of integrative schedule management for Nuclear Power Project. It details schedule management system and the requirement of schedulers and the mode of three schedule management flats. And analysis it combing with the implementation of construction water and all special schedules before FCD to further propose the improving and researching direction for the integrative schedule management. (authors)

  5. Structural integrity monitoring of critical components in nuclear facilities

    International Nuclear Information System (INIS)

    Roth, Maria; Constantinescu, Dan Mihai; Brad, Sebastian; Ducu, Catalin; Malinovschi, Viorel

    2007-01-01

    Full text: The paper presents the results obtained as part of the Project 'Integrated Network for Structural Integrity Monitoring of Critical Components in Nuclear Facilities', RIMIS, a research work underway within the framework of the Ministry of Education and Research Programme 'Research of Excellence'. The main objective of the Project is to constitute a network integrating the national R and D institutes with preoccupations in the structural integrity assessment of critical components in the nuclear facilities operating in Romania, in order to elaborate a specific procedure for this field. The degradation mechanisms of the structural materials used in the CANDU type reactors, operated by Unit 1 and Unit 2 at Cernavoda (pressure tubes, fuel elements sheaths, steam generator tubing) and in the nuclear facilities relating to reactors of this type as, for instance, the Hydrogen Isotopes Separation facility, will be investigated. The development of a flexible procedure will offer the opportunity to extend the applications to other structural materials used in the nuclear field and in the non-nuclear fields as well, in cooperation with other institutes involved in the developed network. The expected results of the project will allow the integration of the network developed at national level in the structures of similar networks operating within the EU, the enhancement of the scientific importance of Romanian R and D organizations as well as the increase of our country's contribution in solving the major issues of the nuclear field. (authors)

  6. Integrated system for nuclear installation control

    International Nuclear Information System (INIS)

    Mirchev, M.; Boyiklieva, R.; Peneva, A.

    2008-01-01

    A comparison between the international requirements and standards to an integrated management system is presented. The IAEA GS-R-3, BS PASS 99, ISO 9001, ISO 14001, BS OHSAS 18001 and ISO/IEC 27001 are reviewed and compared by the following aspects: definition and integration of processes; safety culture, risk analyses, satisfaction of the concerned parties, actions in case of discrepancy

  7. Double gated-integrator for shaping nuclear radiation detector signals

    International Nuclear Information System (INIS)

    Gal, J.

    2001-01-01

    A new shaper, the double gated-integrator, for shaping nuclear radiation detector signals is investigated both theoretically and experimentally. The double gated-integrator consists of a pre-filter and two cascaded gated integrators. Two kinds of pre-filters were considered: a rectangular one and an exponential one. The results of the theoretical calculation show that the best figure of demerit for the double gated-integrator with exponential pre-filter is 1.016. This means that its noise to signal ratio is only 1.6% worse than that it is for infinite cusp shaping. The practical realization of the exponential pre-filter and that of the double gated integrator, both in analogue and in digital way, is very simple. Therefore, the double gated-integrator with exponential pre-filter could be a promising solution for shaping nuclear radiation detector signals

  8. Task force for integral test of High Energy nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Oyama, Yukio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-11-01

    According to completion of the JENDL-High Energy file for neutron nuclear cross sections up to 50 MeV, a task force for integral test of high energy nuclear data was organized to discuss a guide line for integral test activities. A status of existing differential and integral experiments and how to perform such a test were discussed in the task force. Here the purpose and outline of the task force is explained with some future problems raised in discussion among the task member. (author)

  9. Integrated Nuclear-Renewable Energy Systems: Foundational Workshop Report

    Energy Technology Data Exchange (ETDEWEB)

    Bragg-Sitton, Shannon [Idaho National Lab. (INL), Idaho Falls, ID (United States); Boardman, Richard [Idaho National Lab. (INL), Idaho Falls, ID (United States); Ruth, Mark [National Renewable Energy Lab. (NREL), Golden, CO (United States); Zinaman, Owen [National Renewable Energy Lab. (NREL), Golden, CO (United States); Forsberg, Charles [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Collins, John [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-08-01

    The U.S. Department of Energy (DOE) recognizes the need to transform the energy infrastructure of the U.S. and elsewhere to systems that can drastically reduce environmental impacts in an efficient and economically viable manner while utilizing both hydrocarbon resources and clean energy generation sources. Thus, DOE is supporting research and development that could lead to more efficient utilization of clean energy generation sources, including renewable and nuclear options. A concept being advanced by the DOE Offices of Nuclear Energy (NE) and Energy Efficiency and Renewable Energy (EERE) is tighter coupling of nuclear and renewable energy sources in a manner that produces new energy currency for the combined electricity grid, industrial manufacturing, and the transportation energy sectors. This integration concept has been referred to as a “hybrid system” that is capable of providing the right type of energy, at the right time, in the right place. At the direction of DOE-NE and DOE-EERE leadership, project leads at Idaho National Laboratory (INL), National Renewable Energy Laboratory (NREL) and Massachusetts Institute of Technology (MIT) have identified and engaged stakeholders in discussing integrated energy systems that would optimize renewable and nuclear energy integration on a region-by-region basis. Subsequent work will entail conduct of technical, economic, environmental and socio-political evaluations of the leading integrated system options based on a set of criteria established with stakeholder input. The Foundational Workshop for Integrated Nuclear – Renewable Energy Systems was organized around the following objectives: 1. Identify and refine priority region-specific opportunities for integrated nuclear-renewable energy systems in the U.S.; 2. Select Figures of Merit (FOM) to rank and prioritize candidate systems; 3. Discuss enabling technology development needs; 4. Identify analysis requirements, capabilities and gaps to estimate FOM for

  10. Integrated Nuclear-Renewable Energy Systems: Foundational Workshop Report

    International Nuclear Information System (INIS)

    2014-01-01

    The U.S. Department of Energy (DOE) recognizes the need to transform the energy infrastructure of the U.S. and elsewhere to systems that can drastically reduce environmental impacts in an efficient and economically viable manner while utilizing both hydrocarbon resources and clean energy generation sources. Thus, DOE is supporting research and development that could lead to more efficient utilization of clean energy generation sources, including renewable and nuclear options. A concept being advanced by the DOE Offices of Nuclear Energy (NE) and Energy Efficiency and Renewable Energy (EERE) is tighter coupling of nuclear and renewable energy sources in a manner that produces new energy currency for the combined electricity grid, industrial manufacturing, and the transportation energy sectors. This integration concept has been referred to as a ''hybrid system'' that is capable of providing the right type of energy, at the right time, in the right place. At the direction of DOE-NE and DOE-EERE leadership, project leads at Idaho National Laboratory (INL), National Renewable Energy Laboratory (NREL) and Massachusetts Institute of Technology (MIT) have identified and engaged stakeholders in discussing integrated energy systems that would optimize renewable and nuclear energy integration on a region-by-region basis. Subsequent work will entail conduct of technical, economic, environmental and socio-political evaluations of the leading integrated system options based on a set of criteria established with stakeholder input. The Foundational Workshop for Integrated Nuclear - Renewable Energy Systems was organized around the following objectives: 1. Identify and refine priority region-specific opportunities for integrated nuclear-renewable energy systems in the U.S.; 2. Select Figures of Merit (FOM) to rank and prioritize candidate systems; 3. Discuss enabling technology development needs; 4. Identify analysis requirements, capabilities and gaps to

  11. Integrated Support Center for Nuclear Nonproliferation and Security

    International Nuclear Information System (INIS)

    Kimura, Naohito; Naoi, Yosuke

    2010-01-01

    In April 2010, at the Nuclear Security Summit, Japan demonstrated its commitment to the strengthening of nuclear non-proliferation and nuclear security and announced the establishment of the Integrated Comprehensive Support Center for Nuclear Non-proliferation and Nuclear Security in the Japan Atomic Energy Agency (JAEA), under the guidance and authority of the Ministry of Education, Culture, Sports and Science and Technology (MEXT), and in cooperation with other ministries. The goal of the Center is to strengthen nuclear non-proliferation and security in emerging nuclear power countries by sharing Japan's accumulated experiences in its peaceful use of nuclear energy. To achieve its goal, the Center serves three functions: (1) human resource and capacity building, (2) infrastructure development and technical assistance and (3) international coordination and cooperation. The Center will offer three types of training courses to strengthen human resources and capacity building in emerging nuclear power countries. In the Training Course on Nuclear Security, the participants will learn the design and evaluation process for physical protection and detection of and response to illegal or unauthorized acts related to nuclear materials. They will learn these issues not only through lectures and training but also using mockup facilities and virtual reality systems. Second, in the Training Course on Safeguards and State System of Accounting for and Control of Nuclear Material (SSAC), the Center will teach the experience of advanced safeguards activities in Japan for its full-scale nuclear fuel cycle facilities as a non-nuclear weapon state. The participants will learn the IAEA and national safeguards systems, the material accounting system and inspector activities. Third, in the Training on the International Nuclear Nonproliferation Framework, the participants will learn the international framework of nuclear non-proliferation including the IAEA safeguards system and

  12. Integrating Nuclear Energy to Oilfield Operations - Two Case Studies

    International Nuclear Information System (INIS)

    Robertson, Eric P.; Nelson, Lee O.; McKellar, Michael G.; Gandrik, Anastasia M.; Patterson, Mike W.

    2011-01-01

    Fossil fuel resources that require large energy inputs for extraction, such as the Canadian oil sands and the Green River oil shale resource in the western USA, could benefit from the use of nuclear power instead of power generated by natural gas combustion. This paper discusses the technical and economic aspects of integrating nuclear energy with oil sands operations and the development of oil shale resources. A high temperature gas reactor (HTGR) that produces heat in the form of high pressure steam (no electricity production) was selected as the nuclear power source for both fossil fuel resources. Both cases were based on 50,000 bbl/day output. The oil sands case was a steam-assisted, gravity-drainage (SAGD) operation located in the Canadian oil sands belt. The oil shale development was an in-situ oil shale retorting operation located in western Colorado, USA. The technical feasibility of the integrating nuclear power was assessed. The economic feasibility of each case was evaluated using a discounted cash flow, rate of return analysis. Integrating an HTGR to both the SAGD oil sands operation and the oil shale development was found to be technically feasible for both cases. In the oil sands case, integrating an HTGR eliminated natural gas combustion and associated CO2 emissions, although there were still some emissions associated with imported electrical power. In the in situ oil shale case, integrating an HTGR reduced CO2 emissions by 88% and increased natural gas production by 100%. Economic viabilities of both nuclear integrated cases were poorer than the non-nuclear-integrated cases when CO2 emissions were not taxed. However, taxing the CO2 emissions had a significant effect on the economics of the non-nuclear base cases, bringing them in line with the economics of the nuclear-integrated cases. As we move toward limiting CO2 emissions, integrating non-CO2-emitting energy sources to the development of energy-intense fossil fuel resources is becoming

  13. Nuclear safety culture and integrated risk management

    International Nuclear Information System (INIS)

    Joksimovich, V.; Orvis, D.D.

    1993-01-01

    A primary focus of nuclear safety is the prevention of large releases of radioactivity in the case of low-probability severe accidents. An analysis of the anatomy of nuclear (Chernobyl, Three Mile Island Unit 2) and nonnuclear (Challenger, Bhopal, Piper Alpha, etc.) severe accidents yields four broad categories of root causes: human (operating crew response), machine (design with its basic flaws), media (natural phenomena, operational considerations, political environment, commercial pressures, etc.)-providing triggering events, and management (basic organizational safety culture flaws). A strong management can minimize the contributions of humans, machines, and media to the risk arising from the operation of hazardous facilities. One way that management can have a powerful positive influence is through the establishment of a proper safety culture. The term safety culture is used as defined by the International Atomic Energy Agency's International Safety Advisory Group

  14. Structural integrity evaluation of nuclear piping cracket

    International Nuclear Information System (INIS)

    Cadiz Deleito, J.C.

    1985-01-01

    The methodology to evaluation of cracks in nuclear piping is exposed. Linear elastic fracture mechanic is used to prediction of growing crack and the net section collapse theory compared with acceptation criteria of both ASME III and ASME XI code. A case allowable under ASME XI criteria is analysed under ASME III requirements. Consideration must be given to local phenomenon in crack area and local stress evaluated and compared with ASME III acceptation criteria. (author)

  15. Technical Integration of Nuclear Hydrogen Production Technology

    International Nuclear Information System (INIS)

    Lee, Ki Young; Chang, J. H.; Park, J. K.

    2007-06-01

    These works focus on the development of attainment indices for nuclear hydrogen key technologies, the analysis of the hydrogen production process and the performance estimation for hydrogen production system, and the assessment of the nuclear hydrogen production economy. To estimate the attainments of the key technologies in progress with the performance goals of GIF, itemized are the attainment indices based on SRP published in VHTR R and D steering committee of Gen-IV. For assessing the degree of attainments in comparison with the final goals of VHTR technologies in progress of researches, subdivided are the prerequisite items conformed to the NHDD concepts established in a preconceptual design in 2005. The codes for analyzing the hydrogen production economy are developed for calculating the unit production cost of nuclear hydrogen. We developed basic R and D quality management methodology to meet design technology of VHTR's needs. By putting it in practice, we derived some problems and solutions. We distributed R and D QAP and Q and D QAM to each teams and these are in operation. Computer simulations are performed for estimating the thermal efficiency for the electrodialysis component likely to adapting as one of the hydrogen production system in Korea and EED-SI process known as the key components of the hydrogen production systems. Using the commercial codes, the process diagrams and the spread-sheets were produced for the Bunsen reaction process, Sulphuric Acid dissolution process and HI dissolution process, respectively, which are the key components composing of the SI process

  16. Nuclear plant engineering work and integrated management system

    International Nuclear Information System (INIS)

    Ohkubo, Y.; Obata, T.; Tanaka, K.

    1992-01-01

    The Application of computers to the design, engineering, manufacturing and construction works of nuclear power plants has greatly contributed to improvement of productivity and reliability in the nuclear power plants constructed by Mitsubishi Nuclear Group for more than ten years. However, in most cases, those systems have been developed separately and utilized independently in different computer software and hardware environments and have not been fully utilized to achieve high efficiency and reliability. In order to drastically increase the productivity and efficiency, development of NUclear power plant engineering Work and INtegrated manaGement System (NUWINGS) started in 1987 to unify and integrate various conventional and developing systems using the state-of-the-art computer technology. The NUWINGS is almost completed and is now applied to actual plant construction. (author)

  17. Structural integrity of materials in nuclear service: a bibliography

    International Nuclear Information System (INIS)

    Heddleson, F.A.

    1977-01-01

    This report contains 679 abstracts from the Nuclear Safety Information Center (NSIC) computer file dated 1973 through 1976 covering material properties with respect to structural integrity. All materials important to the nuclear industry (except concrete) are covered for mechanical properties, chemical properties, corrosion, fracture or failure, radiation damage, creep, cracking, and swelling. Keyword, author, and permuted-title indexes are included for the convenience of the user

  18. Structural integrity of materials in nuclear service: a bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Heddleson, F.A.

    1977-06-07

    This report contains 679 abstracts from the Nuclear Safety Information Center (NSIC) computer file dated 1973 through 1976 covering material properties with respect to structural integrity. All materials important to the nuclear industry (except concrete) are covered for mechanical properties, chemical properties, corrosion, fracture or failure, radiation damage, creep, cracking, and swelling. Keyword, author, and permuted-title indexes are included for the convenience of the user.

  19. Integrating the stabilization of nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Dalton, H.F. [Department of Energy, Washington, DC (United States)

    1996-05-01

    In response to Recommendation 94-1 of the Defense Nuclear Facilities Safety Board, the Department of Energy committed to stabilizing specific nuclear materials within 3 and 8 years. These efforts are underway. The Department has already repackaged the plutonium at Rocky Flats and metal turnings at Savannah River that had been in contact with plastic. As this effort proceeds, we begin to look at activities beyond stabilization and prepare for the final disposition of these materials. To describe the plutonium materials being stabilize, Figure 1 illustrates the quantities of plutonium in various forms that will be stabilized. Plutonium as metal comprises 8.5 metric tons. Plutonium oxide contains 5.5 metric tons of plutonium. Plutonium residues and solutions, together, contain 7 metric tons of plutonium. Figure 2 shows the quantity of plutonium-bearing material in these four categories. In this depiction, 200 metric tons of plutonium residues and 400 metric tons of solutions containing plutonium constitute most of the material in the stabilization program. So, it is not surprising that much of the work in stabilization is directed toward the residues and solutions, even though they contain less of the plutonium.

  20. Integrated network for structural integrity monitoring of critical components in nuclear facilities, RIMIS

    International Nuclear Information System (INIS)

    Roth, Maria; Constantinescu, Dan Mihai; Brad, Sebastian; Ducu, Catalin; Malinovschi, Viorel

    2008-01-01

    The round table aims to join specialists working in the research area of the Romanian R and D Institutes and Universities involved in structural integrity assessment of materials, especially those working in the nuclear field, together with the representatives of the end user, the Cernavoda NPP. This scientific event will offer the opportunity to disseminate the theoretical, experimental and modelling activities, carried out to date, in the framework of the National Program 'Research of Excellence', Module I 2006-2008, managed by the National Authority for Scientific Research. Entitled 'Integrated Network for Structural Integrity Monitoring of Critical Components in Nuclear Facilities, RIMIS, the project has two main objectives: 1. - to elaborate a procedure applicable to the structural integrity assessment of critical components used in Romanian nuclear facilities (CANDU type Reactor, Hydrogen Isotopes Separation installations); 2. - to integrate the national networking into a similar one of European level, and to enhance the scientific significance of Romanian R and D organisations as well as to increase the contribution in solving major issues of the nuclear field. The topics of the round table will be focused on: 1. Development of a Structural Integrity Assessment Methodology applicable to the nuclear facilities components; 2. Experimental investigation methods and procedures; 3. Numeric simulation of nuclear components behaviour; 4. Further activities to finalize the assessment procedure. Also participations and contributions to sustain the activity in the European Network NULIFE, FP6 will be discussed. (authors)

  1. Summary of a joint US-Japan study of potential approaches to reduce the attractiveness of various nuclear materials for use in a nuclear explosive device by a terrorist group

    Energy Technology Data Exchange (ETDEWEB)

    Bathke, C.G. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM (United States); Inoue, N.; Kuno, Y.; Mihara, T.; Sagara, H. [Japan Atomic Energy Agency, 4-49 Muramatsu, Tokai-mura, Naka-gun, Ibaraki 319-1184 (Japan); Ebbinghaus, B.B. [Lawrence Livermore National Laboratory, P.O. Box L-168, Livermore, CA 94551 (United States); Murphy, J.; Dalton, D. [National Nuclear Security Administration, Department of Energy, 1000 Independence Ave, SW, Washington, DC 20585 (United States); Nagayama, Y. [Ministry of Education, Culture, Sports, Science and Technology, 3-2-2 Kasumigaseki, Chiyoda-ku, Tokyo 100-8959 (Japan)

    2013-07-01

    This paper summarizes the results of a joint US-Japan study to establish a mutual understanding, through scientific-based study, of potential approaches to reduce the attractiveness of various nuclear materials for use in a terrorist nuclear explosive device (NED). 4 approaches that can reduce materials attractiveness with a very high degree of effectiveness are: -) diluting HEU with natural or depleted U to an enrichment of less than 10% U-235; -) storing Pu in nuclear fuel that is not man portable and with a dose rate greater or equal to 10 Gy/h at 1 m; -) storing Pu or HEU in heavy items, i.e. not transportable, provided the removal of the Pu or HEU from the item requires a purification/processing capability; and -) converting Pu and HEU to very dilute forms (such as wastes) that, without any security barriers, would require very long acquisition times to acquire a Category I quantity of Pu or of HEU. 2 approaches that can reduce materials attractiveness with a high degree of effectiveness are: -) converting HEU-fueled research reactors into LEU-fueled research reactors or dilute HEU with natural or depleted U to an enrichment of less than 20% U-235; -) converting U/Al reactor fuel into U/Si reactor fuel. Other approaches have been assessed as moderately or totally inefficient to reduce the attractiveness of nuclear materials.

  2. Modeling fabrication of nuclear components: An integrative approach

    Energy Technology Data Exchange (ETDEWEB)

    Hench, K.W.

    1996-08-01

    Reduction of the nuclear weapons stockpile and the general downsizing of the nuclear weapons complex has presented challenges for Los Alamos. One is to design an optimized fabrication facility to manufacture nuclear weapon primary components in an environment of intense regulation and shrinking budgets. This dissertation presents an integrative two-stage approach to modeling the casting operation for fabrication of nuclear weapon primary components. The first stage optimizes personnel radiation exposure for the casting operation layout by modeling the operation as a facility layout problem formulated as a quadratic assignment problem. The solution procedure uses an evolutionary heuristic technique. The best solutions to the layout problem are used as input to the second stage - a simulation model that assesses the impact of competing layouts on operational performance. The focus of the simulation model is to determine the layout that minimizes personnel radiation exposures and nuclear material movement, and maximizes the utilization of capacity for finished units.

  3. Integrative structure and functional anatomy of a nuclear pore complex

    Science.gov (United States)

    Kim, Seung Joong; Fernandez-Martinez, Javier; Nudelman, Ilona; Shi, Yi; Zhang, Wenzhu; Raveh, Barak; Herricks, Thurston; Slaughter, Brian D.; Hogan, Joanna A.; Upla, Paula; Chemmama, Ilan E.; Pellarin, Riccardo; Echeverria, Ignacia; Shivaraju, Manjunatha; Chaudhury, Azraa S.; Wang, Junjie; Williams, Rosemary; Unruh, Jay R.; Greenberg, Charles H.; Jacobs, Erica Y.; Yu, Zhiheng; de La Cruz, M. Jason; Mironska, Roxana; Stokes, David L.; Aitchison, John D.; Jarrold, Martin F.; Gerton, Jennifer L.; Ludtke, Steven J.; Akey, Christopher W.; Chait, Brian T.; Sali, Andrej; Rout, Michael P.

    2018-03-01

    Nuclear pore complexes play central roles as gatekeepers of RNA and protein transport between the cytoplasm and nucleoplasm. However, their large size and dynamic nature have impeded a full structural and functional elucidation. Here we determined the structure of the entire 552-protein nuclear pore complex of the yeast Saccharomyces cerevisiae at sub-nanometre precision by satisfying a wide range of data relating to the molecular arrangement of its constituents. The nuclear pore complex incorporates sturdy diagonal columns and connector cables attached to these columns, imbuing the structure with strength and flexibility. These cables also tie together all other elements of the nuclear pore complex, including membrane-interacting regions, outer rings and RNA-processing platforms. Inwardly directed anchors create a high density of transport factor-docking Phe-Gly repeats in the central channel, organized into distinct functional units. This integrative structure enables us to rationalize the architecture, transport mechanism and evolutionary origins of the nuclear pore complex.

  4. On the benefits of an integrated nuclear complex for Nevada

    International Nuclear Information System (INIS)

    Blink, J.A.; Halsey, W.G.

    1994-01-01

    An integrated nuclear complex is proposed for location at the Nevada Test Site. In addition to solving the nuclear waste disposal problem, this complex would tremendously enhance the southern Nevada economy, and it would provide low cost electricity to each resident and business in the affected counties. Nuclear industry and the national economy would benefit because the complex would demonstrate the new generation of safer nuclear power plants and revitalize the industry. Many spin-offs of the complex would be possible, including research into nuclear fusion and a world class medical facility for southern Nevada. For such a complex to become a reality, the cycle of distrust between the federal government and the State of Nevada must be broken. The paper concludes with a discussion of implementation through a public process led by state officials and culminating in a voter referendum

  5. Integrative structure and functional anatomy of a nuclear pore complex.

    Science.gov (United States)

    Kim, Seung Joong; Fernandez-Martinez, Javier; Nudelman, Ilona; Shi, Yi; Zhang, Wenzhu; Raveh, Barak; Herricks, Thurston; Slaughter, Brian D; Hogan, Joanna A; Upla, Paula; Chemmama, Ilan E; Pellarin, Riccardo; Echeverria, Ignacia; Shivaraju, Manjunatha; Chaudhury, Azraa S; Wang, Junjie; Williams, Rosemary; Unruh, Jay R; Greenberg, Charles H; Jacobs, Erica Y; Yu, Zhiheng; de la Cruz, M Jason; Mironska, Roxana; Stokes, David L; Aitchison, John D; Jarrold, Martin F; Gerton, Jennifer L; Ludtke, Steven J; Akey, Christopher W; Chait, Brian T; Sali, Andrej; Rout, Michael P

    2018-03-22

    Nuclear pore complexes play central roles as gatekeepers of RNA and protein transport between the cytoplasm and nucleoplasm. However, their large size and dynamic nature have impeded a full structural and functional elucidation. Here we determined the structure of the entire 552-protein nuclear pore complex of the yeast Saccharomyces cerevisiae at sub-nanometre precision by satisfying a wide range of data relating to the molecular arrangement of its constituents. The nuclear pore complex incorporates sturdy diagonal columns and connector cables attached to these columns, imbuing the structure with strength and flexibility. These cables also tie together all other elements of the nuclear pore complex, including membrane-interacting regions, outer rings and RNA-processing platforms. Inwardly directed anchors create a high density of transport factor-docking Phe-Gly repeats in the central channel, organized into distinct functional units. This integrative structure enables us to rationalize the architecture, transport mechanism and evolutionary origins of the nuclear pore complex.

  6. The disposition of nuclear waste: an integrated international approach

    International Nuclear Information System (INIS)

    Waltar, A.E.

    2001-01-01

    This paper proposes the establishment of a new, globally integrated approach for dealing with spent nuclear fuel (SNF), high-level waste, and plutonium supplies. The end product is envisioned to be a new global agency (tentatively called the International Nuclear Waste Authority, or INWA), which would have the authority to establish and enforce all nuclear waste disposal standards and subsequently execute all financial arrangements appropriate for obtaining full-scale global implementation. We suggest the IAEA as the logical existing organization to facilitate generating the structure for the INWA. (author)

  7. Development of integrated nuclear data utilization system for innovative reactors

    International Nuclear Information System (INIS)

    Naoki, Yamano; Masayuki, Igashira; Akira, Hasegawa; Kiyoshi, Kato

    2005-01-01

    An integrated nuclear data utilization system has been developing for innovative nuclear energy systems such as innovative reactors and accelerator-driven systems. The system has been constructed as a modular code system, which consists of a managing system and two subsystems. The management system named CONDUCT controls system resource management of the PC Linux server and the user authentication through Internet access. A subsystem is the nuclear data search and plotting subsystem based on a SPES engine developed by Hokkaido University. Nuclear data such as EXFOR, JENDL-3.3, ENDF/B-VI and JEFF-3.1 can be searched and plotted in the subsystem. The other is the nuclear data processing and utilization subsystem, which is able to handle JENDL-3.3, ENDF/B-VI and JEFF-3.1 to generate point-wise and group cross sections in several formats, and perform various criticality and shielding benchmarks for verification of nuclear data and validation of design methods for innovative reactors. This paper presents an overview of the integrated nuclear data utilization system, describes the progress of the system development to examine the operability of the user interface and discuss specifications of the two subsystems. (authors)

  8. Implementation of integrated safeguards at Nuclear Fuel Plant Pitesti, Romania

    International Nuclear Information System (INIS)

    Olaru, Vasilica; Ivana, Tiberiu; Epure, Gheorghe

    2010-01-01

    The nuclear activity in ROMANIA was for many years under Traditional Safeguards (TS) and has developed in good conditions this type of nuclear safeguards. Now, the opportunity exists to improve the performance and quality of the safeguards activity and increase the accountancy and control of nuclear material by passing to Integrated Safeguards (IS). The legal framework is the Law 100/2000 for ratification of the Protocol between Romania and International Atomic Energy Agency (IAEA), additional to the Agreement between the Socialist Republic of Romania Government and IAEA related to safeguards as part of the Treaty on the non-proliferation of nuclear weapons published in the Official Gazette no. 3/31 January 1970, and the Additional Protocol content published in the Official Gazette no. 295/ 29.06.2000. The first discussion about Integrated Safeguards (IS) between Nuclear Fuel Plant (NFP) representatives and IAEA inspectors was in June 2005. In Feb. 2007 an IAEA mission visited NFP and established the main steps for implementing the IS. There were visited the storages, technological flow, and was reviewed the disposal times for different nuclear materials, the applied chemical analysis, measuring methods, weighting method and elaborating procedure of the documents and lists. At that time the IAEA and NFP representatives established the main points for starting the IS at NFP: performing the Short Notice Random Inspections (SNRI); communication of the days established for SNRI for each year; communication of the estimated deliveries and shipments for first quarter and then for the rest of the year: daily mail box declaration (DD) with respect to the deposit time for several nuclear materials i.e. advance notification (AN) for each nuclear material transfer (shipments and receipts), others. At 01 June 2007 Romania has passed officially to Integrated Safeguards and NFP (WRMD) has taken all measures to implement this objective. (authors)

  9. Problems of attracting nuclear energy resources in order to provide economical and rational consumption of fossil fuels

    International Nuclear Information System (INIS)

    Nazarov, E.K.; Nikitin, A.T.; Ponomarev-Stepnoy, N.N.; Protsenko, A.N.; Stolyarevskii, A.Ya.; Doroshenko, N.A.

    1990-01-01

    The solution of problems related to increasing costs of fossil fuels and application of nuclear energy in the industrial sector could be the development and commercialization of high temperature nuclear reactors, as the majority of power consuming industrial processes demand that the temperature of heat carrier generated to be in the range from 900-1000 deg. C. In the Soviet Union the strategy adopted for solving energy supply problems was named 'nuclear-hydrogen power engineering and technologies'. Based on analytic research and taking into account the present state of the art, the new alternative energy sources, e.g. nuclear ones, should be introduced into the industry by the following steps: development and mastering of stable operation of high-temperature nuclear reactors; search of rational technical solutions for heat discharge from nuclear reactors; utilisation of meet the power demand of existing production plants; complete substitution of organic raw materials burned now with nuclear energy; review the conditions and development of organizational and engineering solutions acceptable for implementing the nuclear energy in commercial processes

  10. Problems of attracting nuclear energy resources in order to provide economical and rational consumption of fossil fuels

    Energy Technology Data Exchange (ETDEWEB)

    Nazarov, E K; Nikitin, A T; Ponomarev-Stepnoy, N N; Protsenko, A N; Stolyarevskii, A Ya; Doroshenko, N A [State Institute of Nitrogen Industry, Moscow (USSR); [I.V. Kurchatov Institute of Atomic Energy, Moscow (USSR)

    1990-07-01

    The solution of problems related to increasing costs of fossil fuels and application of nuclear energy in the industrial sector could be the development and commercialization of high temperature nuclear reactors, as the majority of power consuming industrial processes demand that the temperature of heat carrier generated to be in the range from 900-1000 deg. C. In the Soviet Union the strategy adopted for solving energy supply problems was named 'nuclear-hydrogen power engineering and technologies'. Based on analytic research and taking into account the present state of the art, the new alternative energy sources, e.g. nuclear ones, should be introduced into the industry by the following steps: development and mastering of stable operation of high-temperature nuclear reactors; search of rational technical solutions for heat discharge from nuclear reactors; utilisation of meet the power demand of existing production plants; complete substitution of organic raw materials burned now with nuclear energy; review the conditions and development of organizational and engineering solutions acceptable for implementing the nuclear energy in commercial processes.

  11. Monte Carlo evaluation of path integral for the nuclear shell model

    International Nuclear Information System (INIS)

    Lang, G.H.

    1993-01-01

    The authors present a path-integral formulation of the nuclear shell model using auxillary fields; the path-integral is evaluated by Monte Carlo methods. The method scales favorably with valence-nucleon number and shell-model basis: full-basis calculations are demonstrated up to the rare-earth region, which cannot be treated by other methods. Observables are calculated for the ground state and in a thermal ensemble. Dynamical correlations are obtained, from which strength functions are extracted through the Maximum Entropy method. Examples in the s-d shell, where exact diagonalization can be carried out, compared well with exact results. The open-quotes sign problemclose quotes generic to quantum Monte Carlo calculations is found to be absent in the attractive pairing-plus-multipole interactions. The formulation is general for interacting fermion systems and is well suited for parallel computation. The authors have implemented it on the Intel Touchstone Delta System, achieving better than 99% parallelization

  12. Altruists Attract

    Directory of Open Access Journals (Sweden)

    Daniel Farrelly

    2007-04-01

    Full Text Available Explaining human cooperation continues to present a challenge because it goes beyond what is predicted by established theories of kinship and reciprocal altruism. Little attention has been paid to the sexual selection hypothesis that proposes that cooperation can act as a display that attracts mates. The costs of cooperating are then offset not by kinship or reciprocation but by increased mating success. Here we present results from a series of experiments which show that, as predicted by the sexual selection hypothesis, people preferentially direct cooperative behavior towards more attractive members of the opposite sex. Furthermore, cooperative behavior increases the perceived attractiveness of the cooperator. Economically costly behaviors can therefore bring benefits through mate choice and sexual selection should be regarded as an evolutionary mechanism capable of promoting cooperation.

  13. Development of nuclear fuel for integrated reactor

    Energy Technology Data Exchange (ETDEWEB)

    Song, Kee Nam; Kim, H. K.; Kang, H. S.; Yoon, K. H.; Chun, T. H.; In, W. K.; Oh, D. S.; Kim, D. W.; Woo, Y. M

    1999-04-01

    The spacer grid assembly which provides both lateral and vertical support for the fuel rods and also provides a flow channel between the fuel rods to afford the heat transfer from the fuel pellet into the coolant in a reactor, is one of the major structural components of nuclear fuel for LWR. Therefore, the spacer grid assembly is a highly ranked component when the improvement of hardware is pursued for promoting fuel performance. Main objective of this project is to develop the inherent spacer grid assembly and to research relevant technologies on the spacer grid assembly. And, the UO{sub 2}-based SMART fuel is preliminarily designed for the 330MWt class SMART, which is planned to produce heat as well as electricity. Results from this project are listed as follows. 1. Three kinds of spacer grid candidates have been invented and applied for domestic and US patents. In addition, the demo SG(3x3 array) were fabricated, which the mechanical/structural test was carried out with. 2. The mechanical/structural technologies related to the spacer grid development are studied and relevant test requirements were established. 3. Preliminary design data of the UO{sub 2}-based SMART fuel have been produced. The structural characteristics of several components such as the top/bottom end piece and the holddown spring assembly were analysed by consulting the numerical method.

  14. Development of nuclear fuel for integrated reactor

    International Nuclear Information System (INIS)

    Song, Kee Nam; Kim, H. K.; Kang, H. S.; Yoon, K. H.; Chun, T. H.; In, W. K.; Oh, D. S.; Kim, D. W.; Woo, Y. M.

    1999-04-01

    The spacer grid assembly which provides both lateral and vertical support for the fuel rods and also provides a flow channel between the fuel rods to afford the heat transfer from the fuel pellet into the coolant in a reactor, is one of the major structural components of nuclear fuel for LWR. Therefore, the spacer grid assembly is a highly ranked component when the improvement of hardware is pursued for promoting fuel performance. Main objective of this project is to develop the inherent spacer grid assembly and to research relevant technologies on the spacer grid assembly. And, the UO 2 -based SMART fuel is preliminarily designed for the 330MWt class SMART, which is planned to produce heat as well as electricity. Results from this project are listed as follows. 1. Three kinds of spacer grid candidates have been invented and applied for domestic and US patents. In addition, the demo SG(3x3 array) were fabricated, which the mechanical/structural test was carried out with. 2. The mechanical/structural technologies related to the spacer grid development are studied and relevant test requirements were established. 3. Preliminary design data of the UO 2 -based SMART fuel have been produced. The structural characteristics of several components such as the top/bottom end piece and the holddown spring assembly were analysed by consulting the numerical method

  15. Integral design small nuclear power plant UNITHERM

    International Nuclear Information System (INIS)

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

    1995-01-01

    The need to erect expensive energy transmission lines to these places demands to use independent local energy sources. Therefore, a reasonable alternative to the plants fired fossil fuel, mostly hydrocarbon fuel, may come from the nuclear power plants (NPP) of relatively small capacity which are nonattended, shipped to the site by large-assembled modules and completely withdrawable from the site during decommissioning. Application of NPPs for power and heat supply may prove to be cost-efficient and rather positive from social and ecological point of view. UNITHERM NPP belongs to such energy sources and may be used for heat and power supply. Heat can be provided both as hot water and superheated steam. The consumers are able to specify heat/energy supply ratio. NPP design provides for independent energy supply to the consumers and the possibility to disconnect each of them without disruption of operation of the others. Thermal hydraulic diagram of UNITHERM NPP provides for the use of three interconnected, process circuits. The consumers of thermal energy (turbogenerator unit and boilers of the central heating unit) are arranged in the last circuit

  16. Integrated analysis of oxide nuclear fuel sintering

    International Nuclear Information System (INIS)

    Baranov, V.; Kuzmin, R.; Tenishev, A.; Timoshin, I.; Khlunov, A.; Ivanov, A.; Petrov, I.

    2011-01-01

    Dilatometric and thermal-gravimetric investigations have been carried out for the sintering process of oxide nuclear fuel in gaseous Ar - 8% H 2 atmosphere at temperatures up to 1600 0 C. The pressed compacts were fabricated under real production conditions of the OAO MSZ with application of two different technologies, so called 'dry' and 'wet' technologies. Effects of the grain size growth after the heating to different temperatures were observed. In order to investigate the effects produced by rate of heating on properties of sintered fuel pellets, the heating rates were varied from 1 to 8 0 C per minute. Time of isothermal overexposure at maximal temperature (1600 0 C) was about 8 hours. Real production conditions were imitated. The results showed that the sintering process of the fuel pellets produced by two technologies differs. The samples sintered under different heating rates were studied with application of scanning electronic microscopy analysis for determination of mean grain size. A simulation of heating profile for industrial furnaces was performed to reduce the beam cycles and estimate the effects of variation of the isothermal overexposure temperatures. Based on this data, an optimization of the sintering conditions was performed in operations terms of OAO MSZ. (authors)

  17. Nuclear thermionic power plant integration problems

    International Nuclear Information System (INIS)

    Fraas, A.P.

    1967-02-01

    The numerous boundary conditions to be met in preparing a well proportioned, properly integrated design for a thermionic cell reactor are discussed with the emphasis on materials and fabrication problems. Pertinent experience with fuel elements, tube header sheets, electric heaters, and pressure vessels is cited to highlight key limitations that have been encountered in structurally similar equipment. A reference design is presented to indicate how one might attempt to satisfy all of the many boundary conditions. The study indicates that it will be difficult to get a reactor core power density greater than about 35 w/cm 3 and that, while it is possible to minimize the ill effects of failures within individual cells by employing series-parallel connections, the study further indicates that there is inherently a high probability of leaks and electrical shorts and arcs within the reactor so that it is doubtful that good reliability can be obtained

  18. Performance tests for integral reactor nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, Dong-Seong; Yim, Jeong-Sik; Lee, Chong-Tak; Kim, Han-Soo; Koo, Yang-Hyun; Lee, Byung-Ho; Cheon, Jin-Sik; Oh, Je-Yong

    2006-02-15

    An integral type reactor SMART plans to utilize metallic Zr-U fuel which is Zr-based alloy with 34{approx}38 wt% U. In order to verify the technologies for the design and manufacturing of the fuel and get a license, performance tests were carried out. Experimental Fuel Assembly (EFA) manufactured in KAERI is being successfully irradiated in the MIR reactor of RIAR from September 4 2004, and it has achieved burnup of 0.21 g/cc as of January 25 2006. Thermal properties of irradiated Zr-U fuel were measured. Up to the phase transformation temperature, thermal diffusivity increased linearly in proportion to temperature. However its dependence on the burnup was not significant. RIA tests with 4 unirradiated Zr-U fuel rods were performed in Kurchatov Institute to establish a safety criterion. In the case of the un-irradiated Zr-U fuel, the energy deposition during the control rod ejection accident should be less than 172 cal/g to prevent the failure accompanying fuel fragmentation and dispersal. Finally the irradiation tests of fuel rods have been performed at HANARO. The HITE-2 test was successfully completed up to a burnup of 0.31 g/cc. The HITE-3 test began in February 2004 and will be continued up to a target burnup of 0.6 g/cc.

  19. Model integration and the economics of nuclear power

    International Nuclear Information System (INIS)

    Lundgren, S.

    1985-01-01

    The author proposes and applies a specific approach to model integration, i.e. the merger of two or several independently developed models. The approach is intended for integrations of activity analysis sector models and applied general equilibrium models. Model integration makes it possible to extend the range of applicability of applied general equilibrium models by exploiting the information contained in sector models. It also makes it possible to evaluate the validity of the partial equilibrium analyses in which sector models often are employed. The proposed approach is used to integrate a sector model of electricity and heat production with a general equilibrium model of the Swedish economy. Both models have been constructed within the research programme. The author uses the integrated model to look at two issues concerning the role of nuclear power on the Swedish electricity market: What are the likely consequences of a nuclear power discontinuation and how does the nuclear power investment programme of the 1970's and the early 1980's compare with a socially efficient one. (Author)

  20. 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.

  1. Building an integrated nuclear engineering and nuclear science human resources pipeline at the Idaho National Engineering and Environmental Laboratory

    International Nuclear Information System (INIS)

    Sneed, A.; Sikorski, B.; Lineberry, M.; Jolly, J.

    2004-01-01

    Full text: In 2002, the US Department of Energy (US DOE) transferred sponsorship of the INEEL and ANL-W to the DOE Office of Nuclear Energy, Science and Technology and designated the INEEL and ANL-W as the nation's lead laboratories for nuclear reactor and nuclear fuel cycle research and development. This transfer acknowledged the laboratories' history, infrastructure, expertise and commitment to collaborate broadly in order to fulfill its assigned role as the nation's center for nuclear energy research and development. Key to this role is the availability of well-educated and trained nuclear engineers, professionals from other disciplines of engineering, nuclear scientists, and others with advanced degrees in supporting disciplines such as physics, chemistry, and math. In 2005 the INEEL and ANL-W will be combined into the Idaho National Laboratory (INL). One of US DOE's objectives for the INL will be for it to take a strong role in the revitalization of nuclear engineering and nuclear science education in the US. Responding to this objective for the INL and the national need to rejuvenate nuclear engineering and nuclear science research and education, ISU, University of Idaho (UI), Boise State University, the INEEL, and ANL-W are all supporting a new Institute of Nuclear Science and Engineering (INSE), initially proposed by and to be administered by ISU. The Institute will rely on the resources of both universities and the INL to create a US center for reactor and fuel cycle research to development and attract outstanding faculty and students to Idaho and to the INL. The Institute and other university based education development efforts represent only one component of a viable Human Resources Pipeline from university to leading edge laboratory researcher. Another critical component is the successful integration of new graduates into the laboratory research environment, the transfer of knowledge from senior researchers, and the development of these individuals into

  2. Fatal attraction

    DEFF Research Database (Denmark)

    Jensen, Kim Ebensgaard

    2012-01-01

    The purpose of this paper is two-fold. Firstly, it presents an argument for usage-based inheritance models over complete inheritance models in construction grammar. It is argued that, with the principle of inductive language learning as their foundation, usage-based inheritance models allow...... for redundancies and incongruities in construction networks which enables linguists to take into account details of language use, which would otherwise not be facilitated in complete inheritance models. Secondly, making use of the method of collostructional analysis, the article offers a corpus-based description...... of the use of the Danish ihjel-construction which accounts for patterns of attraction of construction-verb attraction, patterns of productivity, and various types of subconstructions, including item- and item-class-based ones and metaphorical extensions. The description of the ihjel-construction should also...

  3. Integrated Nuclear Infrastructure Review (INIR) Missions: The First Six Years

    International Nuclear Information System (INIS)

    2015-12-01

    IAEA Integrated Nuclear Infrastructure Review (INIR) missions are designed to assist Member States in evaluating the status of their national infrastructure for the introduction of a nuclear power programme. INIR missions are conducted upon request from the Member State. Each INIR mission is coordinated and led by the IAEA and conducted by a team of IAEA staff and international experts drawn from Member States which have experience in different aspects of developing and deploying nuclear infrastructure. INIR missions cover the 19 infrastructure issues described in Milestones in the Development of a National Infrastructure for Nuclear Power, IAEA Nuclear Energy Series No. NG-G-3.1, published in 2007 and revised in 2015, and the assessment is based on an analysis of a self-evaluation report prepared by the Member State, a review of the documents it provides and interviews with its key officials. Phase 1 INIR missions evaluate the status of the infrastructure to achieve Milestone 1 (Ready to make a knowledgeable commitment to a nuclear power programme). Phase 2 INIR missions evaluate the status of the infrastructure to achieve Milestone 2 (Ready to invite bids/negotiate a contract for the first nuclear power plant). From 2009 to 2014, 14 IAEA INIR missions and follow-ups were conducted in States embarking on a nuclear power programme and one State expanding its programme. During this time, considerable experience was gained by the IAEA on the conduct of INIR missions, and this feedback has been used to continually improve the overall INIR methodology. The INIR methodology has thus evolved and is far more comprehensive today than in 2009. Despite the limited number of INIR missions conducted, some common findings were identified in Member States embarking on nuclear power programmes. This publication summarizes the results of the missions and highlights the most significant areas in which recommendations were made

  4. Toshiba integrated information system for design of nuclear power plants

    International Nuclear Information System (INIS)

    Abe, Yoko; Kawamura, Hirobumi; Sasaki, Norio; Takasaka, Kiyoshi

    1993-01-01

    TOSHIBA aims to secure safety, increase reliability and improve efficiency through the engineering for nuclear power plants and has been introducing Computer Aided Engineering (CAE). Up to the present, TOSHIBA has been developing computer systems which support each field of design and applying them to the design of nuclear power plants. The new design support system has been developed to integrate each of those systems in order to realize much greater improvement in accuracy and increase of reliability in design using state-of-the-art computer technology

  5. INTEGRATION OF FACILITY MODELING CAPABILITIES FOR NUCLEAR NONPROLIFERATION ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    Gorensek, M.; Hamm, L.; Garcia, H.; Burr, T.; Coles, G.; Edmunds, T.; Garrett, A.; Krebs, J.; Kress, R.; Lamberti, V.; Schoenwald, D.; Tzanos, C.; Ward, R.

    2011-07-18

    Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

  6. Integration of facility modeling capabilities for nuclear nonproliferation analysis

    International Nuclear Information System (INIS)

    Garcia, Humberto; Burr, Tom; Coles, Garill A.; Edmunds, Thomas A.; Garrett, Alfred; Gorensek, Maximilian; Hamm, Luther; Krebs, John; Kress, Reid L.; Lamberti, Vincent; Schoenwald, David; Tzanos, Constantine P.; Ward, Richard C.

    2012-01-01

    Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

  7. Integration Of Facility Modeling Capabilities For Nuclear Nonproliferation Analysis

    International Nuclear Information System (INIS)

    Gorensek, M.; Hamm, L.; Garcia, H.; Burr, T.; Coles, G.; Edmunds, T.; Garrett, A.; Krebs, J.; Kress, R.; Lamberti, V.; Schoenwald, D.; Tzanos, C.; Ward, R.

    2011-01-01

    Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

  8. Nuclear electric propulsion: An integral part of NASA's nuclear propulsion project

    International Nuclear Information System (INIS)

    Stone, J.R.

    1992-01-01

    NASA has initiated a technology program to establish the readiness of nuclear propulsion technology for the Space Exploration Initiative (SEI). This program was initiated with a very modest effort identified with nuclear thermal propulsion (NTP); however, nuclear electric propulsion (NEP) is also an integral part of this program and builds upon NASA's Base Research and Technology Program in power and electric propulsion as well as the SP-100 space nuclear power program. Although the Synthesis Group On America's SEI has identified NEP only as an option for cargo missions, recent studies conducted by NASA-Lewis show that NEP offers the potential for early manned Mars missions as well. Lower power NEP is also of current interest for outer planetary robotic missions. Current plans are reviewed for the overall nuclear propulsion project, with emphasis on NEP and those elements of NTP program which have synergism with NEP

  9. An integrated approach to site selection for nuclear power plants

    International Nuclear Information System (INIS)

    Hassan, E.M.A.

    1975-01-01

    A method of analysing and evaluating the large number of factors influencing site selection is proposed, which can interrelate these factors and associated problems in an integrated way and at the same time establish a technique for site evaluation. The objective is to develop an integrated programme that illustrates the complexity and dynamic interrelationships of the various factors to develop an improved understanding of the functions and objectives of siting nuclear power plants and would aim finally at the development of an effective procedure and technique for site evaluation and/or comparative evaluation for making rational site-selection decisions. (author)

  10. Development of an integrated cost model for nuclear plant decommissioning

    International Nuclear Information System (INIS)

    Amos, G.; Roy, R.

    2003-01-01

    A need for an integrated cost estimating tool for nuclear decommissioning and associated waste processing and storage facilities for Intermediate Level Waste (ILW) was defined during the authors recent MSc studies. In order to close the defined gap a prototype tool was developed using logically derived CER's and cost driver variables. The challenge in developing this was to be able to produce a model that could produce realistic cost estimates from the limited levels of historic cost data that was available for analysis. The model is an excel based tool supported by 3 point risk estimating output and is suitable for producing estimates for strategic or optional cost estimates (±30%) early in the conceptual stage of a decommissioning project. The model was validated using minimal numbers of case studies supported by expert opinion discussion. The model provides an enhanced approach for integrated decommissioning estimates which will be produced concurrently with strategic options analysis on a nuclear site

  11. Study concerning an integrated radiation monitoring systems for nuclear facilities

    International Nuclear Information System (INIS)

    Oprea, I.; Oprea, M.; Stoica, M.; Cerga, V.; Pirvu, V; Badea, E.

    1996-01-01

    This paper presents an integrated radiation monitoring system designed to assess the effects of nuclear accidents and to provide a basis for making right decisions and countermeasures in order to reduce health damages. The system implies a number of stationary monitoring equipment, data processing unit and a communication network. The system meets the demands of efficiency and reliability, providing the needed tools to easily create programs able to process simple input data filling the information management system. (author). 10 refs

  12. Safety evaluation of socket weld integrity in nuclear piping

    International Nuclear Information System (INIS)

    Choi, Y.H.; Kim, H.J.; Choi, S.Y.; Kim, Y.J.; Kim, Y.J.

    2004-01-01

    The purposes of this paper are to evaluate the integrity of socket weld in nuclear piping and prepare the technical basis for a new guideline on radiographic testing (RT) for the socket weld. Recently, the integrity of the socket weld is regarded as a safety concern in nuclear power plants because lots of failures and leaks have been reported in the socket weld. The root causes of the socket weld failure are known as unanticipated loadings such as vibration or thermal fatigue and improper weld joint during construction. The ASME Code sec. III requires 1/16 inch gap between the pipe and fitting in the socket weld. Many failure cases, however, showed that the gap requirement was not satisfied. The Code also requires magnetic particle examination (MT) or liquid penetration examination (PT) on the socket weld, but not radiographic examination (RT). It means that it is not easy to examine the 1/16 inch gap in the socket weld by using the NDE methods currently required in the Code. In this paper, the effects of the requirements in the ASME Code sec. III on the socket weld integrity were evaluated by using finite element method. The crack behavior in the socket weld was also investigated under vibration event in nuclear power plants. The results showed that the socket weld was very susceptible to the vibration if the requirements in ASME Code were not satisfied. The constraint between the pipe and fitting due to the contact significantly affects the integrity of the socket weld. This paper also suggests a new guideline on the RT for the socket weld during construction stage in nuclear power plants. (orig.)

  13. Integral tightness measurements at the Paks-1 nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Taubner, R.; Techy, Z. (Villamosenergiaipari Kutato Intezet, Budapest (Hungary))

    1983-01-01

    The containment system experiments of the Paks-1 nuclear reactor are described. The integrated tightness measurements of the hermetic system were completed in 1982. The principles and methods and the evaluation of the results of the measurements are discussed. Some features of the filtration characteristics are demonstrated using relative values and a method enabling the description of the physical contents of the characteristics by flow technical functions is outlined.

  14. Summarisation of construction and commissioning experience for nuclear power integrated test facility

    International Nuclear Information System (INIS)

    Xiao Zejun; Jia Dounan; Jiang Xulun; Chen Bingde

    2003-01-01

    Since the foundation of Nuclear Power Institute of China, it has successively designed various engineering experimental facilities, and constructed nuclear power experimental research base, and accumulated rich construction experiences of nuclear power integrated test facility. The author presents experience on design, construction and commissioning of nuclear power integrated test facility

  15. Problems of attracting nuclear energy resources in order to provide economical and rational consumption of fossil fuels

    International Nuclear Information System (INIS)

    Nazarov, E.K.; Nikitin, A.T.; Ponomarev-Stepnoy, N.N.; Protsenko, A.N.; Stolyarevskii, A.Ya.; Doroshenko, N.A.

    1990-01-01

    Depletion of fossil fuel resources and the gradual increase in cost of their extraction and transportation to the places of their consumption put forward into a line of the most urgent tasks the problem of rational and economical utilization of fuel and energy resources, as well as introduction of new energy sources into various sectors of the national economy. The nuclear energy sources which are widely spread in power engineering have not yet been used to a proper extent in the sectors of industrial technologies and residential space heating, which are the most energy consuming sectors in the national economy. The most effective way of solving this problem can be the development and commercialization of high temperature nuclear reactors, as the majority of power consuming industrial processes and those involved in chemico-thermal systems of distant heat transmission demand the temperature of a heat carrier generated by nuclear reactors and assimilated by the above processes to be in the range from 900 0 to 1000 0 C. (author)

  16. Foundational development of an advanced nuclear reactor integrated safety code

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  17. Foundational development of an advanced nuclear reactor integrated safety code.

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-02-01

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

  18. Defense Nuclear Material Stewardship Integrated Inventory Information Management System (IIIMS).

    Energy Technology Data Exchange (ETDEWEB)

    Aas, Christopher A.; Lenhart, James E.; Bray, Olin H.; Witcher, Christina Jenkin

    2004-11-01

    Sandia National Laboratories was tasked with developing the Defense Nuclear Material Stewardship Integrated Inventory Information Management System (IIIMS) with the sponsorship of NA-125.3 and the concurrence of DOE/NNSA field and area offices. The purpose of IIIMS was to modernize nuclear materials management information systems at the enterprise level. Projects over the course of several years attempted to spearhead this modernization. The scope of IIIMS was broken into broad enterprise-oriented materials management and materials forecasting. The IIIMS prototype was developed to allow multiple participating user groups to explore nuclear material requirements and needs in detail. The purpose of material forecasting was to determine nuclear material availability over a 10 to 15 year period in light of the dynamic nature of nuclear materials management. Formal DOE Directives (requirements) were needed to direct IIIMS efforts but were never issued and the project has been halted. When restarted, duplicating or re-engineering the activities from 1999 to 2003 is unnecessary, and in fact future initiatives can build on previous work. IIIMS requirements should be structured to provide high confidence that discrepancies are detected, and classified information is not divulged. Enterprise-wide materials management systems maintained by the military can be used as overall models to base IIIMS implementation concepts upon.

  19. Integration of facility modeling capabilities for nuclear nonproliferation analysis

    International Nuclear Information System (INIS)

    Burr, Tom; Gorensek, M.B.; Krebs, John; Kress, Reid L.; Lamberti, Vincent; Schoenwald, David; Ward, Richard C.

    2012-01-01

    Developing automated methods for data collection and analysis that can facilitate nuclearnonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facilitymodeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facilitymodeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facilitymodelingcapabilities and illustrates how they could be integrated and utilized for nonproliferationanalysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facilitymodeling tools. After considering a representative sampling of key facilitymodelingcapabilities, the proposed integration framework is illustrated with several examples.

  20. Human nucleoporins promote HIV-1 docking at the nuclear pore, nuclear import and integration.

    Directory of Open Access Journals (Sweden)

    Francesca Di Nunzio

    Full Text Available The nuclear pore complex (NPC mediates nucleo-cytoplasmic transport of macromolecules and is an obligatory point of passage and functional bottleneck in the replication of some viruses. The Human Immunodeficiency Virus (HIV has evolved the required mechanisms for active nuclear import of its genome through the NPC. However the mechanisms by which the NPC allows or even assists HIV translocation are still unknown. We investigated the involvement of four key nucleoporins in HIV-1 docking, translocation, and integration: Nup358/RanBP2, Nup214/CAN, Nup98 and Nup153. Although all induce defects in infectivity when depleted, only Nup153 actually showed any evidence of participating in HIV-1 translocation through the nuclear pore. We show that Nup358/RanBP2 mediates docking of HIV-1 cores on NPC cytoplasmic filaments by interacting with the cores and that the C-terminus of Nup358/RanBP2 comprising a cyclophilin-homology domain contributes to binding. We also show that Nup214/CAN and Nup98 play no role in HIV-1 nuclear import per se: Nup214/CAN plays an indirect role in infectivity read-outs through its effect on mRNA export, while the reduction of expression of Nup98 shows a slight reduction in proviral integration. Our work shows the involvement of nucleoporins in diverse and functionally separable steps of HIV infection and nuclear import.

  1. Maintenance management for nuclear power plant 'Integrated valve maintenance'

    International Nuclear Information System (INIS)

    Gerner, P.; Zanner, G.

    2001-01-01

    The deregulation of Europe's power market does force many utilities, and especially nuclear power plant operators, to introduce extensive cost-cutting measures in order to be able to compete within this new environment. The optimization of plant outages provides considerable potential for raising plant availability but can also lower operating costs by reducing e.g. expenditure on maintenance. Siemens Nuclear Power GmbH, in cooperation with plant operators, is currently implementing new and improved service concepts which can have a major effect on the way in which maintenance will be performed in the future. Innovative service packages for maintenance in nuclear power plants are available which can be used to perform a time- and cost-effective maintenance. The concepts encompass optimization of the overall sequence from planning in advance to the individual measures including reduction of the scope of maintenance activities, identification of cost cutting potential and bundling of maintenance activities. The main features of these maintenance activities are illustrated here using the examples of outage planning and integrated valve maintenance. In nuclear power plants approx. 5000 valves are periodically preventively, condition-based or breakdown-based maintained. Because of this large number of valves to be maintained a high potential of improvements and cost reductions can be achieved by performing an optimized, cost-effective maintenance based on innovative methods and tools. Siemens Nuclear Power GmbH has developed and qualified such tools which allow to reduce service costs while maintaining high standards of safety and availability. By changing from preventive to predictive (condition-based) maintenance - the number of valves to be maintained may be reduced considerably. The predictive maintenance is based on the Siemens Nuclear Power GmbH diagnostic and evaluation method (ADAM). ADAM is used to monitor the operability of valves by analytical verification of

  2. Nuclear Application Programs Development and Integration for a Simulator

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun-Joon; Lee, Tae-Woo [KEPCO Engineering and Construction Co., Deajeon (Korea, Republic of)

    2016-10-15

    KEPCO E and C participated in the NAPS (Nuclear Application Programs) development project for BNPP (Barakah Nuclear Power Plant) simulator. The 3KEY MASTER™ was adopted for this project, which is comprehensive simulation platform software developed by WSC (Western Services Corporation) for the development, and control of simulation software. The NAPS based on actual BNPP project was modified in order to meet specific requirements for nuclear power plant simulators. Considerations regarding software design for BNPP simulator and interfaces between the 3KM platform and application programs are discussed. The repeatability is one of functional requirements for nuclear power plant simulators. In order to migrate software from actual plants to simulators, software functions for storing and retrieving plant conditions and program variables should be implemented. In addition, software structures need to be redesigned to meet the repeatability, and source codes developed for actual plants would have to be optimized to reflect simulator’s characteristics as well. The synchronization is an important consideration to integrate external application programs into the 3KM simulator.

  3. Study on system integration of robots operated in nuclear fusion facility and nuclear power plant facilities

    International Nuclear Information System (INIS)

    Oka, Kiyoshi

    2004-07-01

    A present robot is required to apply to many fields such as amusement, welfare and protection against disasters. The are however only limited numbers of the robots, which can work under the actual conditions as a robot system. It is caused by the following reasons: (1) the robot system cannot be realized by the only collection of the elemental technologies, (2) the performance of the robot is determined by that of the integrated system composed of the complicated elements with many functions, and (3) the respective elements have to be optimized in the integrated robot system with a well balance among them, through their examination, adjustment and improvement. Therefore, the system integration of the robot composed of a large number of elements is the most critical issue to realize the robot system for actual use. In the present paper, I describe the necessary approaches and elemental technologies to solve the issues on the system integration of the typical robot systems for maintenance in the nuclear fusion facility and rescue in the accident of the nuclear power plant facilities. These robots work under the intense radiation condition and restricted space in place of human. In particular, I propose a new approach to realize the system integration of the robot for actual use from the viewpoints of not only the environment and working conditions but also the restructure and optimization of the required elemental technologies with a well balance in the robot system. Based on the above approach, I have a contribution to realize the robot systems working under the actual conditions for maintenance in the nuclear fusion facility and rescue in the accident of the nuclear power plant facilities. (author)

  4. Nuclear power plant Angra integrated enterprise management system

    International Nuclear Information System (INIS)

    Andrade, Ronaldo Barata de

    2009-01-01

    The characteristics and peculiarities of the Nuclear Power Plant ANGRA 3 enterprise, amongst which its technical complexity, the size of the project and of the supplies of goods and services contracted for for the Brazilian and foreign scopes, the variety of contractors and participants involved in the implementation, associated with the need of integrated management of all the activities of the enterprise, requires the setting of standardized criteria and procedures to be adopted by the enterprise Project Management Team and by all involved ELETRONUCLEAR (ETN) Units, Suppliers and Contractors for Brazilian and foreign goods and services for the execution of the activities related to overall enterprise planning. These criteria and procedures aim at covering the five Project Management Process Groups: Initiating Process Group, Planning Process Group, Execution Process Group, Monitoring and Controlling Process Group and Closing Process Group. For the ANGRA 3 enterprise, ETN developed the Integrated Enterprise Management System - INTEGRA, being the software 'Primavera Enterprise Project Management' a fundamental part of this system. The aim of this paper is to describe the main concepts involving the ANGRA 3 enterprise management, and the integration between the processes, including all disciplines in all phases of the enterprise life cycle, such as: Nuclear and Environmental Licensing, Infrastructure, National and Foreign Engineering, National and Import Supplies, Civil Works, Electromechanical Erection, Commissioning. (author)

  5. Integrated neutron/gamma-ray portal monitors for nuclear safeguards

    International Nuclear Information System (INIS)

    Fehlau, P.E.

    1994-01-01

    Radiation monitoring is one nuclear-safeguards measure used to protect against the theft of special nuclear materials (SNM) by pedestrians departing from SNM access areas. The integrated neutron/gamma-ray portal monitor is an ideal radiation monitor for the task when the SNM is plutonium. It achieves high sensitivity for detecting both bare and shielded plutonium by combining two types of radiation detector. One type is a neutron-chamber detector, comprising a large, hollow, neutron moderator that contains a single thermal-neutron proportional counter. The entrance wall of each chamber is thin to admit slow neutrons from plutonium contained in a moderating shield, while the other walls are thick to moderate fast neutrons from bare or lead-shielded plutonium so that they can be detected. The other type of detector is a plastic scintillator that is primarily for detecting gamma rays from small amounts of unshielded plutonium. The two types of detector are easily integrated by making scintillators part of the thick back wall of each neutron chamber or by inserting them into each chamber void. The authors compared the influence of the two methods of integration on detecting neutrons and gamma rays, and they examined the effectiveness of other design factors and the methods for signal detection as well

  6. Integrity assessment of stationary blade ring for nuclear power plant

    International Nuclear Information System (INIS)

    Park, Jung Yong; Chung, Yong Keun; Park, Jong Jin; Kang, Yong Ho

    2004-01-01

    The inner side between HP stationary blades in no.1 turbine of nuclear power plant A is damaged by the FAC(Flow Assisted Corrosion) which is exposed to moisture. For many years the inner side is repaired by welding the damaged part, however, the FAC continues to deteriorate the original material of the welded blade ring. In this study, we have two stages to verify the integrity of stationary blade ring in nuclear power plant A. In the stage I, replication of blade ring is performed to survey the microstructure of blade ring. In the stage II, the stress analysis of blade ring is performed to verify the structural safety of blade ring. Throughout the two stages analysis of blade ring, the stationary blade ring had remained undamaged

  7. Rethinking the Future Grid: Integrated Nuclear Renewable Energy Systems: Preprint

    Energy Technology Data Exchange (ETDEWEB)

    Bragg-Sitton, S. M.; Boardman, R.; Ruth, M.; Zinaman, O.; Forsberg, C.

    2015-01-01

    The U.S. DOE is supporting research and development that could lead to more efficient utilization of clean energy generation sources, including renewable and nuclear options, to meet both grid demand and thermal energy needs in the industrial sector. One concept under consideration by the DOE-NE and DOE-EERE is tighter coupling of nuclear and renewable energy sources in a manner that better optimizes energy use for the combined electricity, industrial manufacturing, and transportation sectors. This integration concept has been referred to as a 'hybrid system' that is capable of apportioning thermal and electrical energy to first meet the grid demand (with appropriate power conversion systems), then utilizing excess thermal and, in some cases, electrical energy to drive a process that results in an additional product.

  8. RETHINKING THE FUTURE GRID: INTEGRATED NUCLEAR-RENEWABLE ENERGY SYSTEMS

    Energy Technology Data Exchange (ETDEWEB)

    S.M. Bragg-Sitton; R. Boardman

    2014-12-01

    The 2013 electricity generation mix in the United States consisted of ~13% renewables (hydropower, wind, solar, geothermal), 19% nuclear, 27% natural gas, and 39% coal. In the 2011 State of the Union Address, President Obama set a clean energy goal for the nation: “By 2035, 80 percent of America’s electricity will come from clean energy sources. Some folks want wind and solar. Others want nuclear, clean coal and natural gas. To meet this goal we will need them all.” The U.S. Department of Energy (DOE) Offices of Nuclear Energy (NE) and Energy Efficiency and Renewable Energy (EERE) recognize that “all of the above” means that we are called to best utilize all available clean energy sources. To meet the stated environmental goals for electricity generation and for the broader energy sector, there is a need to transform the energy infrastructure of the U.S. and elsewhere. New energy systems must be capable of significantly reducing environmental impacts in an efficient and economically viable manner while utilizing both hydrocarbon resources and clean energy generation sources. The U.S. DOE is supporting research and development that could lead to more efficient utilization of clean energy generation sources, including renewable and nuclear options, to meet both grid demand and thermal energy needs in the industrial sector. A concept being advanced by the DOE-NE and DOE-EERE is tighter coupling of nuclear and renewable energy sources in a manner that better optimizes energy use for the combined electricity, industrial manufacturing, and the transportation sectors. This integration concept has been referred to as a “hybrid system” that is capable of apportioning thermal and electrical energy to first meet the grid demand (with appropriate power conversion systems), then utilizing excess thermal and, in some cases, electrical energy to drive a process that results in an additional product. For the purposes of the present work, the hybrid system would

  9. Integrated multi-scale modelling and simulation of nuclear fuels

    International Nuclear Information System (INIS)

    Valot, C.; Bertolus, M.; Masson, R.; Malerba, L.; Rachid, J.; Besmann, T.; Phillpot, S.; Stan, M.

    2015-01-01

    This chapter aims at discussing the objectives, implementation and integration of multi-scale modelling approaches applied to nuclear fuel materials. We will first show why the multi-scale modelling approach is required, due to the nature of the materials and by the phenomena involved under irradiation. We will then present the multiple facets of multi-scale modelling approach, while giving some recommendations with regard to its application. We will also show that multi-scale modelling must be coupled with appropriate multi-scale experiments and characterisation. Finally, we will demonstrate how multi-scale modelling can contribute to solving technology issues. (authors)

  10. Bibliography of integral charged particle nuclear data. Archival edition

    International Nuclear Information System (INIS)

    Burrows, T.W.; Dempsey, P.

    1980-03-01

    This is the fourth annual edition of the National Nuclear Data Center charged-particle bibliography. This edition is cumulative and supersedes the previous editions. The bibliography's primary aims are to satisfy the need for a concise and comprehensive index of integral charged-particle cross section data and to provide an index of charged-particle data compiled in the international exchange format, EXFOR. This part of the publication deals with isotope production; references are ordered by mass of the nuclide produced. The present publication is an archival volume; future publications will be cumulative supplements to this edition

  11. Computer-integrated design and information management for nuclear projects

    International Nuclear Information System (INIS)

    Gonzalez, A.; Martin-Guirado, L.; Nebrera, F.

    1987-01-01

    Over the past seven years, Empresarios Agrupados has been developing a comprehensive, computer-integrated system to perform the majority of the engineering, design, procurement and construction management activities in nuclear, fossil-fired as well as hydro power plant projects. This system, which is already in a production environment, comprises a large number of computer programs and data bases designed using a modular approach. Each software module, dedicated to meeting the needs of a particular design group or project discipline, facilitates the performance of functional tasks characteristic of the power plant engineering process

  12. Nuclear methods - an integral part of the NBS certification program

    International Nuclear Information System (INIS)

    Gills, T.E.

    1984-01-01

    Within the past twenty years, new techniques and methods have emerged in response to new technologies that are based upon the performance of high-purity and well-characterized materials. The National Bureau of Standards, through its Standard Reference Materials (SRM's) Program, provides standards in the form of many of these materials to ensure accuracy and the compatibility of measurements throughout the US and the world. These standards, defined by the National Bureau of Standards as Standard Reference Materials (SRMs), are developed by using state-of-the-art methods and procedures for both preparation and analysis. Nuclear methods-activation analysis constitute an integral part of that analysis process

  13. Integrating design and purchasing [in nuclear engineering] with Ingecad

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    Ingecad was developed by the Ingevision division of Framatome to overcome deficiencies in traditional computer-aided design. It was developed for nuclear power project engineering around the principle of the shared management of a common database, thus making it possible to integrate several engineering disciplines. The multiuser database is managed and accessed by the different application softwares, corresponding to particular aspects of the engineering task: electrical and process control schematics; plant piping design; pressurized equipment design etc. The use of a common database ensures coherence between the different engineering disciplines, particularly between the process engineering, the plant layout design, the piping, and the instrumentation and control engineering. (author)

  14. Bibliography of integral charged particle nuclear data. Archival edition

    International Nuclear Information System (INIS)

    Burrows, T.W.; Dempsey, P.

    1980-03-01

    This is the fourth annual edition of the National Nuclear Data Center charged-particle bibliography. This edition is cumulative and supersedes the previous editions. The bibliography's primary aims are to satisfy the need for a concise and comprehensive index of integral charged-particle cross section data and to provide an index of charged-particle data compiled in the international exchange format. References in this Part are by target for the various incident charged particles (in order of increasing A). The present publication is an archival volume; future publications will be cumulative supplements to this edition

  15. Multinational enterprises in regional innovation systems: attraction factors and integration mechanisms = Les entreprises multinationales dans les systèmes régionaux d'innovation: facteurs d'attraction et mécanismes d'intégration

    OpenAIRE

    Baier, Elisabeth

    2011-01-01

    This work explains mutual influences between MNEs and regional innovation networks during innovation processes. An analytical framework integrates different research perspectives and allows analysing the integration of MNEs in regional innovation networks through the identification of attraction factors and interaction mechanisms between regional and organisational learning.

  16. Functional integrals for nuclear many-particle systems

    International Nuclear Information System (INIS)

    Lobanov, Yu.Yu.

    1996-04-01

    The new method for computation of the physical characteristics of quantum systems with many degrees of freedom is described. This method is based on the representation of the matrix element of the evolution operator in Euclidean metrics in a form of the functional integral with a certain measure in the corresponding space and on the use of approximation formulas which we constructed for this kind of integrals. The method does not require preliminary discretization of space and time and allows to use the deterministic algorithms. This approach proved to have important advantages over the other known methods, including the higher efficiency of computations. Examples of application of the method to the numerical study of some potential nuclear models as well as comparison of results with the experimental data and with the values obtained by the other authors are presented. (author). 25 refs, 1 fig., 2 tabs

  17. Socket weld integrity in nuclear piping under fatigue loading condition

    International Nuclear Information System (INIS)

    Choi, Young Hwan; Choi, Sun Yeong

    2007-01-01

    The purpose of this paper is to evaluate the integrity of socket weld in nuclear piping under the fatigue loading. The integrity of socket weld is regarded as a safety concern in nuclear power plants because many failures have been world-widely reported in the socket weld. Recently, socket weld failures in the chemical and volume control system (CVCS) and the primary sampling system (PSS) were reported in Korean nuclear power plants. The root causes of the socket weld failures were known as the fatigue due to the pressure and/or temperature loading transients and the vibration during the plant operation. The ASME boiler and pressure vessel (B and PV) Code Sec. III requires 1/16 in. gap between the pipe and fitting in the socket weld with the weld leg size of 1.09 x t 1 , where t 1 is the pipe wall thickness. Many failure cases, however, showed that the gap requirement was not satisfied. In addition, industry has demanded the reduction of weld leg size from 1.09 x t 1 to 0.75 x t 1 . In this paper, the socket weld integrity under the fatigue loading was evaluated using three-dimensional finite element analysis considering the requirements in the ASME Code. Three types of loading conditions such as the deflection due to vibration, the pressure transient ranging from P = 0 to 15.51 MPa, and the thermal transient ranging from T = 25 to 288 deg. C were considered. The results are as follows; (1) the socket weld is susceptible to the vibration where the vibration levels exceed the requirement in the ASME operation and maintenance (OM) code. (2) The effect of pressure or temperature transient load on socket weld in CVCS and PSS is not significant owing to the low frequency of transient during plant operation. (3) 'No gap' is very risky to the socket weld integrity for the systems having the vibration condition to exceed the requirement specified in the ASME OM Code and/or the transient loading condition from P = 0 and T = 25 deg. C to P = 15.51 MPa and T = 288 deg. C. (4

  18. Structural integrity evaluation of PWR nuclear reactor pressure vessels

    International Nuclear Information System (INIS)

    Cruz, Julio R.B.; Mattar Neto, Miguel

    1999-01-01

    The reactor pressure vessel (RPV) is the most important structural component of a PWR nuclear power plant. It contains the reactor core and is the main component of the primary system pressure boundary, the system responsible for removing the heat generated by the nuclear reactions. It is considered not replaceable and, therefore, its lifetime is a key element to define the plant life as a whole. Three critical issues related to the reliability of the RPV structural integrity come out by reason of the radiation damage imposed to the vessel material during operation. These issues concern the definition of pressure versus temperature limits for reactor heatup and cooldown, pressurized thermal shock evaluation and assessment of reactor vessels with low upper shelf Charpy impact energy levels. This work aims to present the major aspects related to these topics. The requirements for preventing fracture of the RPV are reviewed as well as the available technology for assessing the safety margins. For each mentioned problem, the several steps for structural integrity evaluation are described and the analysis methods are discussed. (author)

  19. Fossil fuel savings, carbon emission reduction and economic attractiveness of medium-scale integrated biomass gasification combined cycle cogeneration plants

    Directory of Open Access Journals (Sweden)

    Kalina Jacek

    2012-01-01

    Full Text Available The paper theoretically investigates the system made up of fluidized bed gasifier, SGT-100 gas turbine and bottoming steam cycle. Different configurations of the combined cycle plant are examined. A comparison is made between systems with producer gas (PG and natural gas (NG fired turbine. Supplementary firing of the PG in a heat recovery steam generator is also taken into account. The performance of the gas turbine is investigated using in-house built Engineering Equation Solver model. Steam cycle is modeled using GateCycleTM simulation software. The results are compared in terms of electric energy generation efficiency, CO2 emission and fossil fuel energy savings. Finally there is performed an economic analysis of a sample project. The results show relatively good performance in the both alternative configurations at different rates of supplementary firing. Furthermore, positive values of economic indices were obtained. [Acknowledgements. This work was carried out within the frame of research project no. N N513 004036, titled: Analysis and optimization of distributed energy conversion plants integrated with gasification of biomass. The project is financed by the Polish Ministry of Science.

  20. Evaluation of integrity of radiation sources of nuclear gauges

    International Nuclear Information System (INIS)

    Torohate, Wiclif Francisco

    2016-01-01

    Nuclear equipment meters are mainly used in the industry in quality control and process control. The principle of operation consists in a shielded radioactive source together with a radiation detector such that the radiation interacts with the material to be analyzed before reaching the detector, providing real time data. Can be as their fixed and mobile mobility, the unique properties of ionizing radiation are used in three basic modes, transmission, backscatter or dispersion or induced (reactive). With the advancement and technological modernization in the world, the demand for nuclear gauges becomes increasingly larger. Currently in Brazil there are about 465 process control plants and 21 portable systems and Mozambique about 45 facilities using nuclear gauges. This font registration is done through a process called source inventory that allows also to know the category of the source, the danger or risk to human health that the source offers. The handling of this equipment requires personnel, certified, skilled and well trained in radiation protection area in accordance with the requirements of the various CNEN Rules. Due to the presence of radioactive source and because these devices are used by workers risk because there external radiation. In this context, we made the smear test in two fixed meters from the IRD industry laboratory, which determines the integrity of the source package, mandatory item in periodic integrity testing of the radiation source of this type of device. A set of procedures is made for its implementation as an evaluation of the radiological risk by radiological survey. It was intended to contribute to the learning handling and safe use of these meters. (author)

  1. A High Integrity Can Design for Degraded Nuclear Fuel

    International Nuclear Information System (INIS)

    Holmes, P.A.

    1999-01-01

    A high integrity can (HIC), designed to meet the ASME Boiler and Pressure Vessel Code (Section III, Div. 3, static conditions) is proposed for the interim storage and repository disposal of Department of Energy (DOE) spent nuclear fuel. The HIC will be approximately 5 3/8 inches (134.38mm) in outside diameter with 1/4 inch (6.35mm) thick walls, and have a removable lid with a metallic seal that is capable of being welded shut. The opening of the can is approximately 4 3/8 inches (111.13mm). The HIC is primarily designed to contain items in the DOE SNF inventory that do not meet acceptance standards for direct disposal in a geologic repository. This includes fuel in the form of particulate dusts, sectioned pieces of fuel, core rubble, melted or degraded (non-intact) fuel elements, unclad uranium alloys, metallurgical specimens, and chemically reactive fuel components. The HIC is intended to act as a substitute cladding for the spent nuclear fuel, further isolate problematic materials, provide a long-term corrosion barrier, and add an extra internal pressure barrier to the waste package. The HIC will also delay potential fission product release and maintain geometry control for extended periods of time. For the entire disposal package to be licensed by the Nuclear Regulatory Commission, a HIC must effectively eliminate the disposal problems associated with problem SNF including the release of radioactive and/or reactive material and over pressurization of the HIC due to chemical reactions within the can. Two HICs were analyzed to envelop a range of can lengths between 42 and 101 inches. Using Abacus software, the HIC's were analyzed for end, side, and corner drops. Hastelloy C-22 was chosen based upon structural integrity, corrosion resistance, and neutron adsorption properties

  2. Integrated System Modeling for Nuclear Thermal Propulsion (NTP)

    Science.gov (United States)

    Ryan, Stephen W.; Borowski, Stanley K.

    2014-01-01

    Nuclear thermal propulsion (NTP) has long been identified as a key enabling technology for space exploration beyond LEO. From Wernher Von Braun's early concepts for crewed missions to the Moon and Mars to the current Mars Design Reference Architecture (DRA) 5.0 and recent lunar and asteroid mission studies, the high thrust and specific impulse of NTP opens up possibilities such as reusability that are just not feasible with competing approaches. Although NTP technology was proven in the Rover / NERVA projects in the early days of the space program, an integrated spacecraft using NTP has never been developed. Such a spacecraft presents a challenging multidisciplinary systems integration problem. The disciplines that must come together include not only nuclear propulsion and power, but also thermal management, power, structures, orbital dynamics, etc. Some of this integration logic was incorporated into a vehicle sizing code developed at NASA's Glenn Research Center (GRC) in the early 1990s called MOMMA, and later into an Excel-based tool called SIZER. Recently, a team at GRC has developed an open source framework for solving Multidisciplinary Design, Analysis and Optimization (MDAO) problems called OpenMDAO. A modeling approach is presented that builds on previous work in NTP vehicle sizing and mission analysis by making use of the OpenMDAO framework to enable modular and reconfigurable representations of various NTP vehicle configurations and mission scenarios. This approach is currently applied to vehicle sizing, but is extensible to optimization of vehicle and mission designs. The key features of the code will be discussed and examples of NTP transfer vehicles and candidate missions will be presented.

  3. Integration of radiation monitoring for nuclear emergency response teams

    Energy Technology Data Exchange (ETDEWEB)

    Olsen, J T; Thompson, N Y [Royal Military Coll. of Canada, Kingston, ON (Canada)

    1994-12-31

    The Canadian Forces have established Nuclear Emergency Response Teams to cope with potential radiation accidents. Previously, only gamma and high-energy beta radiation could be detected. Recently, new radiation sampling, detecting, and analytical equipment has been bought, including air samplers, beta counters, high-purity germanium gamma detectors, and multi-channel analyzers together with Gamma Vision Software to analyze gamma spectra. The purpose of the present study is to propose a way to use the new equipment, to analyze the results from the gamma and beta detectors, and to integrate the results into a format for decision making. Integration is achieved through the creation of a computer program, Radiation Integration Program (RIP). This program analyzes gross beta counts, and uses them to estimate danger to the thyroid. As well the results from Gamma Vision are converted from Bq to dose rate for several parts of the body. Overall gamma results affecting the thyroid are compared to the beta results to verify the initial estimations.

  4. Modern integrated environmental monitoring and processing systems for nuclear facilities

    International Nuclear Information System (INIS)

    Oprea, I.

    2000-01-01

    The continuous activity to survey and monitor releases and the current radiation levels in the vicinity of a nuclear object is essential for person and environment protection. Considering the vast amount of information and data needed to keep an updated overview of a situation both during the daily surveillance work and during accident situations, the need for an efficient monitoring and processing system is evident. The rapid development, both in computer technology and in telecommunications, the evolution of fast and accurate computer codes enabling the on-line calculations improve the quality of decision-making in complex situations and assure a high efficiency. The monitoring and processing systems are used both for environmental protection and for controlling nuclear power plant emergency and post-accident situations. Such a system can offer information to the radiation management systems in order to assess the consequences of nuclear accidents and to establish a basis for right decisions in civil defense. The integrated environmental monitoring systems have as main task to record, collect, process and transmit the radiation levels and weather data, incorporating a number of stationary or mobile radiation monitoring equipment, weather parameter measuring station, an information processing center and the communication network, all running under a real-time operating system.They provide the automatic data collection on-line and off-line, remote diagnostic, advanced presentation techniques, including a graphically oriented executive support, which has the ability to respond to an emergency by geographical representation of the hazard zones on the map. The systems are based on local intelligent measuring and transmission units, simultaneous processing and data presentation using a real-time operating system for personal computers and geographical information system (GIS). All information can be managed directly from the map by multilevel data retrieving and

  5. INVESTMENT ATTRACTIVENESS OF ENTERPRISES

    Directory of Open Access Journals (Sweden)

    Nadiia Davydenko

    2017-03-01

    Full Text Available In the article the approaches to defining the essence of the concept of “investment attractiveness of enterprises” were analyzed. On the example of "Agrofirm Brusilov" depth analysis of the agricultural enterprises to evaluate of profitability, liquidity, solvency, financial stability, the timing of the return of invested funds and minimizing investment risks was conducted. To study methods of rating and system analysis were used. To justify the conditions of  increasing investment attractiveness farms method of scoring was used. It was established as a result of the use of integrated evaluation of the financial position one can see problem aspects of financial position of the company and develop measures to enhance liquidity, solvency, identify potential for raising the efficiency of company and prevention of financial crisis. The analysis of financial position showed that the management of the enterprise doesn’t  think  about  financial stability and solvency, does not understand the benefit of borrowed capital. Using research results in practice of agricultural enterprises allows us to give a real evaluation of investment attractiveness and justify ways to improve it. Key words: investments, investment attractiveness, potential business, financial position.

  6. Africa attracted by nuclear energy

    International Nuclear Information System (INIS)

    Anon.

    2006-01-01

    Africa would prefer to use its uranium reserves instead of exporting them but the obstacles to this project are the financing difficulties, the lack of regulation and the lack of expert in this area. (N.C.)

  7. Design of integrated safeguards systems for nuclear facilities

    International Nuclear Information System (INIS)

    de Montmollin, J.M.; Walton, R.B.

    1978-06-01

    Safeguards systems that are capable of countering postulated threats to nuclear facilities must be closely integrated with plant layout and processes if they are to be effective and if potentially-severe impacts on plant operations are to be averted. This paper describes a facilities safeguards system suitable for production plant, in which the traditional elements of physical protection and periodic material-balance accounting are extended and augmented to provide close control of material flows. Discrete material items are subjected to direct, overriding physical control where appropriate. Materials in closely-coupled process streams are protected by on-line NDA and weight measurements, with rapid computation of material balances to provide immediate indication of large-scale diversion. The system provides information and actions at the safeguards/operations interface

  8. Design of integrated safeguards systems for nuclear facilities

    International Nuclear Information System (INIS)

    de Montmollin, J.M.; Walton, R.B.

    1976-01-01

    Safeguards systems that are capable of countering postulated threats to nuclear facilities must be closely integrated with plant layout and processes if they are to be effective and if potentially severe impacts on plant operations are to be averted. A facilities safeguards system suitable for a production plant is described in which the traditional elements of physical protection and periodic material-balance accounting are extended and augmented to provide close control of material flows. Discrete material items are subjected to direct, overriding physical control where appropriate. Materials in closely coupled process streams are protected by on-line NDA and weight measurements, with rapid computation of material balances to provide immediate indication of large-scale diversion. The system provides an information and actions at the safeguards/operations interface

  9. Integrated CAD/CAE for nuclear power plants

    International Nuclear Information System (INIS)

    Lecoq, P.; Lachat, J.C.

    1987-01-01

    The size of the French nuclear power program has led both EDF and Framatome to equip themselves progressively with management software, computer-assisted design (CAD) systems, and computer-assisted engineering (CAE) systems. The nature of the projects and of the respective activities of EDF and Framatome determined the essential specifications of these computerized systems. EDF and Framatome have pooled their CAD/CAE efforts in a joint venture (Groupement d'Interet Economique) called GIAO, set up in 1985 by EDF and Aquitaine Systeme (a subsidiary of Framatome and Elf Aquitaine). GIAO's ambition is to become a pole of French CAD/CAE efforts and to foster progress in integrated computer-assisted engineering, by enlarging the synergy of EDF and Framatome in this field to other enterprises that participate in design and construction of complex industrial plants

  10. Nuclear material data management and integration. A safeguard perspective

    International Nuclear Information System (INIS)

    Wilkey, David D.; Martin, H.R.; O'Leary, Jerry

    1999-01-01

    This paper is a discussion of the use of available data in the performance of nuclear material (NM) safeguards. The discussion considers the various sources of data and system requirements for collecting and managing that data, and is preliminary concerned with domestic safeguards requirements such as those specified by the US Department of Energy. The preferred configuration for integrated data management does not necessarily require a single computer system; however, separate computerized systems with direct inter-system connections is preferred. Use of all relevant data NM accounting, NM control, physical protection, and non-safeguards) is necessary to assure the most effective protection for the NM inventories. Where direct exchange of data is not possible, a systematic program to implement indirect exchange is essential [ru

  11. INEL integrated spent nuclear fuel consolidation task team report

    International Nuclear Information System (INIS)

    Henry, R.N.; Clark, J.H.; Chipman, N.A.

    1994-01-01

    This document describes a draft plan and schedule to consolidate spent nuclear fuel (SNF) and special nuclear material (SNW) from aging storage facilities throughout the Idaho National Engineering Laboratory (INEL) to the Idaho Chemical Processing Plant (ICPP) in a safe, cost-effective, and expedient manner. A fully integrated and resource-loaded schedule was developed to achieve consolidation as soon as possible. All of the INEL SNF and SNM management task, projects, and related activities from fiscal year 1994 to the end of the consolidation period are logic-tied and integrated with each other. The schedule and plan are presented to initiate discussion of their implementation, which is expected to generate alternate concepts that can be evaluated using the methodology described in this report. Three perturbations to consolidating SNF as soon as possible are also explored. If the schedule is executed as proposed, the new and on-going consolidation activities will require about 6 years to complete and about $25.3M of additional funding. Reduced annual operating costs are expected to recover the additional investment in about 6.4 years. The total consolidation program as proposed will cost about $66.8M and require about 6 years to recover via reduced operating costs from retired SNF/SNM storage facilities. Detailed schedules and cost estimates for the Test Reactor Area Materials Test Reactor canal transfers are included as an example of the level of detail that is typical of the entire schedule (see Appendix D). The remaining work packages for each of the INEL SNF consolidation transfers are summarized in this document. Detailed cost and resource information is available upon request for any of the SNF consolidation transfers

  12. Multivariable robust control of an integrated nuclear power reactor

    Directory of Open Access Journals (Sweden)

    A. Etchepareborda

    2002-12-01

    Full Text Available The design of the main control system of the CAREM nuclear power plant is presented. This plant is an inherently safe low-power nuclear reactor with natural convection on the primary coolant circuit and is self-pressurized with a steam dome on the top of the pressure vessel (PV. It is an integrated reactor as the whole primary coolant circuit is within the PV. The primary circuit transports the heat to the secondary circuit through once-through steam generators (SG. There is a feedwater valve at the inlet of the SG and a turbine valve at the outlet of the SG. The manipulated variables are the aperture of these valves and the reactivity of the control rods. The control target is to regulate the primary and secondary pressures and to monitor steam flow reference ramps on a range of nominal flow from 100% to 40%. The requirements for the control system are robust stability, low-order simple controllers and transient/permanent error bounding. The controller design is based on a detailed RETRAN plant model, from which linear perturbed open-loop dynamic models at different powers are identified. Two low-order nominal models with their associated uncertainties are chosen for two different power ranges. Robust controllers with acceptable performances are designed for each range. Numerical optimization based on the loop-shaping method is used for the controller design. The designed controllers are implemented in the RETRAN model and tested in simulations achieving successful results.

  13. Bibliography of integral charged-particle nuclear data

    International Nuclear Information System (INIS)

    Burrows, T.W.; Wyant, G.

    1981-03-01

    This publication is the first supplement to the archival edition of the National Nuclear Data Center's charged-particle bibliography. This supplement contains citations to all references scanned since March 15, 1980, and all corrections and additions to previous citations, and indexes all data received in the international exchanged format (EXFOR). The primary goal of the bibliography has been to satisfy the need expressed by the Nuclear Reaction Data Center Network for a concise and comprehensive bibliography of integral charged-particle cross section data and to provide an index of data exchanged among the members. As a result of a recommendation by the recent Workshop on Intense High Energy Neutron Source and Their Characteristics, we have also undertaken to expand the coverage of charged-particle-induced neutron-source reactions to include differential data. This supplement is divided into two sections, References and Isotope Production. The References section contains all references satisfying the criteria noted. The Isotope Production section contains an abbreviated reference line for all entries which contain information on a definite residual nucleus, on particle production, or on mass, charge, or isotopic distributions. Entries in the References section are sequentially numbered. These sequence numbers serve as a link between the two sections

  14. Nuclear data and integral experiments in reactor physics

    International Nuclear Information System (INIS)

    Farinelli, U.

    1980-01-01

    The material given here broadly covers the content of the 10 lectures delivered at the Winter Course on Reactor Theory and Power Reactors, ICTP, Trieste (13 February - 10 March 1978). However, the parts that could easily be found in the current literature have been omitted and replaced with the appropriate references. The needs for reactor physics calculations, particularly as applicable to commercial reactors, are reviewed in the introduction. The relative merits and shortcomings of fundamental and semi-empirical methods are discussed. The relative importance of different nuclear data, the ways in which they can be measured or calculated, and the sources of information on measured and evaluated data are briefly reviewed. The various approaches to the condensation of nuclear data to multigroup cross sections are described. After some consideration to the sensitivity calculations and the evaluation of errors, some of the most important type of integral experiments in reactor physics are introduced, with a view to showing the main difficulties in the interpretation and utilization of their results and the most recent trends in experimentation. The conclusions try to assign some priorities in the implementation of experimental and calculational capabilities, especially for a developing country. (author)

  15. Integrated information system for analysis of nuclear power plants

    International Nuclear Information System (INIS)

    Galperin, A.

    1994-01-01

    Performing complicated engineering analyses of a nuclear power plant requires storage and manipulation of a large amount of information, both data and knowledge. This information is characterized by its multidisciplinary nature, complexity, and diversity. The problems caused by inefficient and lengthy manual operations involving the data flow management within the frame-work of the safety-related analysis of a power plant can be solved by applying the computer aided engineering principles. These principles are the basis of the design of an integrated information storage system (IRIS). The basic idea is to create a computerized environment, which includes both database and functional capabilities. Consideration and analysis of the data types and required data manipulation capabilities as well as operational requirements, resulted in the choice of an object-oriented data-base management system (OODBMS) as a development platform for solving the software engineering problems. Several advantages of OODBMSs over conventional relations database systems were found of crucial importance, especially providing the necessary flexibility for different data types and extensibility potential. A detailed design of a data model is produced for the plant technical data and for the storage of analysis results. The overall system architecture was designed to assure the feasibility of integrating database capabilities with procedures and functions written in conventional algorithmic programming languages

  16. French nuclear plants PWR vessel integrity assessment and life management

    Energy Technology Data Exchange (ETDEWEB)

    Bezdikian, G. [Electricite de France (EDF), Div. Production Nucleaire, 93 - Saint-Denis (France); Quinot, P. [FRAMATOME, Dept. Bloc Reacteur et Boucles Primaires, 92 - Paris-La-Defence (France); Faidy, C.; Churier-Bossennec, H. [Electricite de France (EDF), Div. Ingenierie et Service, 69 - Villeurbanne (France)

    2001-07-01

    The Reactor Pressure Vessel life management of 56 PWR 3 loop and 4 loop reactors units was engaged by the French Utility EDF (Electricite de France) a few years ago and is yet on going on. This paper will present the work carried out within the framework of justifying why the 34 three loop reactor vessels will remain acceptable for operation for a lifetime of at least 40-years. A summary of the measures will be given. An overall review of actions will be presented describing the French approach, using important existing databases, including studies related to irradiation surveillance monitoring program and end of life fluence assessment. The last results obtained are based on generic integrity analyses for all categories of situations (normal upset emergency and faulted conditions) until the end of lifetime, postulating circumferential an radial kinds of flaw located in the stainless steel cladding or shallow sub-cladding area. The results of structural integrity analyses beginning with elastic computations and completed with three-dimensional finite element elastic plastic computations for envelope cases, are compared with code criteria for operating plants. The objective is to evaluate the margins on different parameters as RTNDT (Reference Nil Ductility Transition Temperature), toughness or crack size, to justify the global fitness for service of all these Reactor Pressure Vessels. The paper introduces EDF's maintenance strategy, related to integrity assessment, for those nuclear power plants under operation, based on NDE in-service inspection of the first thirty millimeters in the thickness of the wall and major surveillance programs of the vessels. (author)

  17. French nuclear plants PWR vessel integrity assessment and life management

    International Nuclear Information System (INIS)

    Bezdikian, G.; Quinot, P.; Faidy, C.; Churier-Bossennec, H.

    2001-01-01

    The Reactor Pressure Vessel life management of 56 PWR 3 loop and 4 loop reactors units was engaged by the French Utility EDF (Electricite de France) a few years ago and is yet on going on. This paper will present the work carried out within the framework of justifying why the 34 three loop reactor vessels will remain acceptable for operation for a lifetime of at least 40-years. A summary of the measures will be given. An overall review of actions will be presented describing the French approach, using important existing databases, including studies related to irradiation surveillance monitoring program and end of life fluence assessment. The last results obtained are based on generic integrity analyses for all categories of situations (normal upset emergency and faulted conditions) until the end of lifetime, postulating circumferential an radial kinds of flaw located in the stainless steel cladding or shallow sub-cladding area. The results of structural integrity analyses beginning with elastic computations and completed with three-dimensional finite element elastic plastic computations for envelope cases, are compared with code criteria for operating plants. The objective is to evaluate the margins on different parameters as RTNDT (Reference Nil Ductility Transition Temperature), toughness or crack size, to justify the global fitness for service of all these Reactor Pressure Vessels. The paper introduces EDF's maintenance strategy, related to integrity assessment, for those nuclear power plants under operation, based on NDE in-service inspection of the first thirty millimeters in the thickness of the wall and major surveillance programs of the vessels. (author)

  18. Integrated online condition monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Hashemian, Hashem M.

    2010-01-01

    Online condition monitoring or online monitoring (OLM) uses data acquired while a nuclear power is operating to continuously assess the health of the plant's sensors, processes, and equipment; to measure the dynamic performance of the plant's process instrumentation; to verify in-situ the calibration of the process instrumentation; to detect blockages, voids, and leaks in the pressure sensing lines; to identify core flow anomalies; to extend the life of neutron detectors and other sensors; and to measure the vibration of reactor internals. Both the steady-state or DC output of plant sensors and their AC signal or noise output can be used to assess sensor health, depending on whether the application is monitoring a rapidly changing (e.g., core barrel motion) or a slowly changing (e.g., sensor calibration) process. The author has designed, developed, installed, and tested OLM systems (comprised of software/hardware-based data acquisition and data processing modules) that integrate low-frequency (1 mHz to 1 Hz) techniques such as RTD cross-calibration, pressure transmitter calibration monitoring, and equipment condition monitoring and high-frequency (1 Hz to 1 kHz) techniques such as the noise analysis technique. The author has demonstrated the noise analysis technique's effectiveness for measuring the dynamic response-time of pressure transmitters and their sensing lines; for performing predictive maintenance on reactor internals; for detecting core flow anomalies; and for extending neutron detector life. Integrated online condition monitoring systems can combine AC and DC data acquisition and signal processing techniques, can use data from existing process sensors during all modes of plant operation, including startup, normal operation, and shutdown; can be retrofitted into existing PWRs, BWRs, and other reactor types and will be integrated into next-generation plants. (orig.)

  19. Integrated online condition monitoring system for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hashemian, Hashem M. [Analysis and Measurement Services Corporation, Knoxville, TN (United States). AMS Technology Center

    2010-09-15

    Online condition monitoring or online monitoring (OLM) uses data acquired while a nuclear power is operating to continuously assess the health of the plant's sensors, processes, and equipment; to measure the dynamic performance of the plant's process instrumentation; to verify in-situ the calibration of the process instrumentation; to detect blockages, voids, and leaks in the pressure sensing lines; to identify core flow anomalies; to extend the life of neutron detectors and other sensors; and to measure the vibration of reactor internals. Both the steady-state or DC output of plant sensors and their AC signal or noise output can be used to assess sensor health, depending on whether the application is monitoring a rapidly changing (e.g., core barrel motion) or a slowly changing (e.g., sensor calibration) process. The author has designed, developed, installed, and tested OLM systems (comprised of software/hardware-based data acquisition and data processing modules) that integrate low-frequency (1 mHz to 1 Hz) techniques such as RTD cross-calibration, pressure transmitter calibration monitoring, and equipment condition monitoring and high-frequency (1 Hz to 1 kHz) techniques such as the noise analysis technique. The author has demonstrated the noise analysis technique's effectiveness for measuring the dynamic response-time of pressure transmitters and their sensing lines; for performing predictive maintenance on reactor internals; for detecting core flow anomalies; and for extending neutron detector life. Integrated online condition monitoring systems can combine AC and DC data acquisition and signal processing techniques, can use data from existing process sensors during all modes of plant operation, including startup, normal operation, and shutdown; can be retrofitted into existing PWRs, BWRs, and other reactor types and will be integrated into next-generation plants. (orig.)

  20. Integration of the military and civilian nuclear fuel cycles in Russia

    International Nuclear Information System (INIS)

    Bukharin, O.

    1994-01-01

    This paper describes the close integration of the civil and military nuclear fuel cycles in Russia. Individual processing facilities, as well as the flow of nuclear material, are described as they existed in the 1980s and as they exist today. The end of the Cold War and the breakup of the Soviet Union weakened the ties between the two nuclear fuel cycles, but did not separate them. Separation of the military and civilian nuclear fuel cycles would facilitate Russia's integration into the world's nuclear fuel cycle and its participation in international non-proliferation regimes

  1. CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC

    International Nuclear Information System (INIS)

    Wu, Yican; Song, Jing; Zheng, Huaqing; Sun, Guangyao; Hao, Lijuan; Long, Pengcheng; Hu, Liqin

    2015-01-01

    Highlights: • The new developed CAD-based Monte Carlo program named SuperMC for integrated simulation of nuclear system makes use of hybrid MC-deterministic method and advanced computer technologies. SuperMC is designed to perform transport calculation of various types of particles, depletion and activation calculation including isotope burn-up, material activation and shutdown dose, and multi-physics coupling calculation including thermo-hydraulics, fuel performance and structural mechanics. The bi-directional automatic conversion between general CAD models and physical settings and calculation models can be well performed. Results and process of simulation can be visualized with dynamical 3D dataset and geometry model. Continuous-energy cross section, burnup, activation, irradiation damage and material data etc. are used to support the multi-process simulation. Advanced cloud computing framework makes the computation and storage extremely intensive simulation more attractive just as a network service to support design optimization and assessment. The modular design and generic interface promotes its flexible manipulation and coupling of external solvers. • The new developed and incorporated advanced methods in SuperMC was introduced including hybrid MC-deterministic transport method, particle physical interaction treatment method, multi-physics coupling calculation method, geometry automatic modeling and processing method, intelligent data analysis and visualization method, elastic cloud computing technology and parallel calculation method. • The functions of SuperMC2.1 integrating automatic modeling, neutron and photon transport calculation, results and process visualization was introduced. It has been validated by using a series of benchmarking cases such as the fusion reactor ITER model and the fast reactor BN-600 model. - Abstract: Monte Carlo (MC) method has distinct advantages to simulate complicated nuclear systems and is envisioned as a routine

  2. Nuclear reactor pressure vessel integrity insurance by crack arrestability evaluation using load from CVN tests

    International Nuclear Information System (INIS)

    Fabry, A.

    1997-01-01

    The present work is undertaken in the framework of nuclear reactor pressure vessel (RPV) surveillance and aims at revisiting the crack arrest approach to structural integrity insurance. This approach, performed under normal plant operation conditions, can also offer an attractive alternative to the crack initiation philosophy promoted for accidental analysis. To this end, an accidental conservative, cost effective and robust methodology is forwarded and demonstrated: it makes use of the crack arrest information contained in the instrumented Charpy V-notch impact test and/or in the shear fracture appearance of broken samples. Particular attention is paid to the appraisal of uncertainties and the related safety margin. The resulting capability is placed in perspective with the state-of-the-art crack initiation methodology based on the slow bend testing of recracked specimens, presently under standardization world-wide. The investigation leads to highlight three conceptual weaknesses of current enfgineering and regulatory practices. Improved crack arrestability evaluation emerges as an optimal approach to insure safe PWR operation up to design end-of-life and beyond

  3. Nuclear reactor pressure vessel integrity insurance by crack arrestability evaluation using load from CVN tests

    Energy Technology Data Exchange (ETDEWEB)

    Fabry, A.

    1997-10-15

    The present work is undertaken in the framework of nuclear reactor pressure vessel (RPV) surveillance and aims at revisiting the crack arrest approach to structural integrity insurance. This approach, performed under normal plant operation conditions, can also offer an attractive alternative to the crack initiation philosophy promoted for accidental analysis. To this end, an accidental conservative, cost effective and robust methodology is forwarded and demonstrated: it makes use of the crack arrest information contained in the instrumented Charpy V-notch impact test and/or in the shear fracture appearance of broken samples. Particular attention is paid to the appraisal of uncertainties and the related safety margin. The resulting capability is placed in perspective with the state-of-the-art crack initiation methodology based on the slow bend testing of recracked specimens, presently under standardization world-wide. The investigation leads to highlight three conceptual weaknesses of current enfgineering and regulatory practices. Improved crack arrestability evaluation emerges as an optimal approach to insure safe PWR operation up to design end-of-life and beyond.

  4. Study of developing nuclear fabrication facility's integrated emergency response manual

    International Nuclear Information System (INIS)

    Kim, Taeh Yeong; Cho, Nam Chan; Han, Seung Hoon; Moon, Jong Han; Lee, Jin Hang; Min, Guem Young; Han, Ji Ah

    2016-01-01

    Public begin to pay attention to emergency management. Thus, public's consensus on having high level of emergency management system up to advanced country's is reached. In this social atmosphere, manual is considered as key factor to prevent accident or secure business continuity. Therefore, we first define possible crisis at KEPCO Nuclear Fuel (hereinafter KNF) and also make a 'Reaction List' for each crisis situation at the view of information-design. To achieve it, we analyze several country's crisis response manual and then derive component, indicate duties and roles at the information-design point of view. From this, we suggested guideline to make 'Integrated emergency response manual(IERM)'. The manual we used before have following few problems; difficult to applicate at the site, difficult to deliver information. To complement these problems, we searched manual elements from the view of information-design. As a result, we develop administrative manual. Although, this manual could be thought as fragmentary manual because it confined specific several agency/organization and disaster type

  5. Steam Generator tube integrity -- US Nuclear Regulatory Commission perspective

    International Nuclear Information System (INIS)

    Murphy, E.L.; Sullivan, E.J.

    1997-01-01

    In the US, the current regulatory framework was developed in the 1970s when general wall thinning was the dominant degradation mechanism; and, as a result of changes in the forms of degradation being observed and improvements in inspection and tube repair technology, the regulatory framework needs to be updated. Operating experience indicates that the current U.S. requirements should be more stringent in some areas, while in other areas they are overly conservative. To date, this situation has been dealt with on a plant-specific basis in the US. However, the NRC staff is now developing a proposed steam generator rule as a generic framework for ensuring that the steam generator tubes are capable of performing their intended safety functions. This paper discusses the current U.S. regulatory framework for assuring steam generator (SG) tube integrity, the need to update this regulatory framework, the objectives of the new proposed rule, the US Nuclear Regulatory Commission (NRC) regulatory guide (RG) that will accompany the rule, how risk considerations affect the development of the new rule, and some outstanding issues relating to the rule that the NRC is still dealing with

  6. Integral Fast Reactor: A future source of nuclear energy

    International Nuclear Information System (INIS)

    Southon, R.

    1993-01-01

    Argonne National Laboratory is developing a reactor concept that would be an important part of the worlds energy future. This report discusses the Integral Fast Reactor (IFR) concept which provides significant improvements over current generation reactors in reactor safety, plant complexity, nuclear proliferation, and waste generation. Two major facilities, a reactor and a fuel cycle facility, make up the IFR concept. The reactor uses fast neutrons and metal fuel in a sodium coolant at atmospheric pressure that relies on laws of physics to keep it safe. The fuel cycle facility is a hot cell using remote handling techniques for fabricating reactor fuel. The fuel feed stock includes spent fuel from the reactor, and potentially, spent light water reactor fuel and plutonium from weapons. This paper discusses the unique features of the IFR concept and the differences the quality assurance program has from current commercial practices. The IFR concept provides an opportunity to design a quality assurance program that makes use of the best contemporary ideas on management and quality

  7. Development of an integrated database management system to evaluate integrity of flawed components of nuclear power plant

    International Nuclear Information System (INIS)

    Mun, H. L.; Choi, S. N.; Jang, K. S.; Hong, S. Y.; Choi, J. B.; Kim, Y. J.

    2001-01-01

    The object of this paper is to develop an NPP-IDBMS(Integrated DataBase Management System for Nuclear Power Plants) for evaluating the integrity of components of nuclear power plant using relational data model. This paper describes the relational data model, structure and development strategy for the proposed NPP-IDBMS. The NPP-IDBMS consists of database, database management system and interface part. The database part consists of plant, shape, operating condition, material properties and stress database, which are required for the integrity evaluation of each component in nuclear power plants. For the development of stress database, an extensive finite element analysis was performed for various components considering operational transients. The developed NPP-IDBMS will provide efficient and accurate way to evaluate the integrity of flawed components

  8. Development of integrity evaluation technology for pressurized components in nuclear power plant and IT based integrity evaluation system

    International Nuclear Information System (INIS)

    Kim, Young Jin; Choi, Jae Boong; Shim, Do Jun

    2004-02-01

    The objective of this research is to develop on efficient integrity evaluation technology and to investigate the applicability of the newly-developed technology such as internet-based cyber platform etc. to Nuclear Power Plant(NPP) components. The development of an efficient structural integrity evaluation system is necessary for safe operation of NPP as the increase of operating periods. Moreover, material test data as well as emerging structural integrity assessment technology are also needed for the evaluation of aged components. The following five topics are covered in this project: development of the wall-thinning evaluation program for nuclear piping; development of structural integrity evaluation criteria for steam generator tubes with cracks of various shape; development of fatigue life evaluation system for major components of NPP; ingegration of internet-based cyber platform and integrity evaluation program for primary components of NPP; effects of aging on strength of dissimilar welds

  9. Development of integrity evaluation technology for pressurized components in nuclear power plant and IT based integrity evaluation system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Choi, Jae Boong; Shim, Do Jun [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2004-02-15

    The objective of this research is to develop on efficient integrity evaluation technology and to investigate the applicability of the newly-developed technology such as internet-based cyber platform etc. to Nuclear Power Plant(NPP) components. The development of an efficient structural integrity evaluation system is necessary for safe operation of NPP as the increase of operating periods. Moreover, material test data as well as emerging structural integrity assessment technology are also needed for the evaluation of aged components. The following five topics are covered in this project: development of the wall-thinning evaluation program for nuclear piping; development of structural integrity evaluation criteria for steam generator tubes with cracks of various shape; development of fatigue life evaluation system for major components of NPP; ingegration of internet-based cyber platform and integrity evaluation program for primary components of NPP; effects of aging on strength of dissimilar welds.

  10. Attractive evolutionary equilibria

    OpenAIRE

    Roorda, Berend; Joosten, Reinoud

    2011-01-01

    We present attractiveness, a refinement criterion for evolutionary equilibria. Equilibria surviving this criterion are robust to small perturbations of the underlying payoff system or the dynamics at hand. Furthermore, certain attractive equilibria are equivalent to others for certain evolutionary dynamics. For instance, each attractive evolutionarily stable strategy is an attractive evolutionarily stable equilibrium for certain barycentric ray-projection dynamics, and vice versa.

  11. Rheology of attractive emulsions.

    Science.gov (United States)

    Datta, Sujit S; Gerrard, Dustin D; Rhodes, Travers S; Mason, Thomas G; Weitz, David A

    2011-10-01

    We show how attractive interactions dramatically influence emulsion rheology. Unlike the repulsive case, attractive emulsions below random close packing, φ(RCP), can form soft gel-like elastic solids. However, above φ(RCP), attractive and repulsive emulsions have similar elasticities. Such compressed attractive emulsions undergo an additional shear-driven relaxation process during yielding. Our results suggest that attractive emulsions begin to yield at weak points through the breakage of bonds, and, above φ(RCP), also undergo droplet configurational rearrangements.

  12. Developments of integrity evaluation technology for pressurized components in nuclear power plant and IT based integrity evaluation system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Choi, Jae Boong; Shim, Do Jun [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2003-03-15

    The objective of this research is to develop an efficient evaluation technology and to investigate applicability of newly-developed technology, such as internet-based cyber platform, to operating power plants. Development of efficient evaluation systems for Nuclear Power Plant components, based on structural integrity assessment techniques, are increasingly demanded for safe operation with the increasing operating period of Nuclear Power Plants. The following five topics are covered in this project: development of assessment method for wall-thinned nuclear piping based on pipe test; development of structural integrity program for steam generator tubes with cracks of various shape; development of fatigue life evaluation system for mam components of NPP; development of internet-based cyber platform and integrity program for primary components of NPP; effect of aging on strength of dissimilar welds.

  13. Severe accidents and nuclear containment integrity (SANCY). SANCY summary report

    Energy Technology Data Exchange (ETDEWEB)

    Lindholm, I. [VTT Processes, Espoo (Finland)

    2004-07-01

    SANCY project investigates physical phenomena related to severe nuclear accidents with importance to Finnish nuclear power plants. Currently the major topics are the ex-vessel coolability issues, long-term severe accident management and containment leak tightness and adoption and development of new calculation tools considering also the needs of the future Olkiluoto 3 plant. SANCY employs both experimental and analytical methods. (orig.)

  14. Nuclear safety, security and safeguards. An application of an integrated approach

    Energy Technology Data Exchange (ETDEWEB)

    Chapman, Howard; Edwards, Jeremy; Fitzpatrick, Joshua; Grundy, Colette; Rodger, Robert; Scott, Jonathan [National Nuclear Laboratory, Warrington (United Kingdom)

    2018-01-15

    National Nuclear Laboratory has recently produced a paper regarding the integrated approach of nuclear safety, security and safeguards. The paper considered the international acknowledgement of the inter-relationships and potential benefits to be gained through improved integration of the nuclear '3S'; Safety, Security and Safeguards. It considered that combining capabilities into one synergistic team can provide improved performance and value. This approach to integration has been adopted, and benefits realised by the National Nuclear Laboratory through creation of a Safety, Security and Safeguards team. In some instances the interface is clear and established, as is the case between safety and security in the areas of Vital Area Identification. In others the interface is developing such as the utilisation of safeguards related techniques such as nuclear material accountancy and control to enhance the security of materials. This paper looks at a practical example of the progress to date in implementing Triple S by a duty holder.

  15. Management information system for cost-schedule integration control for nuclear power projects

    International Nuclear Information System (INIS)

    Liu Wei; Wang Yongqing; Tian Li

    2001-01-01

    Based on the project management experience abroad and at home, a cost-schedule integration control model was developed to improve nuclear power project management. The model integrates cost data with the scheduling data by unity coding to efficiently implement cost-schedule integration control on line. The software system architecture and database is designed and implemented. The system functions include estimating and forecasting dynamically cash flow, scheduling and evaluating deviation from the cost-schedule plan, etc. The research and development of the system should improve the architecture of computer integrated management information systems for nuclear power projects in China

  16. Research on integrated managing system based on CIMS for nuclear power plant safety

    International Nuclear Information System (INIS)

    Zhou Gang

    2006-01-01

    In order to improve safety, economy and reliability of operation for nuclear power plant (NPP), a novel integrated managing method was proposed based on the ideas of computer and contemporary integrated manufacturing system (CIMS). The application of CIMS to nuclear power plant safety management was researched. In order to design an integrated managing system to meet the needs of NPP safety management, all work related to nuclear safety is divided into different category according to its characters. On basis of this work, general integrated managing system was designed at first. Then subsystems were designed and every subsystem implements a category of nuclear safety management work. All subsystems are independent relatively on the one hand and are interrelated on other hand by global information system. (authors)

  17. Analysis of a nuclear backscattering and reaction data by the method of convolution integrals

    International Nuclear Information System (INIS)

    Lewis, M.B.

    1979-02-01

    A quantitative description of nuclear backscattering and reaction processes is made. Various formulas pertinent to nuclear microanalysis are assembled in a manner useful for experimental application. Convolution integrals relating profiles of atoms in a metal substrate to the nuclear reaction spectra obtained in the laboratory are described and computed. Energy straggling and multiple scattering are explicitly included and shown to be important. Examples of the application of the method to simple backscattering, oxide films, and implanted gas are discussed. 7 figures, 1 table

  18. Integrated planning for nuclear siting - The South African experience

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, J C.A.; Heidstra, N; Graupner, O F [Eskom, Johannesburg (South Africa); Hambleton-Jones, B [Atomic Energy Corporation of South Africa Ltd., Pellindaba, Pretoria (South Africa)

    1990-06-01

    This paper describes the process involved in the current national programme to identify potential sites for nuclear power development in South Africa. A description is given of the sensitivity studies - the evaluation of the potential perturbations to and opportunities for the biophysical and socioeconomic environments and the suitability studies - the evaluation of environmental influences on geotechnical, safety and financial considerations. This programme is divorced from any decision of whether or not to build further nuclear power station in South Africa. The programme described is a long range land-use planning exercise considered expedient in the face of competition for land that share similar requirements as those of nuclear power station sites. It is also designed to streamline nuclear power station lead times and to make national and regional planners aware of Eskom's requirements in the drafting of their policies and plans. (author)

  19. Integrated planning for nuclear siting - The South African experience

    International Nuclear Information System (INIS)

    Hobbs, J.C.A.; Heidstra, N.; Graupner, O.F.; Hambleton-Jones, B.

    1990-01-01

    This paper describes the process involved in the current national programme to identify potential sites for nuclear power development in South Africa. A description is given of the sensitivity studies - the evaluation of the potential perturbations to and opportunities for the biophysical and socioeconomic environments and the suitability studies - the evaluation of environmental influences on geotechnical, safety and financial considerations. This programme is divorced from any decision of whether or not to build further nuclear power station in South Africa. The programme described is a long range land-use planning exercise considered expedient in the face of competition for land that share similar requirements as those of nuclear power station sites. It is also designed to streamline nuclear power station lead times and to make national and regional planners aware of Eskom's requirements in the drafting of their policies and plans. (author)

  20. Good practices in provision of nuclear safeguards and security training courses at the Integrated Support Center for Nuclear Nonproliferation and Nuclear Security

    Directory of Open Access Journals (Sweden)

    Kobayashi Naoki

    2017-01-01

    Full Text Available More than five years have passed since the Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN was established under the Japan Atomic Energy Agency (JAEA in December 2010 and started its activities, in response to the commitment of Japan at the Nuclear Security Summit in Washington D.C.. The ISCN has been vigorously involved in capacity building assistance on nuclear nonproliferation (safeguards and nuclear security, mainly in the Asian region. It has provided 105 training courses to 2901 participants in total as of August 2016. The ISCN plays a major role in strengthening nuclear nonproliferation and nuclear security in the region, and this can be considered one of the great results of the Nuclear Security Summit process. The ISCN has cooperated with the US Department of Energy/National Nuclear Security Administration (DOE/NNSA and Sandia National Laboratories (SNL to establish a base of instructors, particularly for the Center's flagship two-week courses, the Regional Training Course on Physical Protection of Nuclear Material and Facilities (RTC on PP and the Regional Training Course on State Systems of Accounting for and Control of Nuclear Material (RTC on SSAC. Furthermore, the ISCN has provided training courses for experts in Japan, making the best use of the Center's knowledge and experience of organizing international courses. The ISCN has also started joint synchronized training with the Joint Research Centre of the European Commission (EC JRC on nuclear safeguards. This paper describes the good practices at the ISCN through its five years of activities, focusing on its progress in nuclear safeguards and nuclear security training.

  1. Verification and validation as an integral part of the development of digital systems for nuclear applications

    International Nuclear Information System (INIS)

    Straker, E.A.; Thomas, N.C.

    1983-01-01

    The nuclear industry's current attitude toward verification and validation (V and V) is realized through the experiences gained to date. On the basis of these experiences, V and V can effectively be applied as an integral part of digital system development for nuclear electric power applications. An overview of a typical approach for integrating V and V with system development is presented. This approach represents a balance between V and V as applied in the aerospace industry and the standard practice commonly applied within the nuclear industry today

  2. Nuclear Hybrid Energy Systems Initial Integrated Case Study Development and Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Harrison, Thomas J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Greenwood, Michael Scott [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-12-01

    The US Department of Energy Office of Nuclear Energy established the Nuclear Hybrid Energy System (NHES) project to develop a systematic, rigorous, technically accurate set of methods to model, analyze, and optimize the integration of dispatchable nuclear, fossil, and electric storage with an industrial customer. Ideally, the optimized integration of these systems will provide economic and operational benefits to the overall system compared to independent operation, and it will enhance the stability and responsiveness of the grid as intermittent, nondispatchable, renewable resources provide a greater share of grid power.

  3. Attractive evolutionary equilibria

    NARCIS (Netherlands)

    Joosten, Reinoud A.M.G.; Roorda, Berend

    2011-01-01

    We present attractiveness, a refinement criterion for evolutionary equilibria. Equilibria surviving this criterion are robust to small perturbations of the underlying payoff system or the dynamics at hand. Furthermore, certain attractive equilibria are equivalent to others for certain evolutionary

  4. Attraction and cooperative behavior

    OpenAIRE

    Donja Darai; Silvia Grätz

    2012-01-01

    Being good-looking seems to generate substantial benefits in many social interactions, making the "beauty premium" a not to be underrated economic factor. This paper investigates how physical attractiveness enables people to generate these benefits in the case of cooperation, using field data from a modified one-shot prisoner's dilemma played in a high-stakes television game show. While attractive contestants are not more or less cooperative than less attractive ones, facial attractiveness pr...

  5. Integration of remotely operated manipulator systems for the nuclear industry

    International Nuclear Information System (INIS)

    Blight, J.; Cornec, G.

    2003-01-01

    There is no getting away from remotely operated manipulator systems in significant part in dismantling operations, because of the actual radioactive emitting level of installations. However, some main contractors, who have been involved in dismantling projects in the past few years are reluctant to use remotely operated systems because: - equipment characteristics are not suitable for the environment and the work to be performed; - There are some design problems; - Main components do not withstand operation any longer, after some time; - There are deficiencies in the management of quality, for critical equipment problems that degrade the productivity and increase direct and indirect labour cost. As a summary therefore, equipment available on this dismantling market are reputedly unreliable and not 'industrial' (sturdy) enough. However, numerous operations in maintenance in primary loops of nuclear reactors, or in the Offshore sector, are carried out remotely, to the satisfaction of the operators and the investors. In the dismantling sector, a thorough analysis of the difficulties encountered indicates that their origin is mostly due to a lack of methodology - that needs to be addressed -, rather than a technical problem. In that context, CYBERNETIX proposes to be involved in phases upstream and downstream of the equipment supply's. Upstream: Participate in developing/validating the scenarios to be used to optimise the constraints of remote operations/equipment. Downstream: Participate actively in supporting the client on-site, ensuring that equipment are available and maintained by competent and motivated people, and thus, getting experience in order to improve the State-of-the-Art of robotic in that field. Then, the contracting authority and CYBERNETIX jointly define the limits and the content of the involvement of each party, and also define the most appropriate type of 'partnership' between the main contactor and the participating companies, and in order to

  6. Review of recent benchmark experiments on integral test for high energy nuclear data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Nakashima, Hiroshi; Tanaka, Susumu; Konno, Chikara; Fukahori, Tokio; Hayashi, Katsumi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-11-01

    A survey work of recent benchmark experiments on an integral test for high energy nuclear data evaluation was carried out as one of the work of the Task Force on JENDL High Energy File Integral Evaluation (JHEFIE). In this paper the results are compiled and the status of recent benchmark experiments is described. (author)

  7. Fire protection system management in nuclear facilities: strengthening factor of integrated management system - a case study

    International Nuclear Information System (INIS)

    Santos, Joao Regis dos

    2005-01-01

    The present study investigated and analyzed the importance of a system of integrated safety manage, environment and health in a nuclear installation, having as perspective, the fire protection manage. The inquiry was made using a qualitative research involving a case study, where the considered environment was the Reconversion and UO 2 Plant of the Industrias Nucleares do Brasil (INB), located in Resende, Rio de Janeiro and the studied population, the managers and the staff directly involved with the aspects related to the safety of the industrial complex of the related company. The motivation for the research was the search of a bigger interaction of the questions related to the safety, environment and health in the nuclear industry having, as axle of the investigation, the fire protection. As a result, it was observed that in a nuclear installation, although dealing with diversified safety processes, integration is possible and necessary, since there are more reasons for integration than otherwise. (author)

  8. Idea: an integrated set of tools for sustainable nuclear decommissioning projects

    International Nuclear Information System (INIS)

    Detilleux, M.; Centner, B.; Vanderperre, S.; Wacquier, W.

    2008-01-01

    Decommissioning of nuclear installations constitutes an important challenge and shall prove to the public that the whole nuclear life cycle is fully mastered by the nuclear industry. This could lead to an easier public acceptance of the construction of new nuclear power plants. When ceasing operation, nuclear installations owners and operators are looking for solutions in order to assess and keep decommissioning costs at a reasonable level, to fully characterise waste streams (in particular radiological inventories of difficult-to-measure radionuclides) and to reduce personnel exposure during the decommissioning activities taking into account several project, site and country specific constraints. In response to this need, Tractebel Engineering has developed IDEA (Integrated DEcommissioning Application), an integrated set of computer tools, to support the engineering activities to be carried out in the frame of a decommissioning project. IDEA provides optimized solutions from an economical, environmental, social and safety perspective. (authors)

  9. Development of web-based integrity evaluation system for primary components in a nuclear power plant

    International Nuclear Information System (INIS)

    Lee, S.M.; Kim, J.C.; Choi, J.B.; Kim, Y.J.; Choi, S.N.; Jang, K.S.; Hong, S.Y.

    2004-01-01

    A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including periodical in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage integrity issues on a nuclear power plant. In this paper, a web-based integrity evaluation system for primary components in a nuclear power plant is proposed. The proposed system, which is named as WEBIES (web-based integrity evaluation system), has been developed in the form of 3-tier system architecture. The system consists of three servers; application program server, user interface program server and data warehouse server. The application program server includes the defect acceptance analysis module and the fracture mechanics analysis module which are programmed on the basis of ASME sec. XI, appendix A. The data warehouse server provides data for the integrity evaluation including material properties, geometry information, inspection data and stress data. The user interface program server provides information to all co- workers in the field of integrity evaluation. The developed system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant. (orig.)

  10. Development of web-based integrity evaluation system for primary components in a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S.M.; Kim, J.C.; Choi, J.B.; Kim, Y.J. [SAFE Research Center, Sungkyunkwan Univ., Suwon (Korea); Choi, S.N.; Jang, K.S.; Hong, S.Y. [Korea Electronic Power Research Inst., Daejeon (Korea)

    2004-07-01

    A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including periodical in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage integrity issues on a nuclear power plant. In this paper, a web-based integrity evaluation system for primary components in a nuclear power plant is proposed. The proposed system, which is named as WEBIES (web-based integrity evaluation system), has been developed in the form of 3-tier system architecture. The system consists of three servers; application program server, user interface program server and data warehouse server. The application program server includes the defect acceptance analysis module and the fracture mechanics analysis module which are programmed on the basis of ASME sec. XI, appendix A. The data warehouse server provides data for the integrity evaluation including material properties, geometry information, inspection data and stress data. The user interface program server provides information to all co- workers in the field of integrity evaluation. The developed system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant. (orig.)

  11. Expert system technology for control integration in nuclear reactors

    International Nuclear Information System (INIS)

    Stabler, E.P. Jr.; Zimmerman, J.J.; Stratton, R.C.

    1986-03-01

    This report describes the role of expert system technology in nuclear power plant operation. The use of computers to assist operator decisions would greatly enhance the safety and efficiency of operation. A description of the necessary operator interfaces, data acquisition and validation, plant status and parameter diagnosis, and system reliability is presented. (FL)

  12. Integration of nuclear power in the Portuguese network. Present status

    International Nuclear Information System (INIS)

    Videira, F.M.

    1977-01-01

    The main characteristics of the Portuguese electric energy production system and their evolution in the past and near future are presented. Taking into consideration the Portuguese energy resources the alternatives to meet the additional long range electric energy needs are evaluated. Finally some comments are made about the present status of the nuclear option. (Auth.)

  13. Integration of the nuclear sector in Argentina: Competitiveness and acceptance

    International Nuclear Information System (INIS)

    Espejo, Hector

    2000-01-01

    After the end of Second World War, it was necessary to show clear evidences that the energy value of the nuclear reaction which had been observed, had to be channeled towards other purposes. These purposes were to promote innovations, technologies and applications with the fundamental goals of reducing economic inequities and improving the quality of life. In particular, the nuclear power option was also inserted in the frame of these ideas, and its competence as a safe energy supply had been consolidated and extended at a large scale due to the innovative technology using a new and different fuel. Very early, Argentina initiated activities in this sense and, as a matter of fact, this year it attains half a century of sustained and constant efforts in order to strengthen the role of nuclear activities, both at the national and international levels. This is a reasonable period of time in which a general overview could be made over the technological achievements reached, as well as about the insertion of the nuclear issue in the public opinion. (author)

  14. Face inversion increases attractiveness.

    Science.gov (United States)

    Leder, Helmut; Goller, Juergen; Forster, Michael; Schlageter, Lena; Paul, Matthew A

    2017-07-01

    Assessing facial attractiveness is a ubiquitous, inherent, and hard-wired phenomenon in everyday interactions. As such, it has highly adapted to the default way that faces are typically processed: viewing faces in upright orientation. By inverting faces, we can disrupt this default mode, and study how facial attractiveness is assessed. Faces, rotated at 90 (tilting to either side) and 180°, were rated on attractiveness and distinctiveness scales. For both orientations, we found that faces were rated more attractive and less distinctive than upright faces. Importantly, these effects were more pronounced for faces rated low in upright orientation, and smaller for highly attractive faces. In other words, the less attractive a face was, the more it gained in attractiveness by inversion or rotation. Based on these findings, we argue that facial attractiveness assessments might not rely on the presence of attractive facial characteristics, but on the absence of distinctive, unattractive characteristics. These unattractive characteristics are potentially weighed against an individual, attractive prototype in assessing facial attractiveness. Copyright © 2017 The Authors. Published by Elsevier B.V. All rights reserved.

  15. Summary description of the Babcock and Wilcox integrated nuclear design system

    International Nuclear Information System (INIS)

    Wittkopf, W.A.

    1976-03-01

    The Babcock and Wilcox integrated nuclear design system is divided into three broad areas: basic nuclear data processing, applications data processing, and nuclear design calculations. In basic nuclear data processing, basic nuclear data are collected, evaluated, and processed into a specified fine-energy mesh multigroup data file called a Master Library. In applications data processing, data for selected materials are retrieved from the Master Library and processed into an optimally structured, multigroup Production Library. Using these data and input descriptions of cells or regions, neutron spectra are generated and few-group constants are computed and fitted as a function of fuel burnup, initial enrichment, temperature, etc. In nuclear design calculations, few-group cross-section fits and descriptions of each core region and core geometry are input to a diffusion-depletion program or a nodal program that computes core reactivity, core power distribution, control rod worth, fuel cycle studies, core operating limitations, etc

  16. Psychology in nuclear power plants: an integrative approach to safety - general statement

    International Nuclear Information System (INIS)

    Shikiar, R.

    1983-08-01

    Since the accident at the Three Mile Island nuclear power plant on March 28, 1979, the commercial nuclear industry in the United States has paid increasing attention to the role of humans in overall plant safety. As the regulatory body with primary responsibility for ensuring public health and safety involving nuclear operations, the United States Nuclear Regulatory Commission (NRC) has also become increasingly involved with the ''human'' side of nuclear operations. The purpose of this symposium is to describe a major program of research and technical assistance that the Pacific Northwest Laboratory is performing for the NRC that deals with the issues of safety at nuclear power plants (NPPs). This program addresses safety from several different levels of analysis, which are all important within the context of an integrative approach to system safety

  17. The integral formation of the university technologists in nuclear medicine

    International Nuclear Information System (INIS)

    Tossi, Mirta H.; Chwojnik, Abraham; Otero, Dino

    2003-01-01

    Full text: Nuclear medicine has contributed to notable benefits to the human health from the very beginning. The Radioisotopes techniques, as well as the ionizing radiation used, have evolved providing functional and anatomical information of the patient, through non-invasive methods. With reference to Radiological Protection, the justification of each one of these practices and its perfect execution is intimately related to the benefit provided to the patients. The National Atomic Energy Commission apart from favouring the scientific and technological development, considers indispensable to work thoroughly on the professional training of the prospective technologists. Our over twenty-year experience in organizing and delivering courses of Technologists in Nuclear Medicine, although based on a much simpler program, have allowed the Institute of Nuclear Studies of the Ezeiza Atomic Center to acquire the capacity of developing a program to train highly qualified Technologists in that field. This project represents a step forward of great importance to the graduates qualification, since they will have the endorsement of CNEA and of the Faculty of Medicine of the Maimonides University. These are the three outstanding characteristics agreed on: 1.- General Education, carried out by subjects closely related to the optimisation of the relation Technologist - Patient - Environment and represented by: Radiological Protection and Hospital Security, Psychology, Ethics and Professional Medical Ethics, Nursing, English, Hygiene and Hospital Security and Management of the Quality in Services of Health. 2.- Diagnostic Procedures: planned according to organs, apparatuses or systems which are horizontally crossed by the anatomy, physiology and physiopathology Preparation of the patient, indications, main counter indications, radiopharmaceuticals, mechanisms of incorporation, pathologies, clinical protocols, instrumentation, post radiopharmaceuticals administration imaging

  18. Simulation methods of nuclear electromagnetic pulse effects in integrated circuits

    International Nuclear Information System (INIS)

    Cheng Jili; Liu Yuan; En Yunfei; Fang Wenxiao; Wei Aixiang; Yang Yuanzhen

    2013-01-01

    In the paper the ways to compute the response of transmission line (TL) illuminated by electromagnetic pulse (EMP) were introduced firstly, which include finite-difference time-domain (FDTD) and trans-mission line matrix (TLM); then the feasibility of electromagnetic topology (EMT) in ICs nuclear electromagnetic pulse (NEMP) effect simulation was discussed; in the end, combined with the methods computing the response of TL, a new method of simulate the transmission line in IC illuminated by NEMP was put forward. (authors)

  19. Integrity of austenitic stainless steel piping welds for nuclear service

    International Nuclear Information System (INIS)

    Canalini, A.; Lopes, L.R.

    1983-01-01

    A criterion applying K 1d concept was developed to determine the fracture mechanics properties of austenitic stainless steel nuclear piping welds. The critical dimensions, lenght and depth, for crack initiation were established and plotted in a chart. This study enables the dimensions of a discontinuity detected in an in-service inspection to be compared to the critical dimensions for crack initiation, and the indication can be judged critical or non-critical for the component. (author) [pt

  20. An integrated nuclear enterprise with 30 years' experience

    International Nuclear Information System (INIS)

    Franklin, N.L.

    1978-01-01

    Over three decades the nuclear industry in Britain has evolved from a research organisation, the United Kingdon Atomic Energy Authority (UKAEA), into an organisation capable of manufacturing, constructing and operating nuclear stations, together with fuel manufacture and reprocessing. Large reserves of coal together with the discovery and exploitation of oil and natural gas in the North Sea have enabled the country to avoid the need for a rapid expansion of nuclear power, but as worldwide reserves of fossil fuels decline towards the end of the century its importance can be expected to incease. The physical capability of the construction industry is therefore being strengthened by the ordering of two further advanced gas cooled reactor (AGR) stations and continued investigation of the pressurised water reactor (PWR) in anticipation of future orders. Within the fuel supply industry further enrichment (centrifuge) capacity has been constructed and a decision has been made to build the THORP plant for the reprocessing of oxide fuel. For the longer term the fast breeder reactor is being developed and the problems here are seen to be social rather than technical, concerned mainly with the question of public acceptability. (Auth.)

  1. Development of an Integrated Education/Training based Nuclear Outreach Model

    International Nuclear Information System (INIS)

    Han, Kyongwon; Nam, Youngmi; Hwang, Ina; Lee, Jisuk; Ko, Hansuk; Lee, Taejoon

    2013-01-01

    The Korean nuclear community also recognizes the importance of outreach from its experience with rad waste and nuclear power programs. Accordingly, nationwide programs dealing with public information, support for local community development, and HRD are implemented continuously involving a number of organizations concerned. The Nuclear Training and Education Center (NTC) of the Korea Atomic Energy Research Institute (KAERI), with its unique function and capability as a national research organization, has needs for the enhancement of public acceptance for KAERI programs, a better contribution to the national effort, and addressing the emerging needs for international education/training on nuclear outreach. This paper presents an integrated education/training based nuclear outreach model with a set of reference program, which is developed for NTC. An integrated education/training based nuclear outreach model for NTC is developed addressing the increasing needs for public acceptance on the peaceful use of nuclear energy, in terms of supporting KAERI activities, contributing to the national nuclear outreach efforts, and promoting international education and training on nuclear outreach. The model, harmonized with the national nuclear outreach system, consists of objectives, target audiences, a set of reference program supported by infrastructure and networking, and an evaluation system. The program is further specified into sub-programs with detailed design for the respective audiences. The developed model with a reference program is characterized by its integrity in terms of encompassing the whole outreach process cycle, and setting up of a target audience based total program structure with existing and new sub-programs. Also, it intends to be sustainable by addressing future generations' needs as well as innovative in the program delivery. The model will be continuously upgraded and applied addressing respective needs of the audiences

  2. Science based integrated approach to advanced nuclear fuel development - vision, approach, and overview

    Energy Technology Data Exchange (ETDEWEB)

    Unal, Cetin [Los Alamos National Laboratory; Pasamehmetoglu, Kemal [IDAHO NATIONAL LAB; Carmack, Jon [IDAHO NATIONAL LAB

    2010-01-01

    Advancing the performance of Light Water Reactors, Advanced Nuclear Fuel Cycles, and Advanced Rcactors, such as the Next Generation Nuclear Power Plants, requires enhancing our fundamental understanding of fuel and materials behavior under irradiation. The capability to accurately model the nuclear fuel systems is critical. In order to understand specific aspects of the nuclear fuel, fully coupled fuel simulation codes are required to achieve licensing of specific nuclear fuel designs for operation. The backbone of these codes, models, and simulations is a fundamental understanding and predictive capability for simulating the phase and microstructural behavior of the nuclear fuel system materials and matrices. The purpose of this paper is to identify the modeling and simulation approach in order to deliver predictive tools for advanced fuels development. The coordination between experimental nuclear fuel design, development technical experts, and computational fuel modeling and simulation technical experts is a critical aspect of the approach and naturally leads to an integrated, goal-oriented science-based R & D approach and strengthens both the experimental and computational efforts. The Advanced Fuels Campaign (AFC) and Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Integrated Performance and Safety Code (IPSC) are working together to determine experimental data and modeling needs. The primary objective of the NEAMS fuels IPSC project is to deliver a coupled, three-dimensional, predictive computational platform for modeling the fabrication and both normal and abnormal operation of nuclear fuel pins and assemblies, applicable to both existing and future reactor fuel designs. The science based program is pursuing the development of an integrated multi-scale and multi-physics modeling and simulation platform for nuclear fuels. This overview paper discusses the vision, goals and approaches how to develop and implement the new approach.

  3. Development of an Integrated Education/Training based Nuclear Outreach Model

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kyongwon; Nam, Youngmi; Hwang, Ina; Lee, Jisuk; Ko, Hansuk; Lee, Taejoon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    The Korean nuclear community also recognizes the importance of outreach from its experience with rad waste and nuclear power programs. Accordingly, nationwide programs dealing with public information, support for local community development, and HRD are implemented continuously involving a number of organizations concerned. The Nuclear Training and Education Center (NTC) of the Korea Atomic Energy Research Institute (KAERI), with its unique function and capability as a national research organization, has needs for the enhancement of public acceptance for KAERI programs, a better contribution to the national effort, and addressing the emerging needs for international education/training on nuclear outreach. This paper presents an integrated education/training based nuclear outreach model with a set of reference program, which is developed for NTC. An integrated education/training based nuclear outreach model for NTC is developed addressing the increasing needs for public acceptance on the peaceful use of nuclear energy, in terms of supporting KAERI activities, contributing to the national nuclear outreach efforts, and promoting international education and training on nuclear outreach. The model, harmonized with the national nuclear outreach system, consists of objectives, target audiences, a set of reference program supported by infrastructure and networking, and an evaluation system. The program is further specified into sub-programs with detailed design for the respective audiences. The developed model with a reference program is characterized by its integrity in terms of encompassing the whole outreach process cycle, and setting up of a target audience based total program structure with existing and new sub-programs. Also, it intends to be sustainable by addressing future generations' needs as well as innovative in the program delivery. The model will be continuously upgraded and applied addressing respective needs of the audiences.

  4. Science based integrated approach to advanced nuclear fuel development - vision, approach, and overview

    International Nuclear Information System (INIS)

    Unal, Cetin; Pasamehmetoglu, Kemal; Carmack, Jon

    2010-01-01

    Advancing the performance of Light Water Reactors, Advanced Nuclear Fuel Cycles, and Advanced Rcactors, such as the Next Generation Nuclear Power Plants, requires enhancing our fundamental understanding of fuel and materials behavior under irradiation. The capability to accurately model the nuclear fuel systems is critical. In order to understand specific aspects of the nuclear fuel, fully coupled fuel simulation codes are required to achieve licensing of specific nuclear fuel designs for operation. The backbone of these codes, models, and simulations is a fundamental understanding and predictive capability for simulating the phase and microstructural behavior of the nuclear fuel system materials and matrices. The purpose of this paper is to identify the modeling and simulation approach in order to deliver predictive tools for advanced fuels development. The coordination between experimental nuclear fuel design, development technical experts, and computational fuel modeling and simulation technical experts is a critical aspect of the approach and naturally leads to an integrated, goal-oriented science-based R and D approach and strengthens both the experimental and computational efforts. The Advanced Fuels Campaign (AFC) and Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Integrated Performance and Safety Code (IPSC) are working together to determine experimental data and modeling needs. The primary objective of the NEAMS fuels IPSC project is to deliver a coupled, three-dimensional, predictive computational platform for modeling the fabrication and both normal and abnormal operation of nuclear fuel pins and assemblies, applicable to both existing and future reactor fuel designs. The science based program is pursuing the development of an integrated multi-scale and multi-physics modeling and simulation platform for nuclear fuels. This overview paper discusses the vision, goals and approaches how to develop and implement the new approach.

  5. Framework for Integrating Safety, Operations, Security, and Safeguards in the Design and Operation of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Darby, John L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Horak, Karl Emanuel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaChance, Jeffrey L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Tolk, Keith Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Whitehead, Donnie Wayne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2007-10-01

    The US is currently on the brink of a nuclear renaissance that will result in near-term construction of new nuclear power plants. In addition, the Department of Energy’s (DOE) ambitious new Global Nuclear Energy Partnership (GNEP) program includes facilities for reprocessing spent nuclear fuel and reactors for transmuting safeguards material. The use of nuclear power and material has inherent safety, security, and safeguards (SSS) concerns that can impact the operation of the facilities. Recent concern over terrorist attacks and nuclear proliferation led to an increased emphasis on security and safeguard issues as well as the more traditional safety emphasis. To meet both domestic and international requirements, nuclear facilities include specific SSS measures that are identified and evaluated through the use of detailed analysis techniques. In the past, these individual assessments have not been integrated, which led to inefficient and costly design and operational requirements. This report provides a framework for a new paradigm where safety, operations, security, and safeguards (SOSS) are integrated into the design and operation of a new facility to decrease cost and increase effectiveness. Although the focus of this framework is on new nuclear facilities, most of the concepts could be applied to any new, high-risk facility.

  6. Integrating complex functions: coordination of nuclear pore complex assembly and membrane expansion of the nuclear envelope requires a family of integral membrane proteins.

    Science.gov (United States)

    Schneiter, Roger; Cole, Charles N

    2010-01-01

    The nuclear envelope harbors numerous large proteinaceous channels, the nuclear pore complexes (NPCs), through which macromolecular exchange between the cytosol and the nucleoplasm occurs. This double-membrane nuclear envelope is continuous with the endoplasmic reticulum and thus functionally connected to such diverse processes as vesicular transport, protein maturation and lipid synthesis. Recent results obtained from studies in Saccharomyces cerevisiae indicate that assembly of the nuclear pore complex is functionally dependent upon maintenance of lipid homeostasis of the ER membrane. Previous work from one of our laboratories has revealed that an integral membrane protein Apq12 is important for the assembly of functional nuclear pores. Cells lacking APQ12 are viable but cannot grow at low temperatures, have aberrant NPCs and a defect in mRNA export. Remarkably, these defects in NPC assembly can be overcome by supplementing cells with a membrane fluidizing agent, benzyl alcohol, suggesting that Apq12 impacts the flexibility of the nuclear membrane, possibly by adjusting its lipid composition when cells are shifted to a reduced temperature. Our new study now expands these findings and reveals that an essential membrane protein, Brr6, shares at least partially overlapping functions with Apq12 and is also required for assembly of functional NPCs. A third nuclear envelope membrane protein, Brl1, is related to Brr6, and is also required for NPC assembly. Because maintenance of membrane homeostasis is essential for cellular survival, the fact that these three proteins are conserved in fungi that undergo closed mitoses, but are not found in metazoans or plants, may indicate that their functions are performed by proteins unrelated at the primary sequence level to Brr6, Brl1 and Apq12 in cells that disassemble their nuclear envelopes during mitosis.

  7. Integral charged particle nuclear data bibliography: Literature scanned from April 11, 1987 through November 10, 1988

    International Nuclear Information System (INIS)

    Holden, N.E.; Ramavataram, S.

    1988-12-01

    This publication is the annual supplement to the first edition published in 1984. The primary goal of this publication has been to satisfy the need expressed by the Nuclear Reaction Data Center Network for a concise and comprehensive bibliography of integral charged-particle cross section data. The reader is referred to a partial list of other bibliographies relevant to charged-particle-induced reaction data and to ''A Source List of Nuclear Data Bibliographies, Compilations, and Evaluations'' for a more comprehensive list. Since this publication is not cumulative, earlier versions are also shown in this paper. This publication makes use of a modification to the database of the Nuclear Structure References (NSR) file. This modification allows the retrieval of integral charged particle nuclear data entries from the NSR file. In recent years, the presentation of various sections was changed, as a result of users' suggestions. The authors continue to welcome users' comments. 190 refs., 3 tabs

  8. Integrating security issues in nuclear engineering curriculum in Indonesia. Classical vs policy approaches

    International Nuclear Information System (INIS)

    Putero, Susetyo Hario; Rosita, Widya; Sihana, Fnu; Ferdiansjah; Santosa, Haryono Budi; Muharini, Anung

    2015-01-01

    Recently, risk management for nuclear facilities becomes more complex due to security issue addressed by IAEA. The harmonization between safety, safeguards and security is still questionable. It also challenges to nuclear engineering curriculum in the world how to appropriately lecture the new issue. This paper would like to describe how to integrate this issue in developing nuclear engineering curriculum in Indonesia. Indonesia has still no nuclear power plant, but there are 3 research reactors laid in Indonesia. As addition, there are several hospitals and industries utilizing radioisotopes in their activities. The knowledge about nuclear security of their staffs is also not enough for handling radioactive material furthermore the security officers. Universitas Gadjah Mada (UGM) is the only university in Indonesia offering nuclear engineering program, as consequently the university should actively play the role in overcoming this issue not only in Indonesia, but also in Southeast Asia. In the other hand, students has to have proper knowledge in order to complete in the global nuclear industry. After visited several universities in USA and participated in INSEN meeting, we found that most of universities in the world anticipate this issue by giving the student courses related to policy (non-technical) study based on IAEA NSS 12. In the other hand, the rest just make nuclear security as a case study on their class. Furthermore, almost all of programs are graduate level. UGM decided to enhance several present related undergraduate courses with security topics as first step to develop the awareness of student to nuclear security. The next (curriculum 2016) is to integrate security topics into the entire of curriculum including designing a nuclear security elective course for undergraduate level. The first trial has successfully improved the student knowledge and awareness on nuclear security. (author)

  9. Comment for nuclear data from the FNS integral experiments

    International Nuclear Information System (INIS)

    Maekawa, Hiroshi

    1983-01-01

    Among the integral experiments that were carried out during last one year at FNS, the following three experimental results and their analyses are discribed. 1) Tritium production-rate distribution in a Li 2 O-C assembly, 2) Angle dependent neutron leakage spectra from Li 2 O slab assemblies, 3) Induced activity of Type 316 stainless steel. (author)

  10. An integrated pusher-guide-boat for ship nuclear propulsion

    International Nuclear Information System (INIS)

    Baujat, Jacques.

    1974-01-01

    The pusher guide-boat is characterized in that it comprises a streamlined enclosure with a front surface and an upper surface, containing a nuclear-power generating plant and means for converting the thus-generated power into mechanical energy used for actuating the pusher-boat propelling parts situated rearwardly, and in that the streamlined enclosure comprises, on its front surface and on at least a portion of its upper surface, areas for the contact thereof with respective portions of the vessel driven by said pusher-boat and means for fastening the latter to the vessel, said pusher-boat being also provided with water-ballasts [fr

  11. Pellet bed reactor for nuclear propelled vehicles: Part 2: Missions and vehicle integration trades

    International Nuclear Information System (INIS)

    Haloulakos, V.E.

    1991-01-01

    Mission and vehicle integration tradeoffs involving the use of the pellet bed reactor (PBR) for nuclear powered vehicles is discussed, with much of the information being given in viewgraph form. Information is given on propellant tank geometries, shield weight requirements for conventional tank configurations, effective specific impulse, radiation mapping, radiation dose rate after shutdown, space transfer vehicle design data, a Mars mission summary, sample pellet bed nuclear orbit transfer vehicle mass breakdown, and payload fraction vs. velocity increment

  12. Pellet bed reactor for nuclear propelled vehicles: Part 2: Missions and vehicle integration trades

    Science.gov (United States)

    Haloulakos, V. E.

    1991-01-01

    Mission and vehicle integration tradeoffs involving the use of the pellet bed reactor (PBR) for nuclear powered vehicles is discussed, with much of the information being given in viewgraph form. Information is given on propellant tank geometries, shield weight requirements for conventional tank configurations, effective specific impulse, radiation mapping, radiation dose rate after shutdown, space transfer vehicle design data, a Mars mission summary, sample pellet bed nuclear orbit transfer vehicle mass breakdown, and payload fraction vs. velocity increment.

  13. Integrated solidity test measurement of the airtight compartment system at the Paks nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Osztheimer, M.; Taubner, R.; Techy, Zs. (Villamosenergiaipari Kutato Intezet, Budapest (Hungary))

    1983-01-01

    A brief report on the purpose of the integrated solidity test measurements of the airtight compartment system of the Paks nuclear power plant and on the applied measuring principles is given. The measuring system and the selected measuring methods are evaluated. The characteristic features of the airtight system of the Paks nuclear power plant's 1st block and their effects on the measurement are mentioned.

  14. Nuclear agriculture and biotechnology: integrated approaches for crop improvement

    International Nuclear Information System (INIS)

    Suprasanna, P.; Venugopalan, V.

    2017-01-01

    Use of radiation and radioisotopes in agriculture is one of the most important fields of peaceful applications of atomic energy for societal benefit. They are used to induce genetic variability in crop plants to develop improved mutant varieties, to manage insect pests, to monitor fate and persistence of pesticides, to study fertilizer use efficiency and plant micronutrient uptake and also to preserve agricultural produce. So far, BARC has developed and released 42 Trombay mutant varieties in oilseeds (groundnut, mustard, soybean, sunflower), pulses (pigeonpea, blackgram, greengram, cowpea), rice and jute for commercial cultivation across the nation. Mutant characterization has been benefitted by genomics approaches and availability of crop genome sequencing. In this regard, studies are underway to utilize mutant germplasm for molecular characterization and understanding trait modification. The nuclear technologies have benefited the farmers, traders and end-users and will continue to play a significant role in addressing food and nutritional security. In this presentation, an overview will be given on the activities of the NABTD in the field of nuclear agriculture and biotechnology

  15. Integral logistics of the nuclear fuel Factory Juzbado

    International Nuclear Information System (INIS)

    Perez, P.

    2015-01-01

    The Logistic considers the complete process since the determination of possible demand, production planning, materials procurement, production control and delivery of final products to customer. This complete process is managed in all the scope under the same department called Planning and Logistic. This integration, some times really complex, has allowed to Enusa factory control all the key aspects that allow its running completely, considering the synergy's and important advantages to solve different problems. This article describes how we work of the main areas of procurement, production planning and control, fuel delivery and project planning of improvements on equipment's and factory systems, with an integrated management of all of them under the same direction. (Author)

  16. Space and Terrestrial Power System Integration Optimization Code BRMAPS for Gas Turbine Space Power Plants With Nuclear Reactor Heat Sources

    Science.gov (United States)

    Juhasz, Albert J.

    2007-01-01

    In view of the difficult times the US and global economies are experiencing today, funds for the development of advanced fission reactors nuclear power systems for space propulsion and planetary surface applications are currently not available. However, according to the Energy Policy Act of 2005 the U.S. needs to invest in developing fission reactor technology for ground based terrestrial power plants. Such plants would make a significant contribution toward drastic reduction of worldwide greenhouse gas emissions and associated global warming. To accomplish this goal the Next Generation Nuclear Plant Project (NGNP) has been established by DOE under the Generation IV Nuclear Systems Initiative. Idaho National Laboratory (INL) was designated as the lead in the development of VHTR (Very High Temperature Reactor) and HTGR (High Temperature Gas Reactor) technology to be integrated with MMW (multi-megawatt) helium gas turbine driven electric power AC generators. However, the advantages of transmitting power in high voltage DC form over large distances are also explored in the seminar lecture series. As an attractive alternate heat source the Liquid Fluoride Reactor (LFR), pioneered at ORNL (Oak Ridge National Laboratory) in the mid 1960's, would offer much higher energy yields than current nuclear plants by using an inherently safe energy conversion scheme based on the Thorium --> U233 fuel cycle and a fission process with a negative temperature coefficient of reactivity. The power plants are to be sized to meet electric power demand during peak periods and also for providing thermal energy for hydrogen (H2) production during "off peak" periods. This approach will both supply electric power by using environmentally clean nuclear heat which does not generate green house gases, and also provide a clean fuel H2 for the future, when, due to increased global demand and the decline in discovering new deposits, our supply of liquid fossil fuels will have been used up. This is

  17. Mitigating Capability Analysis during LOCA for Korean Standard Nuclear Power Plants in Containment Integrity

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Young; Park, Soo Yong; Kim, D. H.; Song, Y. M. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    The objective of this paper is to establish Containment spray operational technical bases for the typical Korean Standard Nuclear Power plants (Ulchin units 3 and 4) by modeling the plant, and analyzing a loss of coolant accident (LOCA) using the MAAP code. The severe accident phenomena at nuclear power plants have large uncertainties. For the integrity of the reactor vessel and containment safety against severe accidents, it is essential to understand severe accident sequences and to assess the accident progression accurately by computer codes. Furthermore, it is important to attain the capability to analyze a advanced nuclear reactor design for a severe accident prevention and mitigation.

  18. Application of integrated computer-aided engineering for design, construction and operation of nuclear power plant

    International Nuclear Information System (INIS)

    Kyung-shick Min; Byung-hun Lee

    1987-01-01

    Computer-aided-engineering (CAE) is an essential tool for modern nuclear power plant engineering. It greatly varies in definition, application, and technology from project to project and company to company. Despite the fast growing technologies and applications of CAE, its complexty and variety have thrown aonther puzzle to management of a nuclear project. Without due consideration of an integrated CAE system in early planning stage, the overall efficiency of a nuclear project would slow down due to the inefficiency in data flow. In this paper, practices and perspectives of CAE appliation are discussed under the Korea Power Engineering Company (KOPEC) philosophy in CAE approach. (author)

  19. Integration of PACS and HIS info the workflow of a nuclear medicine department. Experience in Regensburg

    International Nuclear Information System (INIS)

    Maenner, P.; Fuchs, E.; Marienhagen, J.; Schoenberger, J.; Eilles, C.; Tege, B.; Reicherzer, H.G.; Kurz, M.; Boerner, W.

    2006-01-01

    Aim: the development of new diagnostic techniques and the implementation of a modern quality control management system requires the continuous adaptation of existing data processing tools to the nuclear medicine diagnostic workflow. Furthermore, PACS connected to HIS facilitates and enhances the transfer of data and pictures, and satisfies the legal requirements for data retention as regulated by law. Therefore, the aim of this work is to present the architecture, structure and results of such a system newly installed in a department of nuclear medicine. Methods: initially, the nuclear medicine workflow was carefully analyzed and each step was correlated to the corresponding module. The standard SAP R/3 and IS-H / IS-H*med based software used for patient administration at the University of Regensburg Hospital was adapted to the needs of the Nuclear Medicine Department. The networking of the imaging systems was done by integration of a PACS. Finally, the PACS was connected to the HIS to allow the attachment of images to the medical report. Results, conclusion: by connecting the HIS to the nuclear medicine PACS, the workflow was significantly improved. The data management sequence starting at the reception desk, continuing through the nuclear medical examination, to the physician's final written and image report is clearly structured. Although high demands exist on technical support and administration the integration of PACS and HIS into the nuclear medicine workflow leads to enhanced efficiency and reduction in hospital costs. Patient and data management are considerably improved in this way. (orig.)

  20. Integrated services and maintenance in nuclear power plants

    International Nuclear Information System (INIS)

    Roos, Georg

    2001-01-01

    The general situation concerning services and nuclear power maintenance is reviewed following liberalization of Europa's power market. Issues relating to outsourcing maintenance services, effectiveness and reducing cost structure of maintenance are addressed on the cases of power markets in northern countries, Spain, Switzerland, Germany and Hungary. A special attention is paid on range of maintenance activity offered and performanced by Framatome. Ways of reducing costs in the field of maintenance as well as of reducing outage time are indicated. In conclusion, the following items are emphasized: - liberalization of Europe's power market in eastern Europe at its beginning; - in-house service in eastern Europe with numerous personnel; - Framatome ANP covers the entire range of maintenance competence; - consultance can be the first approach for a common co-operation

  1. Integrated approach to optimize operation and maintenance costs for operating nuclear power plants

    International Nuclear Information System (INIS)

    2006-06-01

    In the context of increasingly open electricity markets and the 'unbundling' of generating companies from former utility monopolies, an area of major concern is the economic performance of the existing fleet of nuclear power plants. Nuclear power, inevitably, must compete directly with other electricity generation sources. Coping with this competitive pressure is a challenge that the nuclear industry should meet if the nuclear option is to remain a viable one. This competitive environment has significant implications for nuclear plant operations, including, among others, the need for the more cost effective management of plant activities, and the greater use of analytical tools to balance the costs and benefits of proposed activities, in order to optimize operation and maintenance costs, and thus insure the economic competitiveness of existing nuclear power plants. In the framework of the activities on Nuclear Economic Performance Information System (NEPIS), the IAEA embarked in developing guidance on optimization of operation and maintenance costs for nuclear power plants. The report was prepared building on the fundamental that optimization of operation and maintenance costs of a nuclear power plant is a key component of a broader integrated business strategic planning process, having as overall result achievement of organization's business objectives. It provides advice on optimization of O and M costs in the framework of strategic business planning, with additional details on operational planning and controlling. This TECDOC was elaborated in 2004-2005 in the framework of the IAEA's programme on Nuclear Power Plant Operating Performance and Life Cycle Management, with the support of two consultants meetings and one technical meeting and based on contributions provided by participants. It can serve as a useful reference for the management and operation staff within utilities, nuclear power plant operators and regulators and other organizations involved in

  2. Intelligence and Physical Attractiveness

    Science.gov (United States)

    Kanazawa, Satoshi

    2011-01-01

    This brief research note aims to estimate the magnitude of the association between general intelligence and physical attractiveness with large nationally representative samples from two nations. In the United Kingdom, attractive children are more intelligent by 12.4 IQ points (r=0.381), whereas in the United States, the correlation between…

  3. Assertiveness and Physical Attractiveness.

    Science.gov (United States)

    Kleim, David M.; And Others

    Earlier research investigating the relationship between physical attractiveness and assertiveness found that physically attractive females were more assertive than other females. To investigate this relationship further and to broaden the scope of the study, 69 students were videotaped in groups of five to ten while responding to open-ended…

  4. NMC and A and nuclear criticality safety systems integration: A prospective way for enhancement of the nuclear industry facilities safety

    International Nuclear Information System (INIS)

    Ryazanov, Boris G.; Sviridov, Victor I.; Frolov, Vladimir V.; Shvedov, Maxim O.; Mclaughlin, Thomas P.; Pruvost, Norman L.

    2003-01-01

    the necessity and usefulness of integrating measures and components of MC and A and nuclear safety systems to meet the goals faced by both systems. (author)

  5. Hypertext-based integration for nuclear plant maintenance and operations

    International Nuclear Information System (INIS)

    Tsoukalas, L.H.; Upadhyaya, B.R.

    1991-01-01

    A methodology is presented that uses fuzzy graphs in the emerging paradigm of hypertext for the purpose of integrating data, information and multifaceted knowledge resources abounding in power plant operations and maintenance. A hypertext system is viewed as a set of nodes and links where with each link we associate membership functions embodying context-dependent criteria for navigating large information spaces. A general framework for navigation is outlined and graph-theory navigational tools are developed. A numerical example and a HyperCard-based prototype for monitoring special material in the MHTGR-NPR are included. 10 refs., 12 figs

  6. Integrated management platform of nuclear fuel storage and transportation based on RFID

    International Nuclear Information System (INIS)

    Song Yafeng; Ma Yanqin; Chen Liyu; Jiang Yong; Wu Jianlei; Yang Haibo; Zhang Haiyan

    2012-01-01

    This paper describes integrated system model to improve work efficiency and optimize control measures of nuclear fuel storage and transportation, RFID and information integration technology is introduced, traditional management processes are innovated in data acquisition and monitoring fields as well, system solutions and design model are given by emphasizing on the following key technologies: cascade protection of information system, security protocol of RFID information, algorithm of collision. (authors)

  7. A comparison of integrated and fiber optic responses in the presence of nuclear fields

    International Nuclear Information System (INIS)

    Taylor, E.W.; Wilson, V.R.; Sanchez, A.D.; Coughenour, M.; Chapman, S.

    1988-01-01

    A short survey of past experimental results is presented along with new investigative data, mathematical and physical response models and a comparison of the nuclear effects compatibility of fiber and integrated optic guided wave structures. The disparity in radiation resistance between optical fibers and guided wave structures is discussed and predictions are offered on the impact that these differences may have on influencing the eventual development of totally integrated radiation resistant structures

  8. The innovation and practice of management improved by integration management information system in nuclear enterprise

    International Nuclear Information System (INIS)

    Zhang Fan; Cheng Lihong; Li Qisheng; Ge Zhengfa

    2012-01-01

    This article expounds that Hunan Taohuajiang Nuclear Power Company generally programs the route of company's core business and implements its integration through referencing the experience of informationization construction of other enterprises at the beginning of the foundation of this company, and summarizes the experience of system construction and analyses the innovation and signification of the integrative management information system to the nu- clear power enterprise management from data unified, resources sharing and business electronic and the management improvement of this company. (authors)

  9. Initial estimates of the economical attractiveness of a nuclear closed Brayton combined cycle operating with firebrick resistance-heated energy storage

    Directory of Open Access Journals (Sweden)

    Florian Chavagnat

    2018-04-01

    Full Text Available The Firebrick Resistance-Heated Energy Storage (FIRES concept developed by the Massachusetts Institute of Technology aims to enhance profitability of the nuclear power industry in the next decades. Studies carried out at Massachusetts Institute of Technology already provide estimates of the potential revenue from FIRES system when it is applied to industrial heat supply, the likely first application. Here, we investigate the possibility of operating a power plant (PP with a fluoride-salt-cooled high-temperature reactor and a closed Brayton cycle. This variant offers features such as enhanced nuclear safety as well as flexibility in design of the PP but also radically changes the way of operating the PP. This exploratory study provides estimates of the revenue generated by FIRES in addition to the nominal revenue of the stand-alone fluoride-salt-cooled high-temperature reactor, which are useful for defining an initial design. The electricity price data is based on the day-ahead markets of Germany/Austria and the United States (Iowa. The proposed method derives from the equation of revenue introduced in this study and involves simple computations using MatLab to compute the estimates. Results show variable economic potential depending on the host grid but stress a high profitability in both regions. Keywords: Firebrick Resistance-Heated Energy Storage, Nuclear Power Plant, Revenue Estimate, Storage System

  10. Implementation of integrated safeguards in Nuclear Fuel Plant at Pitesti, Romania

    International Nuclear Information System (INIS)

    Olaru, V.; Ivana, T.; Epure, Gh.

    2009-01-01

    The nuclear activity was conducted for many years in Romania under Traditional Safeguards (TS) and has developed in good conditions the specific nuclear safeguards. Now there is a good opportunity to improve the performance and quality of the safeguards activity and at the same time to increase the accountancy and control of nuclear materials by passing to Integrated Safeguards (IS) implementation. The legal framework is the Law 100/2000 for ratification of the Protocol between Romania and International Atomic Energy Agency (IAEA), additional completion to the Agreement between the Socialist Republic of Romania Government and IAEA relating to safeguards. It is part of the Treaty on the non-proliferation of nuclear weapons published in the Official Gazette no. 3/31 January 1970, and the Additional Protocol published in the Official Gazette no. 295/ 29.06.2000. The first discussion about Integrated Safeguards (IS) between the Nuclear Fuel Plant (FCN) representatives and IAEA inspectors has taken place in June 2005. In Feb. 2007 an IAEA mission visited FCN and established the main steps for implementing the IS. There were visited the storage and the technological flow and it was reviewed the residence times for different nuclear materials, the applied chemical analysis, metrological methods, weighting method and procedures of elaborating the implied documents and lists. At the same time the IAEA and FCN representatives established the main points for implementing the IS at FCN i.e. performing the Short Notice Random Inspections (SNRI), communicating the eligible days for SNRI for each year, communicating the estimated deliveries and shipments for the first quarter and then for the rest of the year, mail box daily declaration (DD) with respect to the residence time for several nuclear materials, advance notification (AN) for each nuclear material transfer (shipments and receipts), etc. At 01 June 2007 Romania has passed officially to Integrated Safeguards and FCN (RO

  11. Integrated management for aging of Atucha Nuclear Power Plant

    International Nuclear Information System (INIS)

    Ranalli, J.M.; Marchena, M.H.; Sabransky, M.; Fonseca, M.; Santich, J.; Pedernera, P.

    2012-01-01

    Atucha NPP is a two PHWR unit site located in Lima, Province of Buenos Aires, 120 km north of Buenos Aires, Argentina.. With the start-up of Atucha II and aiming to integrate the Ageing Management of the plants, the Utility (Nucleolectrica Argentina Sociedad Anonima - NASA) created an Ageing Management Department to cope with all ageing issues of both Atucha I and II. In this project both organization has formed a joint working group. The role of CNEA is providing technical support to the plant in the development of procedures a methodological framework for the Ageing Management Program of Atucha NPP. The main documents that have being issued so far are: . An Ageing Management Manual, including standard definition of Materials, Ageing Related Degradation Mechanisms, Operation Environments customized for Atucha NPP. . Walk down procedures and checklists aimed to systematize data collection during outages. . Procedures for performing Ageing Management Reviews and Maintenance Reviews for passive and active components. . Condition Assessments of several safety related systems. . Condition assessment of electrical components. In the present work a summary of the activities, documental structure and first outputs of the Integrated Ageing Management Program of Atucha NPP is presented (author)

  12. Application of contemporary integrated manufacture systems to nuclear power plants management

    International Nuclear Information System (INIS)

    Zhou Gang; Wang Lushuai; Tang Yaoyang

    2005-01-01

    In order to improve the safety, economy and reliability of the operation of a nuclear power plant (NPP), a novel integrated management method is proposed based on the 'integration' concept of the computer and contemporary integrated manufacture systems (CIMS). The design of integrated management system for NPP is studied. In the design of this system, information integration method based on the database and product data management (PDM) technology is adopted. In order to design and integrated management system satisfying the needs of NPP management, all activities of NPP are divided into different categories according to its characteristics. There are subsystems under the general management system to conduct the management work of different categories. All subsystems are interrelated in the environment of CIMS, but relatively independent. The application of CIMS to NPP provides a new way for scientific management of NPP, and makes the best of human, material and information resources. (authors)

  13. An integrated system for large scale scanning of nuclear emulsions

    Energy Technology Data Exchange (ETDEWEB)

    Bozza, Cristiano, E-mail: kryss@sa.infn.it [University of Salerno and INFN, via Ponte Don Melillo, Fisciano 84084 (Italy); D’Ambrosio, Nicola [Laboratori Nazionali del Gran Sasso, S.S. 17 BIS km 18.910, Assergi (AQ) 67010 (Italy); De Lellis, Giovanni [University of Napoli and INFN, Complesso Universitario di Monte Sant' Angelo, via Cintia Ed. G, Napoli 80126 (Italy); De Serio, Marilisa [University of Bari and INFN, via E. Orabona 4, Bari 70125 (Italy); Di Capua, Francesco [INFN Napoli, Complesso Universitario di Monte Sant' Angelo, via Cintia Ed. G, Napoli 80126 (Italy); Di Crescenzo, Antonia [University of Napoli and INFN, Complesso Universitario di Monte Sant' Angelo, via Cintia Ed. G, Napoli 80126 (Italy); Di Ferdinando, Donato [INFN Bologna, viale B. Pichat 6/2, Bologna 40127 (Italy); Di Marco, Natalia [Laboratori Nazionali del Gran Sasso, S.S. 17 BIS km 18.910, Assergi (AQ) 67010 (Italy); Esposito, Luigi Salvatore [Laboratori Nazionali del Gran Sasso, now at CERN, Geneva (Switzerland); Fini, Rosa Anna [INFN Bari, via E. Orabona 4, Bari 70125 (Italy); Giacomelli, Giorgio [University of Bologna and INFN, viale B. Pichat 6/2, Bologna 40127 (Italy); Grella, Giuseppe [University of Salerno and INFN, via Ponte Don Melillo, Fisciano 84084 (Italy); Ieva, Michela [University of Bari and INFN, via E. Orabona 4, Bari 70125 (Italy); Kose, Umut [INFN Padova, via Marzolo 8, Padova (PD) 35131 (Italy); Longhin, Andrea; Mauri, Nicoletta [INFN Laboratori Nazionali di Frascati, via E. Fermi 40, Frascati (RM) 00044 (Italy); Medinaceli, Eduardo [University of Padova and INFN, via Marzolo 8, Padova (PD) 35131 (Italy); Monacelli, Piero [University of L' Aquila and INFN, via Vetoio Loc. Coppito, L' Aquila (AQ) 67100 (Italy); Muciaccia, Maria Teresa; Pastore, Alessandra [University of Bari and INFN, via E. Orabona 4, Bari 70125 (Italy); and others

    2013-03-01

    The European Scanning System, developed to analyse nuclear emulsions at high speed, has been completed with the development of a high level software infrastructure to automate and support large-scale emulsion scanning. In one year, an average installation is capable of performing data-taking and online analysis on a total surface ranging from few m{sup 2} to tens of m{sup 2}, acquiring many billions of tracks, corresponding to several TB. This paper focuses on the procedures that have been implemented and on their impact on physics measurements. The system proved robust, reliable, fault-tolerant and user-friendly, and seldom needs assistance. A dedicated relational Data Base system is the backbone of the whole infrastructure, storing data themselves and not only catalogues of data files, as in common practice, being a unique case in high-energy physics DAQ systems. The logical organisation of the system is described and a summary is given of the physics measurement that are readily available by automated processing.

  14. Thermal integration of SCWR nuclear and thermochemical hydrogen plants

    International Nuclear Information System (INIS)

    Wang, Z.; Naterer, G.F.; Gabriel, K.S.

    2010-01-01

    In this paper, the intermediate heat exchange between a Generation IV supercritical water-cooled nuclear reactor (SCWR) and a thermochemical hydrogen production cycle is discussed. It is found that the maximum and range of temperatures of a thermochemical cycle are the dominant parameters that affect the design of its coupling with SCWR. The copper-chlorine (Cu-Cl) thermochemical cycle is a promising cycle that can link with SCWRs. The location of extracting heat from a SCWR to a thermochemical cycle is investigated in this paper. Steam bypass lines downstream of the SCWR core are suggested for supplying heat to the Cu-Cl hydrogen production cycle. The stream extraction location is strongly dependent on the temperature requirements of the chemical steps of the thermochemical cycle. The available quantity of heat exchange at different hours of a day is also studied. It is found that the available heat at most hours of power demand in a day can support an industrial scale steam methane reforming plant if the SCWR power station is operating at full design capacity. (author)

  15. An integrated system for large scale scanning of nuclear emulsions

    International Nuclear Information System (INIS)

    Bozza, Cristiano; D’Ambrosio, Nicola; De Lellis, Giovanni; De Serio, Marilisa; Di Capua, Francesco; Di Crescenzo, Antonia; Di Ferdinando, Donato; Di Marco, Natalia; Esposito, Luigi Salvatore; Fini, Rosa Anna; Giacomelli, Giorgio; Grella, Giuseppe; Ieva, Michela; Kose, Umut; Longhin, Andrea; Mauri, Nicoletta; Medinaceli, Eduardo; Monacelli, Piero; Muciaccia, Maria Teresa; Pastore, Alessandra

    2013-01-01

    The European Scanning System, developed to analyse nuclear emulsions at high speed, has been completed with the development of a high level software infrastructure to automate and support large-scale emulsion scanning. In one year, an average installation is capable of performing data-taking and online analysis on a total surface ranging from few m 2 to tens of m 2 , acquiring many billions of tracks, corresponding to several TB. This paper focuses on the procedures that have been implemented and on their impact on physics measurements. The system proved robust, reliable, fault-tolerant and user-friendly, and seldom needs assistance. A dedicated relational Data Base system is the backbone of the whole infrastructure, storing data themselves and not only catalogues of data files, as in common practice, being a unique case in high-energy physics DAQ systems. The logical organisation of the system is described and a summary is given of the physics measurement that are readily available by automated processing

  16. INIR: Integrated Nuclear Infrastructure Review Missions. Guidance on Preparing and Conducting INIR Missions (Rev. 1)

    International Nuclear Information System (INIS)

    2011-04-01

    The IAEA's Integrated Nuclear Infrastructure Review (INIR) missions are designed to assist Member States, at their request, in evaluating the status of their national infrastructure for the introduction of a nuclear power programme. Each INIR mission is coordinated and led by the IAEA and conducted by a team of international experts drawn from Member States who have experience in different aspects of developing and deploying nuclear infrastructure. The IAEA publication Milestones in the Development of a National Infrastructure for Nuclear Power (IAEA Nuclear Energy Series No. NG-G-3.1) contains a description of 19 infrastructure issues to be considered during the different stages of development of a nuclear power programme. The starting point for an INIR mission is a self-evaluation performed by the Member State against these infrastructure issues. Following the self-evaluation, the INIR mission reviews the status of the national nuclear infrastructure, identifies existing gaps in specific infrastructure-related areas and proposes recommendations to fill these gaps. The INIR mission provides Member State representatives with an opportunity to have in depth discussions with international experts about experiences and best practices in different countries. In developing its recommendations, the INIR team takes into account the comments made by the relevant national organizations. Implementation of any of the team's recommendations is at the discretion of the Member State requesting the mission. The results of the INIR mission are expected to help the Member State to develop an action plan to fill any gaps, which in turn will help the development of the national nuclear infrastructure. The IAEA stands ready to assist, as requested and appropriate, in the different steps of this action plan. This guidance publication is directed to assist in preparing and conducting the INIR missions. It was developed under the coordination of the IAEA Integrated Nuclear Infrastructure

  17. The role of actinide burning and the Integral Fast Reactor in the future of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Hollaway, W.R.; Lidsky, L.M.; Miller, M.M.

    1990-12-01

    A preliminary assessment is made of the potential role of actinide burning and the Integral Fast Reactor (IFR) in the future of nuclear power. The development of a usable actinide burning strategy could be an important factor in the acceptance and implementation of a next generation of nuclear power. First, the need for nuclear generating capacity is established through the analysis of energy and electricity demand forecasting models which cover the spectrum of bias from anti-nuclear to pro-nuclear. The analyses take into account the issues of global warming and the potential for technological advances in energy efficiency. We conclude, as do many others, that there will almost certainly be a need for substantial nuclear power capacity in the 2000--2030 time frame. We point out also that any reprocessing scheme will open up proliferation-related questions which can only be assessed in very specific contexts. The focus of this report is on the fuel cycle impacts of actinide burning. Scenarios are developed for the deployment of future nuclear generating capacity which exploit the advantages of actinide partitioning and actinide burning. Three alternative reactor designs are utilized in these future scenarios: The Light Water Reactor (LWR); the Modular Gas-Cooled Reactor (MGR); and the Integral Fast Reactor (FR). Each of these alternative reactor designs is described in some detail, with specific emphasis on their spent fuel streams and the back-end of the nuclear fuel cycle. Four separation and partitioning processes are utilized in building the future nuclear power scenarios: Thermal reactor spent fuel preprocessing to reduce the ceramic oxide spent fuel to metallic form, the conventional PUREX process, the TRUEX process, and pyrometallurgical reprocessing.

  18. The role of actinide burning and the Integral Fast Reactor in the future of nuclear power

    International Nuclear Information System (INIS)

    Hollaway, W.R.; Lidsky, L.M.; Miller, M.M.

    1990-12-01

    A preliminary assessment is made of the potential role of actinide burning and the Integral Fast Reactor (IFR) in the future of nuclear power. The development of a usable actinide burning strategy could be an important factor in the acceptance and implementation of a next generation of nuclear power. First, the need for nuclear generating capacity is established through the analysis of energy and electricity demand forecasting models which cover the spectrum of bias from anti-nuclear to pro-nuclear. The analyses take into account the issues of global warming and the potential for technological advances in energy efficiency. We conclude, as do many others, that there will almost certainly be a need for substantial nuclear power capacity in the 2000--2030 time frame. We point out also that any reprocessing scheme will open up proliferation-related questions which can only be assessed in very specific contexts. The focus of this report is on the fuel cycle impacts of actinide burning. Scenarios are developed for the deployment of future nuclear generating capacity which exploit the advantages of actinide partitioning and actinide burning. Three alternative reactor designs are utilized in these future scenarios: The Light Water Reactor (LWR); the Modular Gas-Cooled Reactor (MGR); and the Integral Fast Reactor (FR). Each of these alternative reactor designs is described in some detail, with specific emphasis on their spent fuel streams and the back-end of the nuclear fuel cycle. Four separation and partitioning processes are utilized in building the future nuclear power scenarios: Thermal reactor spent fuel preprocessing to reduce the ceramic oxide spent fuel to metallic form, the conventional PUREX process, the TRUEX process, and pyrometallurgical reprocessing

  19. Nuclear Energy Advanced Modeling and Simulation (NEAMS) Waste Integrated Performance and Safety Codes (IPSC) : FY10 development and integration.

    Energy Technology Data Exchange (ETDEWEB)

    Criscenti, Louise Jacqueline; Sassani, David Carl; Arguello, Jose Guadalupe, Jr.; Dewers, Thomas A.; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Wang, Yifeng; Schultz, Peter Andrew

    2011-02-01

    This report describes the progress in fiscal year 2010 in developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. Waste IPSC activities in fiscal year 2010 focused on specifying a challenge problem to demonstrate proof of concept, developing a verification and validation plan, and performing an initial gap analyses to identify candidate codes and tools to support the development and integration of the Waste IPSC. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. This year-end progress report documents the FY10 status of acquisition, development, and integration of thermal-hydrologic-chemical-mechanical (THCM) code capabilities, frameworks, and enabling tools and infrastructure.

  20. Guidelines for Preparing and Conducting an Integrated Nuclear Infrastructure Review (INIR)

    International Nuclear Information System (INIS)

    2017-01-01

    Development of a National Infrastructure for Nuclear Power, which was revised in 2015. To facilitate the application of the Milestones approach, the IAEA developed the Integrated Nuclear Infrastructure Review (INIR), which is a holistic peer review to assist Member States in assessing the status of their national infrastructure for the introduction or expansion of nuclear power. Since the first INIR mission in 2009, the IAEA has conducted missions in 16 embarking countries upon their request. The service enables representatives of the host Member State to have in-depth discussions with a team of IAEA and international experts on experiences and best practices in nuclear power infrastructure development. Recommendations and suggestions are provided in a report to the Member State, enabling it to update its national action plan accordingly. The service is a valuable tool to ensure that the infrastructure required for the safe, secure and sustainable use of nuclear power is developed and implemented in a responsible and orderly mannerThis publication updates INIR: Integrated Nuclear Infrastructure Review Missions — Guidance on Preparing and Conducting INIR Missions (Rev. 1). It takes into account the feedback from Member States who have hosted INIR missions, as well as contributions from IAEA staff and external experts familiar with the programme and process of the INIR service provided by the IAEA.

  1. Application specific integrated circuits and hybrid micro circuits for nuclear instrumentation

    International Nuclear Information System (INIS)

    Chandratre, V.B.; Sukhwani, Menka; Mukhopadhyay, P.K.; Shastrakar, R.S.; Sudheer, M.; Shedam, V.; Keni, Anubha

    2009-01-01

    Rapid development in semiconductor technology, sensors, detectors and requirements of high energy physics experiments as well as advances in commercially available nuclear instruments have lead to challenges for instrumentation. These challenges are met with development of Application Specific Integrated Circuits and Hybrid Micro Circuits. This paper discusses various activities in ASIC and HMC development in Bhabha Atomic Research Centre. (author)

  2. Multi-fields' coordination information integrated platform for nuclear power plant operation preparation

    International Nuclear Information System (INIS)

    Yuan Chang; Li Yong; Ye Zhiqiang

    2011-01-01

    To realize the coordination in multi-fields' work and information sharing, by applying the method of Enterprise Architecture (EA), the business architecture, functional flow and application architecture of Nuclear Power Plant's operation preparation information integrated platform are designed, which can realize the information sharing and coordination of multi fields. (authors)

  3. Effects of Quantum Nuclear Delocalisation on NMR Parameters from Path Integral Molecular Dynamics

    Czech Academy of Sciences Publication Activity Database

    Dračínský, Martin; Hodgkinson, P.

    2014-01-01

    Roč. 20, č. 8 (2014), s. 2201-2207 ISSN 0947-6539 Grant - others:Seventh Framework Programme of the European Union(XE) FP7-299242 People Institutional support: RVO:61388963 Keywords : density functional calculations * isotope effects * NMR spectroscopy * nuclear delocalisation * path integral molecular dynamics Subject RIV: CC - Organic Chemistry Impact factor: 5.731, year: 2014

  4. Beyond integrated safeguards: Performance-based assessments for future nuclear controls

    International Nuclear Information System (INIS)

    Pilat, Joseph F.; Budlong Sylvester, Kory W.

    2001-01-01

    Full text: In the future, if the nuclear nonproliferation and arms control agendas are to advance, they will likely become increasingly seen as parallel undertakings with the objective of comprehensive cradle-to-grave controls over nuclear materials and possibly even warheads removed from defense programs along with materials in civilian use. This 'back to the future' prospect was envisioned in the Acheson-Lillienthal Report and the Baruch Plan, and more modestly in the Atoms-for-Peace Proposal. Unlike the grand plans of the early nuclear years, today's and tomorrow's undertakings will more likely consist of a series of incremental steps with the goal of expanding nuclear controls. These steps will be undertaken at a time of fundamental change in the IAEA safeguards system, and they will be influenced by those changes in profound ways. This prospective influence needs to be taken into account as the IAEA develops and implements integrated safeguards, including its efforts to establish new safeguards criteria, undertake technological and administrative improvements in safeguards, implement credible capabilities for the detection of undeclared nuclear facilities and activities and, perhaps, provide for a more intensive involvement in applying safeguards in new roles such as the verification of a Fissile Material Cutoff Treaty. Performance-based criteria offer one promising way to address the effectiveness of integrated safeguards and to provide a common means of assessing the other key areas of a comprehensive approach to nuclear controls as these develop independently and to the extent that they are coordinated in the future. (author)

  5. Integrated software system for seismic evaluation of nuclear power plant structures

    International Nuclear Information System (INIS)

    Xu, J.; Graves, H.L.

    1993-01-01

    The computer software CARES (Computer Analysis for Rapid Evaluation of Structures) was developed by the Brookhaven National Laboratory for the U.S. Nuclear Regulatory Commission. It represents an effort to utilize established numerical methodologies commonly employed by industry for structural safety evaluations of nuclear power plant facilities and incorporates them into an integrated computer software package operated on personal computers. CARES was developed with the objective of including all aspects of seismic performance evaluation of nuclear power structures. It can be used to evaluate the validity and accuracy of analysis methodologies used for structural safety evaluations of nuclear power plants by various utilities. CARES has a modular format, each module performing a specific type of analysis. The seismic module integrates all the steps of a complete seismic analysis into a single package with many user-friendly features such as interactiveness and quick turnaround. Linear structural theory and pseudo-linear convolution theory are utilized as the bases for the development with a special emphasis on the nuclear regulatory requirements for structural safety of nuclear plants. The organization of the seismic module is arranged in eight options, each performing a specific step of the analysis with most of input/output interfacing processed by the general manager. Finally, CARES provides comprehensive post-processing capability for displaying results graphically or in tabular form so that direct comparisons can be easily made. (author)

  6. Global nuclear material monitoring with NDA and C/S data through integrated facility monitoring

    International Nuclear Information System (INIS)

    Howell, J.A.; Menlove, H.O.; Argo, P.; Goulding, C.; Klosterbuer, S.; Halbig, J.

    1996-01-01

    This paper focuses on a flexible, integrated demonstration of a monitoring approach for nuclear material monitoring. This includes aspects of item signature identification, perimeter portal monitoring, advanced data analysis, and communication as a part of an unattended continuous monitoring system in an operating nuclear facility. Advanced analysis is applied to the integrated nondestructive assay and containment and surveillance data that are synchronized in time. End result will be the foundation for a cost-effective monitoring system that could provide the necessary transparency even in areas that are denied to foreign nationals of both US and Russia should these processes and materials come under full-scope safeguards or bilateral agreements. Monitoring systems of this kind have the potential to provide additional benefits including improved nuclear facility security and safeguards and lower personnel radiation exposures. Demonstration facilities in this paper include VTRAP-prototype, Los Alamos Critical Assemblies Facility, Kazakhstan BM-350 Reactor monitor, DUPIC radiation monitoring, and JOYO and MONJU radiation monitoring

  7. Integration of new nuclear power plants into transmission grids part I: Transmission system issues

    International Nuclear Information System (INIS)

    Abi-Samra, N.

    2008-01-01

    Integration of new nuclear plants into a transmission system is a two sided problem. On one side, adding the nuclear plant into an existing grid will change the attributes of that grid: e.g., loading of certain transmission lines will increase; voltages will be affected, etc. On the other side, the grid itself will affect the plant, and the plant needs to be designed to accommodate the specifics of the grid. Based on that, this paper is divided into two parts. Part I addresses the grid issues with the integration of the new plant, with emphasis on the electrical aspects of these issues. Part II of this paper, concentrates on the vulnerability of the plant from grid disturbances. Part II reintroduces a relatively new concept by this author called the Zone of Vulnerability (ZoV) for the new nuclear plants. (authors)

  8. Integrated Plant Safety Assessment, Systematic Evaluation Program: Yankee Nuclear Power Station (Docket No. 50-29)

    International Nuclear Information System (INIS)

    1987-10-01

    The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0825), under the scope of the Systematic Evaluation Program (SEP), for Yankee Atomic Electric Company's Yankee Nuclear Power Station located in Rowe, Massachusetts. The SEP was initiated by the NRC to review the design of older operating nuclear power plants to reconfirm and document their safety. This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Yankee plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when Yankee was licensed, (2) a basis for deciding how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. 2 tabs

  9. Introduction of Integrity Evaluation Criteria Developing during and after fire for Nuclear Power Plant Buildings

    International Nuclear Information System (INIS)

    Lee, Jin Woo

    2016-01-01

    The first project for nuclear power plant built in Korea to taking account the engineering based approach was started on October 2015 including the whole process such as fire hazard analysis, standard fire modeling, cable tray fire with multi spurious operation, structural fire integrity evaluation, and large area fire induced air craft crash. This paper covers the brief developing scheme and roadmap focusing on structural fire evaluation criteria. The meaningful first step for developing the structural fire integrity in nuclear power plant building is started with the series of fire related sub sections mentioned in earlier section. The recognition and sufficient effort of fire research leads to set up the safe and reliable design of nuclear power plant

  10. Introduction of Integrity Evaluation Criteria Developing during and after fire for Nuclear Power Plant Buildings

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jin Woo [KEPCo, Gimcheon (Korea, Republic of)

    2016-05-15

    The first project for nuclear power plant built in Korea to taking account the engineering based approach was started on October 2015 including the whole process such as fire hazard analysis, standard fire modeling, cable tray fire with multi spurious operation, structural fire integrity evaluation, and large area fire induced air craft crash. This paper covers the brief developing scheme and roadmap focusing on structural fire evaluation criteria. The meaningful first step for developing the structural fire integrity in nuclear power plant building is started with the series of fire related sub sections mentioned in earlier section. The recognition and sufficient effort of fire research leads to set up the safe and reliable design of nuclear power plant.

  11. Integrated energy and climate program without nuclear power

    International Nuclear Information System (INIS)

    Haller, W.

    2007-01-01

    Under the German EU Council presidency, the European Union adopted an ambitious climate protection program in spring this year which has consequences for the entire energy sector. A fair system of burden sharing is currently being sought on the level of the European Union. However, the German federal government does not wait for that agreement to be reached, but has added to the clearcut EU plans in order to achieve more climate protection. At the closed meeting of the federal cabinet in Meseberg on August 23-24, 2007, the key points of an integrated energy and climate program were adopted. The unprecedented set of measures comprises 30 points. In many cases, legal measures are required for implementation, which implies a heavy workload facing the federal government and parliament. A major step forward is seen in the federal government's intention to preserve the international competitiveness of the producing sector and energy-intensive industries also under changed framework conditions. The imperative guiding principle must be that care should take precedence over speed. European or worldwide solutions must be found for all measures, be it energy efficiency or climate protection, and all countries must be involved because, otherwise, specific measures taken by individual states will be ineffective. (orig.)

  12. Quality assurance systems - a means for an integrating organization of nuclear power plants

    International Nuclear Information System (INIS)

    Adams, H.W.

    1984-01-01

    The operators of nuclear power plants are in the process of introducing quality assurance systems of the type required in Rule 1401 by the German Kerntechnischer Ausschuss (Nuclear Technology Committee). These systems as a cross sectional function cover most of the organizational areas of a nuclear power plant. Their introduction offers an opportunity to harmonize and supplement existing systems where necessary. Integrated quality assurance systems built up on a data base allow existing DP data and other logical data to be organized in such a way that certain sequences of events can be managed by enforced control. This relieves the personnel responsible for the safety of a nuclear power plant of routine jobs and routine decisions. Greater flexibility is created for personal decisions. Organized sequences of events can be monitored by having lists printed out in which the necessary data are combined into data sets. (orig.) [de

  13. Nuclear safety and security culture - an integrated approach to regulatory oversight

    International Nuclear Information System (INIS)

    Tronea, M.; Ciurea Ercau, C.

    2013-01-01

    The paper presents the development and implementation of regulatory guidelines for the oversight of safety and security culture within licensees organizations. CNCAN (the National Commission for Nuclear Activities of Romania) has used the International Atomic Energy Agency (IAEA) attributes for a strong safety culture as the basis for its regulatory guidelines providing support to the reviewers and inspectors for recognizing and gathering information relevant to safety culture. These guidelines are in process of being extended to address also security culture, based on the IAEA Nuclear Security Series No. 7 document Nuclear Security Culture: Implementing Guide. Recognizing that safety and security cultures coexist and need to reinforce each other because they share the common objective of limiting risk and that similar regulatory review and inspection processes are in place for nuclear security oversight, an integrated approach is considered justified, moreover since the common elements of these cultures outweigh the differences. (authors)

  14. An advanced NSSS integrity monitoring system for Shin-Kori nuclear units 3 and 4

    International Nuclear Information System (INIS)

    Oh, Y. G.; Kim, H. B.; Galin, S. R.; Kim, S. H.; Lee, S. J.

    2009-01-01

    The advanced design features of NSSS (Nuclear Steam Supply System) Integrity Monitoring System for Shin-Kori Nuclear Units 3 and 4 are summarized herein. During the overall system design and detailed component design processes, many design improvements have been made for the system. The major design changes are: 1) the application of a common software platform for all subsystems, 2) the implementation of remote access, control and monitoring capabilities, and 3) the equipment redesign and rearrangement that has simplified the system architecture. Changes give an effect on cabinet size, number of cables, cyber-security, graphic user interfaces, and interfaces with other monitoring systems. The system installation and operation for Shin-Kori Nuclear Units 3 and 4 will be more convenient than those for previous Korean nuclear units in view of its remote control capability, automated test functions, improved user interface functions, and much less cabling. (authors)

  15. An Advanced NSSS Integrity Monitoring System for Shin-Kori Nuclear Units 3 and 4

    Science.gov (United States)

    Oh, Yang Gyun; Galin, Scott R.; Lee, Sang Jeong

    2010-12-01

    The advanced design features of NSSS (Nuclear Steam Supply System) Integrity Monitoring System for Shin-Kori Nuclear Units 3 and 4 are summarized herein. During the overall system design and detailed component design processes, many design improvements have been made for the system. The major design changes are: 1) the application of a common software platform for all subsystems, 2) the implementation of remote access, control and monitoring capabilities, and 3) the equipment redesign and rearrangement that has simplified the system architecture. Changes give an effect on cabinet size, number of cables, cyber-security, graphic user interfaces, and interfaces with other monitoring systems. The system installation and operation for Shin-Kori Nuclear Units 3 and 4 will be more convenient than those for previous Korean nuclear units in view of its remote control capability, automated test functions, improved user interface functions, and much less cabling.

  16. Physical Attractiveness and Courtship

    Science.gov (United States)

    Silverman, Irwin

    1971-01-01

    This study shows a high and disquieting degree of similarity in physical attractiveness between dating partners, and suggests also that more similar partners tend to form stronger romantic attachments. (Author)

  17. Solar ultraviolet-B radiation affects seedling emergence, DNA integrity, plant morphology, growth rate, and attractiveness to herbivore insects in Datura ferox

    International Nuclear Information System (INIS)

    Ballare, C.L.; Scopel, A.L.; Stapleton, A.E.

    1996-01-01

    To study functional relationships between the effects of solar ultraviolet-B radiation (UV0B) on different aspects of the physiology of a wild plant, we carried out exclusion experiments in the field with the summer annual Datura ferrox L. Solar UV-B incident over Buenos Aires reduced daytime seedling emergence, inhibited stem elongation and leaf expansion, and tended to reduce biomass accumulation during early growth. However, UV-B had no effect on calculated net assimilation rate. Using a monoclonal antibody specific to the cyclobutane-pyrimidine dimer (CPD), we found that plants receiving full sunlight had more CPDs per unit of DNA than plants shielded from solar UV-B, but the positive correlation between UV-B and CPD burden tended to level off at high (near solar) UV-B levels. At our field site, Datura plants were consumed by leaf beetles (Coleoptera), and the proportion of plants attacked by insects declined with the amount of UV-B received during growth. Field experiments showed that plant exposure to solar UV-B reduced the likelihood of leaf beetle attack by one-half. Our results highlight the complexities associated with scaling plant responses to solar UV-B, because they show: (a) a lack of correspondence between UV-B effects on net assimilation rate and whole-plant growth rate, (b) nonlinear UV-B dose-response curves, and (c) UV-B effects of plant attractiveness to natural herbivores. 56 refs., 7 figs

  18. Cladding Effects on Structural Integrity of Nuclear Components

    International Nuclear Information System (INIS)

    Sattari-Far, Iradi; Andersson, Magnus

    2006-06-01

    different clad components. Measurement of cladding residual stresses in a decommissioned reactor pressure vessel head, which was exposed to service conditions (pressure test, temperature, neutron irradiation, etc.), and the results from the cladding in a cut-out-piece, which did not experience any service or test pressure, basically showed similar profiles. Considering the low scatter and the reproducible data, the hole-drilling technique is recommended in measurement of the peak of the cladding residual stresses. The profile and magnitude of the cladding residual stresses depend mainly upon cladding composition, cladding thickness, clad component geometry and clad component temperature. The peak of the cladding residual stresses is actually about 2-3 mm under the surface of the clad layer, and values in the range of 150 and 500 MPa are reported. Fracture assessments on different clad components at different loading conditions reveal that fracture assessments based on LEFM and ASME Kk curve lead to unrealistic conservative results, and the cladding residual stresses are of importance for surface crack behaviour, especially under cold loads. The NESC projects have shown that the Master Curve methodology can give good predictions of the conducted experiments. It is reasonable to assume a peak value of cladding residual stresses in the whole clad layer to be equal to the yield strength of the cladding material (around 300 MPa) at room temperature. Providing that the clad component has received PWHT, it can be assumed no residual stresses in the underlying base material. For the nuclear pressure vessel, it is also reasonable to assume that the cladding stress free temperature is at the operation temperature of the vessel (around 300 deg C). It has been shown that the cladding residual stresses have negligible influence on subclad crack behaviour in clad components (receiving PWHT). It has also been shown that the crack growth for subclad cracks would be towards the base

  19. Cladding Effects on Structural Integrity of Nuclear Components

    Energy Technology Data Exchange (ETDEWEB)

    Sattari-Far, Iradi; Andersson, Magnus [lnspecta Technology AB, Stockholm (Sweden)

    2006-06-15

    measurement of different clad components. Measurement of cladding residual stresses in a decommissioned reactor pressure vessel head, which was exposed to service conditions (pressure test, temperature, neutron irradiation, etc.), and the results from the cladding in a cut-out-piece, which did not experience any service or test pressure, basically showed similar profiles. Considering the low scatter and the reproducible data, the hole-drilling technique is recommended in measurement of the peak of the cladding residual stresses. The profile and magnitude of the cladding residual stresses depend mainly upon cladding composition, cladding thickness, clad component geometry and clad component temperature. The peak of the cladding residual stresses is actually about 2-3 mm under the surface of the clad layer, and values in the range of 150 and 500 MPa are reported. Fracture assessments on different clad components at different loading conditions reveal that fracture assessments based on LEFM and ASME Kk curve lead to unrealistic conservative results, and the cladding residual stresses are of importance for surface crack behaviour, especially under cold loads. The NESC projects have shown that the Master Curve methodology can give good predictions of the conducted experiments. It is reasonable to assume a peak value of cladding residual stresses in the whole clad layer to be equal to the yield strength of the cladding material (around 300 MPa) at room temperature. Providing that the clad component has received PWHT, it can be assumed no residual stresses in the underlying base material. For the nuclear pressure vessel, it is also reasonable to assume that the cladding stress free temperature is at the operation temperature of the vessel (around 300 deg C). It has been shown that the cladding residual stresses have negligible influence on subclad crack behaviour in clad components (receiving PWHT). It has also been shown that the crack growth for subclad cracks would be towards the

  20. Study on integrated approach of Nuclear Accident Hazard Predicting, Warning, and Optimized Controlling System based on GIS

    International Nuclear Information System (INIS)

    Tang Lijuan; Huang Shunxiang; Wang Xinming

    2012-01-01

    The issue of nuclear safety becomes the attention focus of international society after the nuclear accident happened in Fukushima. Aiming at the requirements of the prevention and controlling of Nuclear Accident establishment of Nuclear Accident Hazard Predicting, Warning and optimized Controlling System (NAPWS) is a imperative project that our country and army are desiderating, which includes multiple fields of subject as nuclear physics, atmospheric science, security science, computer science and geographical information technology, etc. Multiplatform, multi-system and multi-mode are integrated effectively based on GIS, accordingly the Predicting, Warning, and Optimized Controlling technology System of Nuclear Accident Hazard is established. (authors)

  1. Hysteria makes locations less attractive. Or: Germany, a Republic of scaremongerers? Keynote lecture given at the annual conference on nuclear technology

    International Nuclear Information System (INIS)

    Kraemer, W.

    2005-01-01

    'Panic, Fear and Risk' has become an almost permanent part of the agenda of nuclear technology. This contribution deals with the subject from the perspective of an economic statistician. The question put, analyzed and discussed is about the way in which our society copes with hazards, lives with risks, and handles uncertainties and probabilities. In a nutshell, hazards are coped with in a very inefficient way, risks are evaluated very selectively, and uncertainties and probabilities are handled most imprudently. Incidentally, this irrational attitude towards, and way of coping with, hazards and risks is not an individual, personal problem; it also causes considerable damage to business, industry, and to the national economy as a whole. Rational decisions are obstructed, even prevented, by this type of behavior. A number of blatant, topical examples are given to explain this irrational attitude, which causes actual risks to be regarded as less severe than hypothetical, more spectacular ones, also against the backdrop of this aspect of statistics. The facts determining risk perception and risk acceptance are explained and illustrated. In addition, the role of the media is analyzed critically, in particular the amplification or even marked exaggeration of risks by the media. (orig.)

  2. An integrated approach to energy supply and demand: The role of nuclear energy in Southern Africa

    International Nuclear Information System (INIS)

    Neethling, D.C.; Bredell, J.H.; Basson, J.A.

    1990-01-01

    The importance of an integrated approach to the development of an electricity strategy for Southern Africa is emphasized in view of the numerous options and initiatives that are available for supply and demand side management. Apart from present uncertainties concerning future electricity demand, other factors such as the availability of coal and uranium and the comparative costs of nuclear and coal-based electricity are regarded as the most important parameters which have as yet not been sufficiently quantified to decide on the timing and extent of nuclear energy in Southern Africa. (author)

  3. An integrated approach to energy supply and demand: The role of nuclear energy in Southern Africa

    Energy Technology Data Exchange (ETDEWEB)

    Neethling, D C; Bredell, J H; Basson, J A [National Energy Council, Lynnwood Ridge (South Africa)

    1990-06-01

    The importance of an integrated approach to the development of an electricity strategy for Southern Africa is emphasized in view of the numerous options and initiatives that are available for supply and demand side management. Apart from present uncertainties concerning future electricity demand, other factors such as the availability of coal and uranium and the comparative costs of nuclear and coal-based electricity are regarded as the most important parameters which have as yet not been sufficiently quantified to decide on the timing and extent of nuclear energy in Southern Africa. (author)

  4. SDL-Based Protocol Validation for the Integrated Safety Communication Network in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Jung-hun; Kim, Dong-hoon; Lee, Dong-young; Park, Sung-woo

    2006-01-01

    The communication protocol in nuclear power plants needs to be validated systematically to avoid the critical situation that may be caused by its own faults. We establish the methodology to validate the protocol designed for the Integrated Safety Communication Networks (ISCN) of Korea Nuclear Instrumentation and Control System (KNICS). The ISCN protocol is specified using the formal description technique called the SDL. The validation of ISCN protocol is done via the Simulator and Validator, both of which are main functions provided by the SDL

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

    International Nuclear Information System (INIS)

    Handrlica, Jakub

    2009-01-01

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

  6. A comprehensive economic evaluation of integrated desalination systems using fossil fuelled and nuclear energies and including their environmental costs

    International Nuclear Information System (INIS)

    Nisan, S.; Benzarti, N.

    2008-01-01

    Seawater desalination is now widely accepted as an attractive alternative source of freshwater for domestic and industrial uses. Despite the considerable progress made in the relevant technologies desalination, however, remains an energy intensive process in which the energy cost is the paramount factor. This Study is a first of a kind in that we have integrated the environmental costs into the power and desalination costs. The study has focused on the seawater desalination cost evaluation of the following systems. It is supposed that they will be operating in the co-generation mode (Simultaneous production of electrical power and desalted water) in 2015: Fossil fuelled based systems such as the coal and oil fired plants and the gas turbine combined cycle plant, coupled to MED, and RO; Pressurised water reactors such as the PWR-900 and the AP-600, coupled to MED, and RO; High temperature reactors such as the GT-MHR, the PBMR, coupled to MED, with the utilisation of virtually free waste-heat provided by these reactors. The study is made in real site-specific conditions of a site In Southern Europe. Sensitivity studies for different parameters such as the fossil fuel prices, interest and discount rates, power costs etc., have also been undertaken. The results obtained are then used to evaluate the financial interest of selected integrated desalination systems in terms of a detailed cash flow analysis, providing the net present values, pay back periods and the internal rate of returns. Analysis of the results shows that among the fossil fuelled systems the power and desalination costs by circulating fluidized bed coal fired plant would be the lowest with current coal prices. Those by oil fired plants would be highest. In all cases, integrated nuclear energy systems would lead to considerably lower power and water costs than the corresponding coal based systems. When external costs for different energies are internalized in power and water costs, the relative cost

  7. AFM visualization of sub-50nm polyplex disposition to the nuclear pore complex without compromising the integrity of the nuclear envelope

    DEFF Research Database (Denmark)

    Andersen, Helene; Parhamifar, Ladan; Hunter, A Christy

    2016-01-01

    that were microinjected into the oocytes of Xenopus laevis, as an example of a non-dividing cell, is exclusive to the nuclear pore complex (NPC). AFM images show NPCs clogged only with sub-50nm polyplexes. This mode of disposition neither altered the morphology/integrity of the nuclear membrane nor the NPC...

  8. Building an integrated nuclear engineering and nuclear science human resources pipeline at the Idaho National Engineering and Environmental Laboratory

    International Nuclear Information System (INIS)

    Sneed, A.; Sikorski, B.; Lineberry, M.; Jolly, J.

    2004-01-01

    In a joint effort with the Argonne National Laboratory - West (ANL-W), the Idaho National Engineering and Environmental Laboratory (INEEL) has assumed the lead role for nuclear energy reactor research for the United States Government. In 2005, these two laboratories will be combined into one entity, the Idaho National Laboratory (INL). There are two objectives for the INL: (1) to act as the lead systems integrator for the Department of Energy's Office of Nuclear Energy Science and Technology and, (2) to establish a Center for Advanced Energy Studies. Focusing on the Center for Advanced Energy Studies, this paper presents a Human Resources Pipeline Model outlining a nuclear educational pathway that leads to university and industry research partnerships. The pathway progresses from education to employment and into retirement. Key to the model is research and mentoring and their impact upon each stage. The Center's success will be the result of effective and advanced communications, faculty/student involvement, industry support, inclusive broadbased involvement, effective long-term partnering, and increased federal and state support. (author)

  9. Dynamic Complexity Study of Nuclear Reactor and Process Heat Application Integration

    International Nuclear Information System (INIS)

    Taylor, J'Tia Patrice; Shropshire, David E.

    2009-01-01

    This paper describes the key obstacles and challenges facing the integration of nuclear reactors with process heat applications as they relate to dynamic issues. The paper also presents capabilities of current modeling and analysis tools available to investigate these issues. A pragmatic approach to an analysis is developed with the ultimate objective of improving the viability of nuclear energy as a heat source for process industries. The extension of nuclear energy to process heat industries would improve energy security and aid in reduction of carbon emissions by reducing demands for foreign derived fossil fuels. The paper begins with an overview of nuclear reactors and process application for potential use in an integrated system. Reactors are evaluated against specific characteristics that determine their compatibility with process applications such as heat outlet temperature. The reactor system categories include light water, heavy water, small to medium, near term high-temperature, and far term high temperature reactors. Low temperature process systems include desalination, district heating, and tar sands and shale oil recovery. High temperature processes that support hydrogen production include steam reforming, steam cracking, hydrogen production by electrolysis, and far-term applications such as the sulfur iodine chemical process and high-temperature electrolysis. A simple static matching between complementary systems is performed; however, to gain a true appreciation for system integration complexity, time dependent dynamic analysis is required. The paper identifies critical issues arising from dynamic complexity associated with integration of systems. Operational issues include scheduling conflicts and resource allocation for heat and electricity. Additionally, economic and safety considerations that could impact the successful integration of these systems are considered. Economic issues include the cost differential arising due to an integrated system

  10. Dynamic Complexity Study of Nuclear Reactor and Process Heat Application Integration

    Energy Technology Data Exchange (ETDEWEB)

    J' Tia Patrice Taylor; David E. Shropshire

    2009-09-01

    Abstract This paper describes the key obstacles and challenges facing the integration of nuclear reactors with process heat applications as they relate to dynamic issues. The paper also presents capabilities of current modeling and analysis tools available to investigate these issues. A pragmatic approach to an analysis is developed with the ultimate objective of improving the viability of nuclear energy as a heat source for process industries. The extension of nuclear energy to process heat industries would improve energy security and aid in reduction of carbon emissions by reducing demands for foreign derived fossil fuels. The paper begins with an overview of nuclear reactors and process application for potential use in an integrated system. Reactors are evaluated against specific characteristics that determine their compatibility with process applications such as heat outlet temperature. The reactor system categories include light water, heavy water, small to medium, near term high-temperature, and far term high temperature reactors. Low temperature process systems include desalination, district heating, and tar sands and shale oil recovery. High temperature processes that support hydrogen production include steam reforming, steam cracking, hydrogen production by electrolysis, and far-term applications such as the sulfur iodine chemical process and high-temperature electrolysis. A simple static matching between complementary systems is performed; however, to gain a true appreciation for system integration complexity, time dependent dynamic analysis is required. The paper identifies critical issues arising from dynamic complexity associated with integration of systems. Operational issues include scheduling conflicts and resource allocation for heat and electricity. Additionally, economic and safety considerations that could impact the successful integration of these systems are considered. Economic issues include the cost differential arising due to an integrated

  11. Attracting International Hotels

    DEFF Research Database (Denmark)

    Assaf, A. George; Josiassen, Alexander; Agbola, Frank Wogbe

    2015-01-01

    With the increased international competition facing hotel chains, it is essential that the next destination they enter is the most attractive option possible. The host destinations too have a keen interest in strategically positioning themselves in order to attract international hotels since...... their presence has several positive effects. Using, for the first time, actual on-location data we investigate the factors that matter most for international hotels when selecting host destinations. Specifically, we identify 23 factors that make a destination an attractive (or unattractive) location...... for international hotels. We then rank these. The results show that welcomeness, infrastructure, and crime rate are the three most important factors that influence the location of international hotels in host destinations....

  12. Attracting girls to physics

    Science.gov (United States)

    Borg, Anne; Sui, Manling

    2013-03-01

    Large regional differences remain in the number of girls studying physics and the number of female physicists in academic positions. While many countries struggle with attracting female students to university studies in physics, climbing the academic ladder is the main challenge for these women. Furthermore, for many female physicists the working climate is not very supportive. The workshop Attracting Girls to Physics, organized as part of the 4th IUPAP International Conference on Women in Physics, South Africa 2011, addressed attitudes among education-seeking teenagers and approaches for attracting young girls to physics through successful recruitment plans, including highlighting the broad spectrum of career opportunities for those with physics qualifications. The current paper presents findings, examples of best practices, and recommendations resulting from this workshop.

  13. Evaluation of integrity of radiation sources of nuclear gauges; Avaliacao da integridade de fontes radioativas de medidores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Torohate, Wiclif Francisco

    2016-11-01

    Nuclear equipment meters are mainly used in the industry in quality control and process control. The principle of operation consists in a shielded radioactive source together with a radiation detector such that the radiation interacts with the material to be analyzed before reaching the detector, providing real time data. Can be as their fixed and mobile mobility, the unique properties of ionizing radiation are used in three basic modes, transmission, backscatter or dispersion or induced (reactive). With the advancement and technological modernization in the world, the demand for nuclear gauges becomes increasingly larger. Currently in Brazil there are about 465 process control plants and 21 portable systems and Mozambique about 45 facilities using nuclear gauges. This font registration is done through a process called source inventory that allows also to know the category of the source, the danger or risk to human health that the source offers. The handling of this equipment requires personnel, certified, skilled and well trained in radiation protection area in accordance with the requirements of the various CNEN Rules. Due to the presence of radioactive source and because these devices are used by workers risk because there external radiation. In this context, we made the smear test in two fixed meters from the IRD industry laboratory, which determines the integrity of the source package, mandatory item in periodic integrity testing of the radiation source of this type of device. A set of procedures is made for its implementation as an evaluation of the radiological risk by radiological survey. It was intended to contribute to the learning handling and safe use of these meters. (author)

  14. Clusters in attractive colloids

    Energy Technology Data Exchange (ETDEWEB)

    Coniglio, A [Dipartimento di Scienze Fisiche, Universita di Napoli ' Federico II' , Complesso Universitario di Monte Sant' Angelo, via Cintia 80126 Naples (Italy); Arcangelis, L de [Dipartimento di Ingegneria dell' Informazione and CNISM II Universita di Napoli, Aversa (CE) (Italy); Candia, A de [Dipartimento di Scienze Fisiche, Universita di Napoli ' Federico II' , Complesso Universitario di Monte Sant' Angelo, via Cintia 80126 Naples (Italy); Gado, E Del [Dipartimento di Scienze Fisiche, Universita di Napoli ' Federico II' , Complesso Universitario di Monte Sant' Angelo, via Cintia 80126 Naples (Italy); Fierro, A [Dipartimento di Scienze Fisiche, Universita di Napoli ' Federico II' , Complesso Universitario di Monte Sant' Angelo, via Cintia 80126 Naples (Italy); Sator, N [Laboratoire de Physique Theorique de la Matiere Condensee, Universite Pierre et Marie Curie-Paris6, UMR (CNRS) 7600 Case 121, 4 Place Jussieu 75252 Paris Cedex 05 (France)

    2006-09-13

    We discuss how the anomalous increase of the viscosity in colloidal systems with short-range attraction can be related to the formation of long-living clusters. Based on molecular dynamics and Monte Carlo numerical simulations of different models, we propose a similar picture for colloidal gelation at low and intermediate volume fractions. On this basis, we analyze the distinct role played by the formation of long-living bonds and the crowding of the particles in the slow dynamics of attractive colloidal systems.

  15. Development of multi-channel gated integrator and PXI-DAQ system for nuclear detector arrays

    International Nuclear Information System (INIS)

    Kong Jie; Su Hong; Chen Zhiqiang; Dong Chengfu; Qian Yi; Gao Shanshan; Zhou Chaoyang; Lu Wan; Ye Ruiping; Ma Junbing

    2010-01-01

    A multi-channel gated integrator and PXI based data acquisition system have been developed for nuclear detector arrays with hundreds of detector units. The multi-channel gated integrator can be controlled by a programmable GI controller. The PXI-DAQ system consists of NI PXI-1033 chassis with several PXI-DAQ cards. The system software has a user-friendly GUI which is written in C language using LabWindows/CVI under Windows XP operating system. The performance of the PXI-DAQ system is very reliable and capable of handling event rate up to 40 kHz.

  16. Current nuclear industry practices with regard to the integration of surveillances

    International Nuclear Information System (INIS)

    Stewart, M.; Smith, C.

    1992-04-01

    Commercial nuclear industry practices regarding the integration of technical specification (TS) surveillance and maintenance activities are identified in this report. A questionnaire was developed and used to obtain current industry practices from NRC Regional personnel and INEL engineers with utility experience. Some of these practices indicate that the scheduling of TS surveillance and maintenance items could be more effectively coordinated. Also, must utilities do not formally consider risk implications when they are scheduling maintenance. Methodologies and approaches for proposing and evaluating changes to improve the integration of TS surveillance and maintenance activities have been identified for planned future work

  17. An integral reactor design concept for a nuclear co-generation plant

    International Nuclear Information System (INIS)

    Lee, D.J.; Kim, J.I.; Kim, K.K.; Chang, M.H.; Moon, K.S.

    1997-01-01

    An integral reactor concept for nuclear cogeneration plant is being developed at KAERI as an attempt to expand the peaceful utilization of well established commercial nuclear technology, and related industrial infrastructure such as desalination technology in Korea. Advanced technologies such as intrinsic and passive safety features are implemented in establishing the design concepts to enhance the safety and performance. Research and development including laboratory-scale tests are concurrently underway to evaluate the characteristics of various passive safety concepts and provide the proper technical data for the conceptual design. This paper describes the preliminary safety and design concepts of the advanced integral reactor. Salient features of the design are hexagonal core geometry, once-through helical steam generator, self-pressurizer, and seismic resistant fine control CEDMS, passive residual heat removal system, steam injector driven passive containment cooling system. (author)

  18. INTEGRAL BENCHMARK DATA FOR NUCLEAR DATA TESTING THROUGH THE ICSBEP AND THE NEWLY ORGANIZED IRPHEP

    Energy Technology Data Exchange (ETDEWEB)

    J. Blair Briggs; Lori Scott; Yolanda Rugama; Enrico Satori

    2007-04-01

    The status of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) was last reported in a nuclear data conference at the International Conference on Nuclear Data for Science and Technology, ND-2004, in Santa Fe, New Mexico. Since that time the number and type of integral benchmarks have increased significantly. Included in the ICSBEP Handbook are criticality-alarm / shielding and fundamental physic benchmarks in addition to the traditional critical / subcritical benchmark data. Since ND 2004, a reactor physics counterpart to the ICSBEP, the International Reactor Physics Experiment Evaluation Project (IRPhEP) was initiated. The IRPhEP is patterned after the ICSBEP, but focuses on other integral measurements, such as buckling, spectral characteristics, reactivity effects, reactivity coefficients, kinetics measurements, reaction-rate and power distributions, nuclide compositions, and other miscellaneous-type measurements in addition to the critical configuration. The status of these two projects is discussed and selected benchmarks highlighted in this paper.

  19. Development of probabilistic evaluation methodology for structural integrity of nuclear components

    International Nuclear Information System (INIS)

    Lee, Gang Yong; Yang, Jee Hyeok; Shin, Jeong Woo; Hong, Soon Won; Lee, Won Gyu; Kim, Goo Yeong

    1999-03-01

    Since integrity is very important in Nuclear Power Plants, there have been a lot of researches and several rules are provided. But these are mostly based on the concept of the deterministic fracture mechanics and in many cases, those rules are unrealistic or conservative. Therefore, the concept of the probabilistic fracture mechanics considering the realistic failure of the structure and the quantitative failure probability is introduced in many fields. There have been many researches on the probabilistic fracture mechanics in world, but a few in Korea. The final object of our research os to develop the code years. In the first year study, we obtained the concept of the probabilistic fracture mechanics by reviewing the papers about the integrity evaluation of the nuclear pressure vessel on the base of the probabilistic fracture mechanics and selected the important random variables by comparing the effects of random variables on the failure probability using the existing code

  20. Prototype of evaluation guidance system in Integrated Nuclear Data Evaluation System

    International Nuclear Information System (INIS)

    Fukahori, T.; Nakagawa, T.

    1992-01-01

    Integrated Nuclear Data Evaluation System (INDES) is being developed to keep experiences of nuclear data evaluation for JENDL-3 and to support new evaluations. One of the INDES functions is to set up input data of theoretical calculation codes automatically. In order to use INDES effectively, a prototype of nuclear data evaluation guidance system (E.T.; Evaluation Tutor) was made to help users in selecting a set of suitable theoretical calculation codes by applying knowledge engineering technology. E.T. consists of an inference engine, frames, a rule-base, two example-bases and calculating modules of certainty factors. The inference engine and the calculating modules are written in FORTRAN77. (author)

  1. The first stage of BFS integrated system for nuclear materials control and accounting. Final report

    International Nuclear Information System (INIS)

    1996-09-01

    The BFS computerized accounting system is a network-based one. It runs in a client/server mode. The equipment used in the system includes a computer network consisting of: One server computer system, including peripheral hardware and three client computer systems. The server is located near the control room of the BFS-2 facility outside of the 'stone sack' to ensure access during operation of the critical assemblies. Two of the client computer systems are located near the assembly tables of the BFS-1 and BFS-2 facilities while the third one being the Fissile Material Storage. This final report details the following topics: Computerized nuclear material accounting methods; The portal monitoring system; Test and evaluation of item control technology; Test and evaluation of radiation based nuclear material measurement equipment; and The integrated demonstration of nuclear material control and accounting methods

  2. Lessons in Nuclear Safety, Panel on Integration of People and Programs

    International Nuclear Information System (INIS)

    Pinkston, David

    2015-01-01

    Four slides present a historical perspective on the evolution of nuclear safety, a description of systemic misalignment (available resources do not match expectations, demographic cliff developing, promulgation of increased expectations and new requirements proceeds unabated), and needs facing nuclear safety (financial stability, operational stability, and succession planning). The following conclusions are stated under the heading ''Nuclear Safety - 'The System''': the current universe of requirements is too large for the resource pool available; the current universe of requirements has too many different sources of interpretation; there are so many indicators that it's hard to know what is leading (or important); and the net result can come to defy integrated comprehension at the worker level.

  3. Radionuclide observables during the Integrated Field Exercise of the Comprehensive Nuclear-Test-Ban Treaty.

    Science.gov (United States)

    Burnett, Jonathan L; Miley, Harry S; Milbrath, Brian D

    2016-03-01

    In 2014 the Preparatory Commission for the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO) undertook an Integrated Field Exercise (IFE14) in Jordan. The exercise consisted of a simulated 0.5-2 kT underground nuclear explosion triggering an On-site Inspection (OSI) to search for evidence of a Treaty violation. This research paper evaluates two of the OSI techniques used during the IFE14, laboratory-based gamma-spectrometry of soil samples and in-situ gamma-spectrometry, both of which were implemented to search for 17 OSI relevant particulate radionuclides indicative of nuclear explosions. The detection sensitivity is evaluated using real IFE and model data. It indicates that higher sensitivity laboratory measurements are the optimum technique during the IFE and within the Treaty/Protocol-specified OSI timeframes. Copyright © 2016 Elsevier Ltd. All rights reserved.

  4. Integration of artificial intelligence systems for nuclear power plants surveillance and diagnostics

    International Nuclear Information System (INIS)

    Chetry, Moon K.

    2012-01-01

    The objective of this program is to design, construct operate, test, and evaluate a prototype integrated monitoring and diagnostic system for a nuclear power plant. It is anticipated that this technology will have wide application to other complex systems (e.g., fossil power plants, chemical processing plants, and possibly air traffic control systems). Over the past decade, the University of Tennessee (UT) and others have carried out many projects utilizing various methodologies of artificial intelligence (expert systems, neural networks, fuzzy systems and genetic algorithms) to enhance the performance (safety, efficiency, reliability, and availability) of nuclear power plants. Investigations and studies have included a) instrumentation surveillance and calibration validation, b) inferential sensing to calibration of feed water venture flow during fouling, c) thermodynamic performance modeling with iterative improvement of plant heat rate, d) diagnosis of nuclear power plant transients

  5. Integration of a nuclear power plant in electrical systems, alternative programs, optimization

    International Nuclear Information System (INIS)

    Souza, J.A.M. de.

    1991-01-01

    The problem of integration of a nuclear power plants in a electrical power system, to support the power demand of the system, and mainly also support the power demand at the critical period, I.E., peak demands, is analysed. The factors considered in this analysis are: the demand structure of the region, the availability of others power plants in the electrical net and the capacity factor. (author)

  6. Integral measurements on Caliban and Prospero assemblies for nuclear data validation

    International Nuclear Information System (INIS)

    Casoli, P.; Authier, N.; Richard, B.; Ducauze-Philippe, M.; Cartier, J.

    2011-01-01

    How can the quality of nuclear data libraries be checked? Performing reference experiments also called benchmarks allows the testing of evaluated data. During these experiments, integral values such as reaction rates or neutron effective multiplication coefficients are measured. In this paper, the principles of benchmark construction are explained and illustrated with several works performed on the CALIBAN et PROSPERO critical assemblies operated by the Valduc center: benchmarks for dosimetry, activation reactions studies, neutron noise measurements. (authors)

  7. Expansions of Fermi and symmetrized Fermi integrals and applications in nuclear physics

    International Nuclear Information System (INIS)

    Grypeos, M.; Koutroulos, C.; Luk'yanov, V.; Shebeko, A.

    1998-01-01

    A detailed study is undertaken, using various techniques, in deriving expansions of integrals containing the Fermi or the symmetrized Fermi distributions. The results are presented in a mathematically compact form and consist of generalizations and extensions of previously known expansions. The relevance of the results to quantities of interest in nuclear physics is recalled and particular attention is paid to the so-called exponentially small terms which may play an essential role in certain cases

  8. An integrated approach to care attracts people living with HIV who use illicit drugs in an urban centre with a concentrated HIV epidemic

    Directory of Open Access Journals (Sweden)

    S. Fernando

    2016-11-01

    Full Text Available Abstract Background People living with HIV (PLHIV who are also marginalized by social and structural inequities often face barriers to accessing and adhering to HIV treatment and care. The Dr. Peter Centre (DPC is a non-profit integrated care facility with a supervised injection room that serves PLHIV experiencing multiple barriers to social and health services in Vancouver, Canada. This study examines whether the DPC is successful in drawing in PLHIV with complex health issues, including addiction. Methods Using data collected by the Longitudinal Investigations into Supportive and Ancillary health services (LISA study from July 2007 to January 2010, linked with clinical variables available through the British Columbia Centre for Excellence in HIV/AIDS Drug Treatment Program, we identified DPC and non-DPC clients with a history of injection drug use. Bivariable and multivariable logistic regression analyses compared socio-demographic and clinical characteristics of DPC clients (n = 76 and non-DPC clients (n = 482 with a history of injection drug use. Results Of the 917 LISA participants included within this analysis, 100 (10.9% reported being a DPC client, of which 76 reported a history of injection drug use. Adjusted results found that compared to non-DPC clients with a history of injection drug use, DPC-clients were more likely to be male (AOR: 4.18, 95% CI = 2.09–8.37; use supportive services daily vs. less than daily (AOR: 3.16, 95% CI = 1.79–5.61; to have been diagnosed with a mental health disorder (AOR: 2.11; 95% CI: 1.12–3.99; to have a history of interpersonal violence (AOR: 2.76; 95% CI: 1.23–6.19; and to have ever experienced ART interruption longer than 1 year (AOR: 2.39; 95% CI: 1.38–4.15. Conclusions Our analyses suggest that the DPC operating care model engages PLHIV with complex care needs, highlighting that integrated care facilities are needed to support the multiple intersecting vulnerabilities faced

  9. Integration of artificial intelligence systems for nuclear power plant surveillance and diagnostics

    International Nuclear Information System (INIS)

    Uhrig, R.E.; Hines, J.W.; Nelson, W.R.

    1998-01-01

    The objective of this program is to design, construct, operate, test, and evaluate a prototype integrated monitoring and diagnostic system for a nuclear power plant. It is anticipated that this technology will have wide application to other complex systems (e.g., fossil power plants, chemical processing plants, and possibly air traffic control systems). Over the past decade, the University of Tennessee (UT) and others have carried out many projects utilizing various methodologies of artificial intelligence (expert systems, neural networks, fuzzy systems, and genetic algorithms) to enhance the performance (safety, efficiency, reliability, and availability) of nuclear power plants. Investigations and studies have included a) instrumentation surveillance and calibration validation, b) inferential sensing to calibration of feedwater venturi flow during fouling, c) thermodynamic performance modeling with iterative improvement of plant beat rate, d) diagnosis of nuclear power plant transients, and e) increase in thermal power through monitoring of DNBR (Departure from Nucleate Boiling Regime). To increase the likelihood of these individual systems being used in a nuclear power plant, they must be integrated into a single system that operates virtually autonomously, collecting, interpreting, and providing information to the operators in a simple and understandable format. (author)

  10. Technology development on the assessment of structural integrity of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Jeong Moon; Choun, Y. S.; Choi, I. K. and others

    1999-04-01

    Nuclear power plants in Korea show drop off in their performance and safety margin as the age of plants increase. The reevaluation of Kori-1 Unit on its performance and safety for life extension is expected in the near future. However, technologies and information related are insufficient to quantitatively estimate them. The final goal of this study is to develop the basic testing and evaluation techniques related with structural integrity of important nuclear equipment and structures. A part of the study includes development of equipment qualification technique. To ensure the structural integrity of structures, systems, and equipment in nuclear power plants, the following 5 research tasks were performed in the first year. - Analysis of dynamic characteristics of reactor internals - Analysis of engineering characteristics of instrumental earthquakes recorded in Korea - Analysis of ultimate pressure capacity and failure mode of containments building - Development of advanced NDE techniques using ultrasonic resonance scattering - Development of equipment qualification technique against vibration aging. These technologies developed in this study can be used to ensure the structural safety of operational nuclear power plants, and for the long-term life management. (author)

  11. Integration of artificial intelligence systems for nuclear power plant surveillance and diagnostics

    Energy Technology Data Exchange (ETDEWEB)

    Uhrig, R.E.; Hines, J.W.; Nelson, W.R.

    1998-07-01

    The objective of this program is to design, construct, operate, test, and evaluate a prototype integrated monitoring and diagnostic system for a nuclear power plant. It is anticipated that this technology will have wide application to other complex systems (e.g., fossil power plants, chemical processing plants, and possibly air traffic control systems). Over the past decade, the University of Tennessee (UT) and others have carried out many projects utilizing various methodologies of artificial intelligence (expert systems, neural networks, fuzzy systems, and genetic algorithms) to enhance the performance (safety, efficiency, reliability, and availability) of nuclear power plants. Investigations and studies have included a) instrumentation surveillance and calibration validation, b) inferential sensing to calibration of feedwater venturi flow during fouling, c) thermodynamic performance modeling with iterative improvement of plant beat rate, d) diagnosis of nuclear power plant transients, and e) increase in thermal power through monitoring of DNBR (Departure from Nucleate Boiling Regime). To increase the likelihood of these individual systems being used in a nuclear power plant, they must be integrated into a single system that operates virtually autonomously, collecting, interpreting, and providing information to the operators in a simple and understandable format. (author)

  12. Radionuclide observables during the Integrated Field Exercise of the Comprehensive Nuclear-Test-Ban Treaty

    International Nuclear Information System (INIS)

    Burnett, Jonathan L.; Miley, Harry S.; Milbrath, Brian D.

    2016-01-01

    In 2014 the Preparatory Commission for the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO) undertook an Integrated Field Exercise (IFE14) in Jordan. The exercise consisted of a simulated 0.5–2 kT underground nuclear explosion triggering an On-site Inspection (OSI) to search for evidence of a Treaty violation. This research paper evaluates two of the OSI techniques used during the IFE14, laboratory-based gamma-spectrometry of soil samples and in-situ gamma-spectrometry, both of which were implemented to search for 17 OSI relevant particulate radionuclides indicative of nuclear explosions. The detection sensitivity is evaluated using real IFE and model data. It indicates that higher sensitivity laboratory measurements are the optimum technique during the IFE and within the Treaty/Protocol-specified OSI timeframes. - Highlights: • The 2014 Integrated Field Exercise occurred in Jordan. • The detection sensitivity for two On-site Inspection techniques was evaluated. • The techniques search for 17 particulate radionuclides indicative of nuclear explosions. • Laboratory-based gamma-spectrometry of soil samples was the optimum technique.

  13. Path-integral in collective variables and its application to nuclear and hadron physics

    International Nuclear Information System (INIS)

    Pervushin, V.N.; Rajnkhardt, Kh.; Ehbert, D.

    1979-01-01

    The application of functional integrals to describe collective degrees of freedom in different fields of physics is reviewed for the period since 1965. The application of path integrals to the schematic model of nuclear multiparticle systems with pairing and particle-hole forces permits to lay strict foundations under the so called theory of nuclear field, which hitherto was proved euristically. The Abel gauge theory of interacting massless quarks and vector gluons is described. In this model radiative corrections cause spontaneous dynamic breaking of the chiral γ 5 -invariance. The application of functional integration to two-dimensional quantum chromodynamics is also analyzed. It is shown that the local quark-gluon theory can be transformed in an infinite-component nonpolynomial field theory in terms of colourless bound states - mesons. A modified perturbation theory appears in the form of 1/Nsub(c)-expansion (Nsub(c) - number of quarks), that is formally is very akin to the 1/Ω-expansion (Ωdegeneracy of single-particle states) in the theory of nuclear field

  14. Integrity of the Linker of Nucleoskeleton and Cytoskeleton Is Required for Efficient Herpesvirus Nuclear Egress.

    Science.gov (United States)

    Klupp, Barbara G; Hellberg, Teresa; Granzow, Harald; Franzke, Kati; Dominguez Gonzalez, Beatriz; Goodchild, Rose E; Mettenleiter, Thomas C

    2017-10-01

    that dominant negative SUN2 interferes with efficient herpesvirus nuclear egress, apparently by interfering with fusion between the primary virion envelope and outer nuclear membrane. This identifies a new cellular component important for viral egress and implicates LINC complex integrity in nonconventional nuclear membrane trafficking. Copyright © 2017 American Society for Microbiology.

  15. A system of tourism attractions

    OpenAIRE

    Kušen, Eduard

    2010-01-01

    Although tourism attractions are a basic resource for long term tourism developments, they are not given the proper attention, both, theoretical and practical. Therefore, rare studies of tourism attractions, especially those with the ambition of creating a functional system of tourism attractions, attract special attention. The aim of this paper is to present a new system of tourism attractions. This new system is based on the review of published research on tourism attractions, particularly ...

  16. Building of Nuclear Ship Engineering Simulation System development of the simulator for the integral type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Takahashi, Teruo; Shimazaki, Junya; Yabuuchi, Noriaki; Fukuhara, Yosifumi; Kusunoki, Takeshi; Ochiai, Masaaki [Department of Nuclear Energy Systems, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan); Nakazawa, Toshio [Department of HTTR Project, Oarai Research Establishment, Japan Atomic Energy Research Institute, Oarai, Ibaraki (Japan)

    2000-03-01

    JAERI had carried out the design study of a light-weight and compact integral type reactor of power 100 MW{sub th} with passive safety as a power source for the future nuclear ships, and completed an engineering design. To confirm the design and operation performance and to utilize the study of automation of the operations of reactor, we developed a real-time simulator for the integral type reactor. This simulator is a part of Nuclear Ship Engineering Simulation System (NESSY) and on the same hardware as 'Mutsu' simulator which was developed to simulate the first Japanese nuclear ship Mutsu'. Simulation accuracy of 'Mutsu' simulator was verified by comparing the simulation results With data got in the experimental voyage of 'Mutsu'. The simulator for the integral type reactor uses the same programs which were used in 'Mutsu' simulator for the separate type PWR, and the simulated results are approximately consistent with the calculated values using RELAP5/MOD2 (The later points are reported separately). Therefore simulation accuracy of the simulator for the integral type reactor is also expected to be reasonable, though it is necessary to verify by comparing with the real plant data or experimental data in future. We can get the perspectives to use as a real-time engineering simulator and to achieve the above-mentioned aims. This is a report on development of the simulator for the integral type reactor mainly focused on the contents of the analytical programs expressed the structural features of reactor. (author)

  17. Reactivity worth measurements on the CALIBAN reactor: interpretation of integral experiments for the nuclear data validation

    International Nuclear Information System (INIS)

    Richard, B.

    2012-01-01

    The good knowledge of nuclear data, input parameters for the neutron transport calculation codes, is necessary to support the advances of the nuclear industry. The purpose of this work is to bring pertinent information regarding the nuclear data integral validation process. Reactivity worth measurements have been performed on the Caliban reactor, they concern four materials of interest for the nuclear industry: gold, lutetium, plutonium and uranium 238. Experiments which have been conducted in order to improve the characterization of the core are also described and discussed, the latter are necessary to the good interpretation of reactivity worth measurements. The experimental procedures are described with their associated uncertainties, measurements are then compared to numerical results. The methods used in numerical calculations are reported, especially the multigroup cross sections generation for deterministic codes. The modeling of the experiments is presented along with the associated uncertainties. This comparison led to an interpretation concerning the qualification of nuclear data libraries. Discrepancies are reported, discussed and justify the need of such experiments. (author) [fr

  18. Integration of risk aversion in the evaluation of the external cost of a nuclear accident

    International Nuclear Information System (INIS)

    Eeckhoudt, L.; Schieber, C.; Schneider, Th.

    1998-01-01

    Full text of publication follows: the external costs of fuel cycles used in the production of electricity are those imposed on society and environment that are not accounted for by the producers and consumers of energy. Within the evaluation of the external cost of the nuclear fuel cycle, the evaluation of a nuclear accident has to be addressed. For this purpose, the basic approach consists in calculating the expected value of various occident scenarios. the main criticism of this approach is that there is a discrepancy between the social acceptability of the risk and the average monetary value which corresponds in principle to the compensation of the consequences for each individual of the population affected by the accident. The aim of this paper is to propose a methodology for the integration of risk aversion, relying on the expected utility approach, as well as a numerical application based on the French data for the external cost of a nuclear accident. Although a huge range of values has been published for the relative risk aversion coefficient, it seems reasonable to adopt a value of 2 for the specific case of nuclear accident. This leads to an estimated multiplying coefficient approximately equal to 20 to be applied to the expected external cost of a nuclear accident corresponding to a release of about 1% of the core. In this case, the external cost of the nuclear accident is estimated to 0.046 mECU/kWh (i.e. about 50% of the total external costs of the nuclear fuel cycle estimated at 0.1 mECU/kWh with a 3% discount rate), instead of 0.0023 mECU/kWh without taking into account risk aversion. (authors)

  19. 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

  20. Procedure and information displays in advanced nuclear control rooms: experimental evaluation of an integrated design.

    Science.gov (United States)

    Chen, Yue; Gao, Qin; Song, Fei; Li, Zhizhong; Wang, Yufan

    2017-08-01

    In the main control rooms of nuclear power plants, operators frequently have to switch between procedure displays and system information displays. In this study, we proposed an operation-unit-based integrated design, which combines the two displays to facilitate the synthesis of information. We grouped actions that complete a single goal into operation units and showed these operation units on the displays of system states. In addition, we used different levels of visual salience to highlight the current unit and provided a list of execution history records. A laboratory experiment, with 42 students performing a simulated procedure to deal with unexpected high pressuriser level, was conducted to compare this design against an action-based integrated design and the existing separated-displays design. The results indicate that our operation-unit-based integrated design yields the best performance in terms of time and completion rate and helped more participants to detect unexpected system failures. Practitioner Summary: In current nuclear control rooms, operators frequently have to switch between procedure and system information displays. We developed an integrated design that incorporates procedure information into system displays. A laboratory study showed that the proposed design significantly improved participants' performance and increased the probability of detecting unexpected system failures.

  1. Application of integrated logistic techniques to operation, maintenance and re engineering processes in Nuclear Power plants

    International Nuclear Information System (INIS)

    Santiago Diez, P.

    1997-01-01

    This paper addresses the advisability of adapting and applying management and Integrated Logistic engineering techniques to nuclear power plants instead of using more traditional maintenance management methods. It establishes a historical framework showing the origins of integrated approaches based on traditional logistic support concepts, their phases and the real results obtained in the aeronautic world where they originated. It reviews the application of integrated management philosophy, and logistic support and engineering analysis techniques regarding Availability, Reliability and Maintainability (ARM) and shows their inter dependencies in different phases of the system's life (Design, Development and Operation). It describes how these techniques are applied to nuclear power plant operation, their impact on plant availability and the optimisation of maintenance and replacement plans. The paper analyses the need for data (type and volume), which will have to be collected, and the different tools to manage such data. It examines the different CALS tools developed by EA for engineering and for logistic management. It also explains the possibility of using these tools for process and data operations through the INTERNET. It also focuses on the qualities of some simple examples of possible applications, and how they would be used in the framework of Integrated Logistic Support (ILS). (Author)

  2. Correlations between nuclear data and results of integral slab experiments. Case of hafnium

    International Nuclear Information System (INIS)

    Palau, J.M.

    1997-01-01

    The aim of this thesis was to evaluate how much integral slab experiments can both reduce discrepancies between experimental results and calculations, and improve the knowledge of hafnium isotopes neutronic parameters by an adapted sensitivity and uncertainty method. A statistical approach, based on the generalized least squares method and perturbation theory, has been incorporated into our calculation system in order to deduce microscopic cross-section adjustments from observed integral measurements on this particular 'mock-up' reactor. In this study it has been established that the correlations between integral parameters and hafnium capture cross-sections enable specific variations in the region of resolved resonances at the level of multigroup and punctual cross-sections recommended data (JEF-2.2 evaluation) to be highlighted. The use of determinist methods (APOLLO2 code) together with Monte Carlo- type simulations (TRIPOLI4 code) enabled a depth analysis of the modelling approximations to be carried out. Furthermore, the sensitivity coefficient validation technique employed leads to a reliable assessment of the quality of the new basic nuclear data. In this instance, the adjustments proposed for certain isotope 177 Hf resonance parameters reduce, after error propagation, by 3 to 5 per cent the difference between experimental results and calculations related to this absorbent's efficiency. Beyond this particular application, the qualification methodology integrated in our calculation system should enable other basic sizing parameters to be treated (chemical / geometric data or other unexplored nuclear data) to make technological requirements less stringent. (author)

  3. Correlations between nuclear data and integral slab experiments: the case of hafnium

    International Nuclear Information System (INIS)

    Palau, J.M.

    1999-01-01

    The aim of this work was to evaluate how much integral slab experiments can both reduce discrepancies between experimental results and calculations, and improve the knowledge of hafnium isotopes neutronic parameters by an adapted sensitivity and uncertainty method. A statistical approach, based on the generalized least squares method and perturbation theory, has been incorporated into our calculation system in order to deduce microscopic cross-section adjustments from observed integral measurements on this particular 'mock-up' reactor.In this study it has been established that the correlations between integral parameters and hafnium capture cross-sections enable specific variations in the region of resolved resonances at the level of multigroup and punctual cross-sections recommended data (JEF-2.2 evaluation) to be highlighted. The use of determinist methods together with Monte Carlo- type simulations enabled a depth analysis of the modelling approximations to be carried out. Furthermore, the sensitivity coefficient validation technique employed leads to a reliable assessment of the quality of the new basic nuclear data. In this instance, the adjustments proposed for certain isotope 177 Hf resonance parameters reduce, after error propagation, by 3 to 5 per cent the difference between experimental results and calculations related to this absorbent's efficiency. Beyond this particular application, the qualification methodology integrated in our calculation system should enable other basic sizing parameters to be treated (chemical / geometric data or other unexplored nuclear data) to make technological requirements less stringent. (author)

  4. Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations

    Energy Technology Data Exchange (ETDEWEB)

    Clarno, Kevin T [ORNL; Hamilton, Steven P [ORNL; Philip, Bobby [ORNL; Berrill, Mark A [ORNL; Sampath, Rahul S [ORNL; Allu, Srikanth [ORNL; Pugmire, Dave [ORNL; Dilts, Gary [Los Alamos National Laboratory (LANL); Banfield, James E [ORNL

    2012-02-01

    The Advanced Multi-Physics (AMP) Nuclear Fuel Performance code (AMPFuel) is focused on predicting the temperature and strain within a nuclear fuel assembly to evaluate the performance and safety of existing and advanced nuclear fuel bundles within existing and advanced nuclear reactors. AMPFuel was extended to include an integrated nuclear fuel assembly capability for (one-way) coupled radiation transport and nuclear fuel assembly thermo-mechanics. This capability is the initial step toward incorporating an improved predictive nuclear fuel assembly modeling capability to accurately account for source-terms and boundary conditions of traditional (single-pin) nuclear fuel performance simulation, such as the neutron flux distribution, coolant conditions, and assembly mechanical stresses. A novel scheme is introduced for transferring the power distribution from the Scale/Denovo (Denovo) radiation transport code (structured, Cartesian mesh with smeared materials within each cell) to AMPFuel (unstructured, hexagonal mesh with a single material within each cell), allowing the use of a relatively coarse spatial mesh (10 million elements) for the radiation transport and a fine spatial mesh (3.3 billion elements) for thermo-mechanics with very little loss of accuracy. In addition, a new nuclear fuel-specific preconditioner was developed to account for the high aspect ratio of each fuel pin (12 feet axially, but 1 4 inches in diameter) with many individual fuel regions (pellets). With this novel capability, AMPFuel was used to model an entire 17 17 pressurized water reactor fuel assembly with many of the features resolved in three dimensions (for thermo-mechanics and/or neutronics), including the fuel, gap, and cladding of each of the 264 fuel pins; the 25 guide tubes; the top and bottom structural regions; and the upper and lower (neutron) reflector regions. The final, full assembly calculation was executed on Jaguar using 40,000 cores in under 10 hours to model over 162

  5. Integrative Curriculum Development in Nuclear Education and Research Vertical Enhancement Program

    International Nuclear Information System (INIS)

    Egarievwe, Stephen U.; Jow, Julius O.; Edwards, Matthew E.; Montgomery, V. Trent; James, Ralph B.; Blackburn, Noel D.; Glenn, Chance M.

    2015-01-01

    Using a vertical education enhancement model, a Nuclear Education and Research Vertical Enhancement (NERVE) program was developed. The NERVE program is aimed at developing nuclear engineering education and research to 1) enhance skilled workforce development in disciplines relevant to nuclear power, national security and medical physics, and 2) increase the number of students and faculty from underrepresented groups (women and minorities) in fields related to the nuclear industry. The program uses multi-track training activities that vertically cut across the several education domains: undergraduate degree programs, graduate schools, and post-doctoral training. In this paper, we present the results of an integrative curriculum development in the NERVE program. The curriculum development began with nuclear content infusion into existing science, engineering and technology courses. The second step involved the development of nuclear engineering courses: 1) Introduction to Nuclear Engineering, 2) Nuclear Engineering I, and 2) Nuclear Engineering II. The third step is the establishment of nuclear engineering concentrations in two engineering degree programs: 1) electrical engineering, and 2) mechanical engineering. A major outcome of the NERVE program is a collaborative infrastructure that uses laboratory work, internships at nuclear facilities, on-campus research, and mentoring in collaboration with industry and government partners to provide hands-on training for students. The major activities of the research and education collaborations include: - One-week spring training workshop at Brookhaven National Laboratory: The one-week training and workshop is used to enhance research collaborations and train faculty and students on user facilities/equipment at Brookhaven National Laboratory, and for summer research internships. Participants included students, faculty members at Alabama A and M University and research collaborators at BNL. The activities include 1) tour and

  6. Integrative Curriculum Development in Nuclear Education and Research Vertical Enhancement Program

    Energy Technology Data Exchange (ETDEWEB)

    Egarievwe, Stephen U.; Jow, Julius O.; Edwards, Matthew E.; Montgomery, V. Trent [Nuclear Engineering and Radiological Science Center, Alabama A and M University, Huntsville, AL (United States); James, Ralph B.; Blackburn, Noel D. [Nonproliferation and National Security Department, Brookhaven National Laboratory, Upton, NY (United States); Glenn, Chance M. [College of Engineering, Technology and Physical Sciences, Alabama A and M University, Huntsville, AL (United States)

    2015-07-01

    Using a vertical education enhancement model, a Nuclear Education and Research Vertical Enhancement (NERVE) program was developed. The NERVE program is aimed at developing nuclear engineering education and research to 1) enhance skilled workforce development in disciplines relevant to nuclear power, national security and medical physics, and 2) increase the number of students and faculty from underrepresented groups (women and minorities) in fields related to the nuclear industry. The program uses multi-track training activities that vertically cut across the several education domains: undergraduate degree programs, graduate schools, and post-doctoral training. In this paper, we present the results of an integrative curriculum development in the NERVE program. The curriculum development began with nuclear content infusion into existing science, engineering and technology courses. The second step involved the development of nuclear engineering courses: 1) Introduction to Nuclear Engineering, 2) Nuclear Engineering I, and 2) Nuclear Engineering II. The third step is the establishment of nuclear engineering concentrations in two engineering degree programs: 1) electrical engineering, and 2) mechanical engineering. A major outcome of the NERVE program is a collaborative infrastructure that uses laboratory work, internships at nuclear facilities, on-campus research, and mentoring in collaboration with industry and government partners to provide hands-on training for students. The major activities of the research and education collaborations include: - One-week spring training workshop at Brookhaven National Laboratory: The one-week training and workshop is used to enhance research collaborations and train faculty and students on user facilities/equipment at Brookhaven National Laboratory, and for summer research internships. Participants included students, faculty members at Alabama A and M University and research collaborators at BNL. The activities include 1) tour and

  7. Integration of distributed plant process computer systems to nuclear power generation facilities

    International Nuclear Information System (INIS)

    Bogard, T.; Finlay, K.

    1996-01-01

    Many operating nuclear power generation facilities are replacing their plant process computer. Such replacement projects are driven by equipment obsolescence issues and associated objectives to improve plant operability, increase plant information access, improve man machine interface characteristics, and reduce operation and maintenance costs. This paper describes a few recently completed and on-going replacement projects with emphasis upon the application integrated distributed plant process computer systems. By presenting a few recent projects, the variations of distributed systems design show how various configurations can address needs for flexibility, open architecture, and integration of technological advancements in instrumentation and control technology. Architectural considerations for optimal integration of the plant process computer and plant process instrumentation ampersand control are evident from variations of design features

  8. Timetable Attractiveness Parameters

    DEFF Research Database (Denmark)

    Schittenhelm, Bernd

    2008-01-01

    Timetable attractiveness is influenced by a set of key parameters that are described in this article. Regarding the superior structure of the timetable, the trend in Europe goes towards periodic regular interval timetables. Regular departures and focus on optimal transfer possibilities make...... these timetables attractive. The travel time in the timetable depends on the characteristics of the infrastructure and rolling stock, the heterogeneity of the planned train traffic and the necessary number of transfers on the passenger’s journey. Planned interdependencies between trains, such as transfers...... and heterogeneous traffic, add complexity to the timetable. The risk of spreading initial delays to other trains and parts of the network increases with the level of timetable complexity....

  9. Sharing Rare Attitudes Attracts.

    Science.gov (United States)

    Alves, Hans

    2018-04-01

    People like others who share their attitudes. Online dating platforms as well as other social media platforms regularly rely on the social bonding power of their users' shared attitudes. However, little is known about moderating variables. In the present work, I argue that sharing rare compared with sharing common attitudes should evoke stronger interpersonal attraction among people. In five studies, I tested this prediction for the case of shared interests from different domains. I found converging evidence that people's rare compared with their common interests are especially potent to elicit interpersonal attraction. I discuss the current framework's theoretical implications for impression formation and impression management as well as its practical implications for improving online dating services.

  10. Dynamic Isotope Power System (DIPS) Applications Study. Volume II. Nuclear Integrated Multimission Spacecraft (NIMS) design definition. Final report

    International Nuclear Information System (INIS)

    1979-11-01

    The design requirements for the Nuclear Integrated Multimission Spacecraft. (NIMS) are discussed in detail. The requirements are a function of mission specifications, payload, control system requirements, electric system specifications, and cost limitations

  11. Application of Framework for Integrating Safety, Security and Safeguards (3Ss) into the Design Of Used Nuclear Fuel Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Badwan, Faris M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Demuth, Scott F [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-01-06

    Department of Energy’s Office of Nuclear Energy, Fuel Cycle Research and Development develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development focused on used nuclear fuel recycling and waste management to meet U.S. needs. Used nuclear fuel is currently stored onsite in either wet pools or in dry storage systems, with disposal envisioned in interim storage facility and, ultimately, in a deep-mined geologic repository. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Integrating safety, security, and safeguards (3Ss) fully in the early stages of the design process for a new nuclear facility has the potential to effectively minimize safety, proliferation, and security risks. The 3Ss integration framework could become the new national and international norm and the standard process for designing future nuclear facilities. The purpose of this report is to develop a framework for integrating the safety, security and safeguards concept into the design of Used Nuclear Fuel Storage Facility (UNFSF). The primary focus is on integration of safeguards and security into the UNFSF based on the existing Nuclear Regulatory Commission (NRC) approach to addressing the safety/security interface (10 CFR 73.58 and Regulatory Guide 5.73) for nuclear power plants. The methodology used for adaptation of the NRC safety/security interface will be used as the basis for development of the safeguards /security interface and later will be used as the basis for development of safety and safeguards interface. Then this will complete the integration cycle of safety, security, and safeguards. The overall methodology for integration of 3Ss will be proposed, but only the integration of safeguards and security will be applied to the design of the

  12. Antipsychotics and physical attractiveness.

    Science.gov (United States)

    Seeman, Mary V

    2011-10-01

    Antipsychotics are effective in treating the symptoms of schizophrenia, but they may induce adverse effects, some of which-those that impact negatively on physical appearance-have not been sufficiently discussed in the psychiatric literature. Through a narrative review, to catalog antipsychotic side effects that interfere with physical attractiveness and to suggest ways of addressing them. PubMed databases were searched for information on the association between "antipsychotic side effects" and "attractiveness" using those two search phrases plus the following terms: "weight," "teeth," "skin," "hair," "eyes," "gait," "voice," "odor." Data from relevant qualitative and quantitative articles were considered, contextualized, and summarized. Antipsychotics, as a group, increase weight and may lead to dry mouth and bad breath, cataracts, hirsutism, acne, and voice changes; they may disturb symmetry of gait and heighten the risk for tics and spasms and incontinence, potentially undermining a person's attractiveness. Clinicians need to be aware of the impact of therapeutic drugs on appearance and how important this issue is to patients. Early in treatment, they need to plan preventive and therapeutic strategies.

  13. An approach for evaluating the integrity of fuel applied in Innovative Nuclear Energy Systems

    International Nuclear Information System (INIS)

    Nakae, Nobuo; Ozawa, Takayuki; Ohta, Hirokazu; Ogata, Takanari; Sekimoto, Hiroshi

    2014-01-01

    One of the important issues in the study of Innovative Nuclear Energy Systems is evaluating the integrity of fuel applied in Innovative Nuclear Energy Systems. An approach for evaluating the integrity of the fuel is discussed here based on the procedure currently used in the integrity evaluation of fast reactor fuel. The fuel failure modes determining fuel life time were reviewed and fuel integrity was analyzed and compared with the failure criteria. Metal and nitride fuels with austenitic and ferritic stainless steel (SS) cladding tubes were examined in this study. For the purpose of representative irradiation behavior analyses of the fuel for Innovative Nuclear Energy Systems, the correlations of the cladding characteristics were modeled based on well-known characteristics of austenitic modified 316 SS (PNC316), ferritic–martensitic steel (PNC–FMS) and oxide dispersion strengthened steel (PNC–ODS). The analysis showed that the fuel lifetime is limited by channel fracture which is a nonductile type (brittle) failure associated with a high level of irradiation-induced swelling in the case of austenitic steel cladding. In case of ferritic steel, on the other hand, the fuel lifetime is controlled by cladding creep rupture. The lifetime evaluated here is limited to 200 GW d/t, which is lower than the target burnup value of 500 GW d/t. One of the possible measures to extend the lifetime may be reducing the fuel smeared density and ventilating fission gas in the plenum for metal fuel and by reducing the maximum cladding temperature from 650 to 600 °C for both metal and nitride fuel

  14. An approach for evaluating the integrity of fuel applied in Innovative Nuclear Energy Systems

    Energy Technology Data Exchange (ETDEWEB)

    Nakae, Nobuo, E-mail: nakae-nobuo@jnes.go.jp [Center for Research into Innovative Nuclear Energy System, Tokyo Institute of Technology, 2-12-1-N1-19, Ookayama, Meguro-ku, Tokyo 152-8550 (Japan); Ozawa, Takayuki [Advanced Nuclear System Research and Development Directorate, Japan Atomic Energy Agency, 4-33, Muramatsu, Tokai-mura, Ibaraki-ken 319-1194 (Japan); Ohta, Hirokazu; Ogata, Takanari [Nuclear Technology Research Laboratory, Central Research Institute of Electric Power Industry, 2-11-1, Iwado Kita, Komae-shi, Tokyo 201-8511 (Japan); Sekimoto, Hiroshi [Center for Research into Innovative Nuclear Energy System, Tokyo Institute of Technology, 2-12-1-N1-19, Ookayama, Meguro-ku, Tokyo 152-8550 (Japan)

    2014-03-15

    One of the important issues in the study of Innovative Nuclear Energy Systems is evaluating the integrity of fuel applied in Innovative Nuclear Energy Systems. An approach for evaluating the integrity of the fuel is discussed here based on the procedure currently used in the integrity evaluation of fast reactor fuel. The fuel failure modes determining fuel life time were reviewed and fuel integrity was analyzed and compared with the failure criteria. Metal and nitride fuels with austenitic and ferritic stainless steel (SS) cladding tubes were examined in this study. For the purpose of representative irradiation behavior analyses of the fuel for Innovative Nuclear Energy Systems, the correlations of the cladding characteristics were modeled based on well-known characteristics of austenitic modified 316 SS (PNC316), ferritic–martensitic steel (PNC–FMS) and oxide dispersion strengthened steel (PNC–ODS). The analysis showed that the fuel lifetime is limited by channel fracture which is a nonductile type (brittle) failure associated with a high level of irradiation-induced swelling in the case of austenitic steel cladding. In case of ferritic steel, on the other hand, the fuel lifetime is controlled by cladding creep rupture. The lifetime evaluated here is limited to 200 GW d/t, which is lower than the target burnup value of 500 GW d/t. One of the possible measures to extend the lifetime may be reducing the fuel smeared density and ventilating fission gas in the plenum for metal fuel and by reducing the maximum cladding temperature from 650 to 600 °C for both metal and nitride fuel.

  15. Study on integrity evaluation of structures associated with nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The 3.11 Tohoku District -off the Pacific Ocean Earthquake and tsunami made us observations of tsunami height in large exceedance of the design, and besides it gave the most damages to several nuclear power plants facing the Pacific Ocean at source area of the earthquake. Particularly, at Fukushima-Daiichi Nuclear Power Plant, the great tsunami caused the simultaneous failure on several plant's equipment and components, which escalated into the core damage. Considering these background, the objective of this research is to enhance fundamental technology relative to integrity evaluation of SSC's (System, Structure, components) targeting external events such as earthquakes and tsunamis. Specifically, it is performed to develop structure evaluation methods against tsunami, to develop seismic isolation system, and to enhance non-liner analysis methods for building and so on. In viewpoint of the other external events except earthquake and tsunami, it was performed to develop impact analysis methods on building and outdoor structure against swept things caused by tornadoes. After that on the basis of these developments, it is performed to draw up guidelines such as the base isolation structure review guide, and the structure design and risk evaluation guide against tsunami, which are to be used in cross-check analysis targeting integrity evaluation of nuclear power plant's structures against external events such as earthquakes and tsunamis. (author)

  16. Study on integrity evaluation of structures associated with nuclear power plants

    International Nuclear Information System (INIS)

    2013-01-01

    The 3.11 Tohoku District -off the Pacific Ocean Earthquake and tsunami made us observations of tsunami height in large exceedance of the design, and besides it gave the most damages to several nuclear power plants facing the Pacific Ocean at source area of the earthquake. Particularly, at Fukushima-Daiichi Nuclear Power Plant, the great tsunami caused the simultaneous failure on several plant's equipment and components, which escalated into the core damage. Considering these background, the objective of this research is to enhance fundamental technology relative to integrity evaluation of SSC's (System, Structure, components) targeting external events such as earthquakes and tsunamis. Specifically, it is performed to develop structure evaluation methods against tsunami, to develop seismic isolation system, and to enhance non-liner analysis methods for building and so on. In viewpoint of the other external events except earthquake and tsunami, it was performed to develop impact analysis methods on building and outdoor structure against swept things caused by tornadoes. After that on the basis of these developments, it is performed to draw up guidelines such as the base isolation structure review guide, and the structure design and risk evaluation guide against tsunami, which are to be used in cross-check analysis targeting integrity evaluation of nuclear power plant's structures against external events such as earthquakes and tsunamis. (author)

  17. Integrated software package for nuclear material safeguards in a MOX fuel fabrication facility

    International Nuclear Information System (INIS)

    Schreiber, H.J.; Piana, M.; Moussalli, G.; Saukkonen, H.

    2000-01-01

    Since computerized data processing was introduced to Safeguards at large bulk handling facilities, a large number of individual software applications have been developed for nuclear material Safeguards implementation. Facility inventory and flow data are provided in computerized format for performing stratification, sample size calculation and selection of samples for destructive and non-destructive assay. Data is collected from nuclear measurement systems running in attended, unattended mode and more recently from remote monitoring systems controlled. Data sets from various sources have to be evaluated for Safeguards purposes, such as raw data, processed data and conclusions drawn from data evaluation results. They are reported in computerized format at the International Atomic Energy Agency headquarters and feedback from the Agency's mainframe computer system is used to prepare and support Safeguards inspection activities. The integration of all such data originating from various sources cannot be ensured without the existence of a common data format and a database system. This paper describes the fundamental relations between data streams, individual data processing tools, data evaluation results and requirements for an integrated software solution to facilitate nuclear material Safeguards at a bulk handling facility. The paper also explains the basis for designing a software package to manage data streams from various data sources and for incorporating diverse data processing tools that until now have been used independently from each other and under different computer operating systems. (author)

  18. Development of an integrated system for nuclear material accountancy and control at JAERI

    International Nuclear Information System (INIS)

    Nishimura, Hideo; Nishizawa, Satoshi

    1993-01-01

    This paper describes the design concept and the current status of an integrated system for nuclear material accountancy and control, which is under development at JAERI. We, at JAERI, have decided to update the current system for material accountancy and control and to develop the integrated new system with a consolidated data base in order to augment transparency, credibility and promptness of the system, to materialize a prudent control of obligations required by bilateral nuclear cooperation agreements, and to give information for the physical protection, safely handling, property control and cost-effective use of nuclear material and for public relations. The system is composed of two work-stations operated by UNIX, one for implementation and the other for development, and many terminals located at the headquarters, administrative offices, and research facilities and laboratories. It is connected with a mainframe computer. There are many files on the data base to record inventory changes, book and physical inventories, and statistics on material balances. These files are controlled by a commercial data base management system which enables us to make access to data on the files with a simple query language, spread sheet type software or an application program. (author)

  19. Study on the Standard Establishment for the Integrity Assessment of Nuclear Fuel Cladding Materials

    Energy Technology Data Exchange (ETDEWEB)

    Kang, S-S; Kim, S-H; Jung, Y-K; Yang, C-Y; Kim, I-G; Choi, Y-H; Kim, H-J; Kim, M-W; Rho, B-H [KINS, Daejeon (Korea, Republic of)

    2008-02-15

    Fuel cladding material plays important role as a primary structure under the high temperature, high pressure and neutron environment of nuclear power plant. According to this environment, cladding material can be experienced several type aging phenomena including the neutron irradiation embrittlement. On the other hand, although the early nuclear power plant was designed to fitting into the 40MWd/KgU burn-up, the currently power plant intends to go to the high burn-up range. In this case, the safety criteria which was established at low burn-up needs to conform the applicability at the high burn-up. In this study, the safety criteria of fuel cladding material was reviewed to assess the cladding material integrity, and the material characteristics of cladding were reviewed. The current LOCA criterial was also reviewed, and the basic study for re-establishment of LOCA criteria was performed. The time concept safety criteria was also discussed to prevent the breakaway oxidation. Through the this study, safety issues will be produced and be helpful for integrity insurance of nuclear fuel cladding material. This report is the final report.

  20. Study on the standard establishment for the integrity assessment of nuclear fuel cladding Materials

    Energy Technology Data Exchange (ETDEWEB)

    Kang, S. S.; Kim, S. H.; Jung, Y. K.; Yang, C. Y.; Kim, I. G.; Choi, Y. H.; Kim, H. J.; Kim, M. W.; Rho, B. H. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2007-02-15

    Fuel cladding material plays important role as a primary structure under the high temperature, high pressure and neutron environment of nuclear power plant. According to this environment, cladding material can be experienced several type aging phenomena including the neutron irradiation embrittlement. On the other hand, although the early nuclear power plant was designed to fitting into the 40MWd/KgU burn-up, the currently power plant intends to go to the high burn-up range. In this case, the safety criteria which was established at low burn-up needs to conform the applicability at the high burn-up. In this study, the safety criteria of fuel cladding material was reviewed to assess the cladding material integrity, and the material characteristics of cladding were reviewed. The current LOCA criterial was also reviewed, and the basic study for re-establishment of LOCA criteria was performed. The time concept safety criteria was also discussed to prevent the breakaway oxidation. Through the this study, safety issues will be produced and be helpful for integrity insurance of nuclear fuel cladding material. This report is 2nd term report.

  1. A Study on the Evaluation Technology of Welds Integrity in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Chang, Hyun Young; Kim, Jong Sung; Jin, Tae Eun

    2007-01-01

    The final goal of this study is to develop the core technologies applicable to the design, operation and maintenance of welds in nuclear structures. This study includes predicting microstructure changes and residual stress for welded parts of nuclear power plant components. Furthermore, researches are performed on evaluating fatigue, corrosion, and hydrogen induced cracking and finally constructs systematically integrated evaluation system for structural integrity of nuclear welded structures. In this study, metallurgical and mechanical approaches have been effectively coordinated considering real welding phenomena in the fields of welds properties such as microstructure, composition and residual stress, and in the fields of damage evaluations such as fatigue, corrosion, fatigue crack propagation, and stress corrosion cracking. Evaluation techniques tried in this study can be much economical and effective in that it uses theoretical/semi-empirical but includes many additional parameters that can be introduced in real phenomena such as phase transformation, strength mismatch and residual stress. It is clear that residual stress makes great contribution to fatigue and stress corrosion cracking. Therefore the mitigation techniques have been approached by reducing the residual stress of selected parts resulting in successful conclusions

  2. Design of an integral missile shield in integrated head assembly for pressurized water reactor at commercial nuclear plants

    International Nuclear Information System (INIS)

    Baliga, Ravi; Watts, Tom Neal; Kamath, Harish

    2015-01-01

    In ICONE22, the authors presented the Integrated Head Assembly (IHA) design concept implemented at Callaway Nuclear Power Plant in Missouri, USA. The IHA concept is implemented to reduce the outage duration and the associated radiation exposure to the workers by reducing critical path time during Plant Refueling Outage. One of the head area components in the IHA is a steel missile shield designed to protect the Control Rod Drive Mechanism (CRDM) assembly from damaging other safety-related components in the vicinity in the Containment. Per Federally implemented General Design Criteria for commercial nuclear plants in the USA, the design of Nuclear Steam Supply System (NSSS) must provide protection from the damages caused by a postulated event of CRDM housing units and their associated parts disengaging from the reactor vessel assembly. This event is considered as a Loss of Coolant Accident (LOCA) and assumes that once the CRDM housing unit and their associated parts disengage from the reactor vessel internals assembly, they travel upward by the water jet with the following sequence of events: Per Reference 1, the drive shaft and control rod cluster are forced out of the reactor core by the differential pressure across the drive shaft with the assumption that the drive shaft and control rod cluster, latched together, are fully inserted when the accident occurs. After the travel, the rod cluster control spider will impact the lower side of the upper support plate inside the reactor vessel fracturing the flexure arms in the joint freeing the drive shaft from the control rod cluster. The control rod cluster is stopped by the upper support plate and will remain below the upper support plate during this accident. However, the drive shaft will continue to accelerate in the upward direction until it is stopped by a safety feature in the IHA. The integral missile shield as a safety feature in the IHA is designed to stop the CRDM drive shaft from moving further up in the

  3. Proceedings of the 24th Seismic Research Review: Nuclear Explosion Monitoring: Innovation and Integration

    International Nuclear Information System (INIS)

    Warren, N. Jill

    2002-01-01

    These proceedings contain papers prepared for the 24th Seismic Research Review: Nuclear Explosion Monitoring: Innovation and Integration, held 17-19 September, 2002 in Ponte Vedra Beach, Florida. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  4. Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1995-09-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions

  5. Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

  6. Safety, reliability, risk management and human factors: an integrated engineering approach applied to nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Vasconcelos, Vanderley de; Silva, Eliane Magalhaes Pereira da; Costa, Antonio Carlos Lopes da; Reis, Sergio Carneiro dos [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)], e-mail: vasconv@cdtn.br, e-mail: silvaem@cdtn.br, e-mail: aclc@cdtn.br, e-mail: reissc@cdtn.br

    2009-07-01

    Nuclear energy has an important engineering legacy to share with the conventional industry. Much of the development of the tools related to safety, reliability, risk management, and human factors are associated with nuclear plant processes, mainly because the public concern about nuclear power generation. Despite the close association between these subjects, there are some important different approaches. The reliability engineering approach uses several techniques to minimize the component failures that cause the failure of the complex systems. These techniques include, for instance, redundancy, diversity, standby sparing, safety factors, and reliability centered maintenance. On the other hand system safety is primarily concerned with hazard management, that is, the identification, evaluation and control of hazards. Rather than just look at failure rates or engineering strengths, system safety would examine the interactions among system components. The events that cause accidents may be complex combinations of component failures, faulty maintenance, design errors, human actions, or actuation of instrumentation and control. Then, system safety deals with a broader spectrum of risk management, including: ergonomics, legal requirements, quality control, public acceptance, political considerations, and many other non-technical influences. Taking care of these subjects individually can compromise the completeness of the analysis and the measures associated with both risk reduction, and safety and reliability increasing. Analyzing together the engineering systems and controls of a nuclear facility, their management systems and operational procedures, and the human factors engineering, many benefits can be realized. This paper proposes an integration of these issues based on the application of systems theory. (author)

  7. Proceedings of the 24th Seismic Research Review: Nuclear Explosion Monitoring: Innovation and Integration

    Energy Technology Data Exchange (ETDEWEB)

    Warren, N. Jill [Editor

    2002-09-17

    These proceedings contain papers prepared for the 24th Seismic Research Review: Nuclear Explosion Monitoring: Innovation and Integration, held 17-19 September, 2002 in Ponte Vedra Beach, Florida. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  8. Safety, reliability, risk management and human factors: an integrated engineering approach applied to nuclear facilities

    International Nuclear Information System (INIS)

    Vasconcelos, Vanderley de; Silva, Eliane Magalhaes Pereira da; Costa, Antonio Carlos Lopes da; Reis, Sergio Carneiro dos

    2009-01-01

    Nuclear energy has an important engineering legacy to share with the conventional industry. Much of the development of the tools related to safety, reliability, risk management, and human factors are associated with nuclear plant processes, mainly because the public concern about nuclear power generation. Despite the close association between these subjects, there are some important different approaches. The reliability engineering approach uses several techniques to minimize the component failures that cause the failure of the complex systems. These techniques include, for instance, redundancy, diversity, standby sparing, safety factors, and reliability centered maintenance. On the other hand system safety is primarily concerned with hazard management, that is, the identification, evaluation and control of hazards. Rather than just look at failure rates or engineering strengths, system safety would examine the interactions among system components. The events that cause accidents may be complex combinations of component failures, faulty maintenance, design errors, human actions, or actuation of instrumentation and control. Then, system safety deals with a broader spectrum of risk management, including: ergonomics, legal requirements, quality control, public acceptance, political considerations, and many other non-technical influences. Taking care of these subjects individually can compromise the completeness of the analysis and the measures associated with both risk reduction, and safety and reliability increasing. Analyzing together the engineering systems and controls of a nuclear facility, their management systems and operational procedures, and the human factors engineering, many benefits can be realized. This paper proposes an integration of these issues based on the application of systems theory. (author)

  9. Structural integrity analysis of an Ignalina nuclear power plant building subjected to an airplane crash

    International Nuclear Information System (INIS)

    Dundulis, Gintautas; Kulak, Ronald F.; Marchertas, Algirdas; Uspuras, Eugenijus

    2007-01-01

    Recent terrorist attacks using commandeered commercial airliners on civil structures have raised the issue of the ability of nuclear power plants to survive the consequences of an airliner crash. The structural integrity analysis due to the effects of an aircraft crash on an Ignalina nuclear power plant (INPP) accident localization system (ALS) building is the subject of this paper. A combination of the finite element method and empirical relationships were used for the analysis. A global structural integrity analysis was performed for a portion of the ALS building using the dynamic loading from an aircraft crash impact model. The local effects caused by impact of the aircraft's engine on the building wall were evaluated independently by using an empirical formula. The results from the crash analysis of a twin engine commercial aircraft show that the impacted reinforced concrete wall of the ALS building will not have through-the-wall concrete failure, and the reinforcement will not fail. Strain-rate effects were found to delay the onset of cracking. Therefore, the structural integrity of the impacted wall of the INPP ALS building will be maintained during the crash event studied

  10. Integrated Level 3 risk assessment for the LaSalle Unit 2 nuclear power plant

    International Nuclear Information System (INIS)

    Payne, A.C. Jr.; Brown, T.D.; Miller, L.A.

    1991-01-01

    An integrated Level 3 probabilistic risk assessment (PRA) was performed on the LaSalle County Station nuclear power plant using state-of-the-art PRA analysis techniques. The objective of this study was to provide an estimate of the risk to the offsite population during full power operation of the plant and to include a characterization of the uncertainties in the calculated risk values. Uncertainties were included in the accident frequency analysis, accident progression analysis, and the source term analysis. Only weather uncertainties were included in the consequence analysis. In this paper selected results from the accident frequency, accident progression, source term, consequence, and integrated risk analyses are discussed and the methods used to perform a fully integrated Level 3 PRA are examined. LaSalle County Station is a two-unit nuclear power plant located 55 miles southwest of Chicago, Illinois. Each unit utilizes a Mark 2 containment to house a General Electric 3323 MWt BWR-5 reactor. This PRA, which was performed on Unit 2, included internal as well as external events. External events that were propagated through the risk analysis included earthquakes, fires, and floods. The internal event accident scenarios included transients, transient-induced LOCAs (inadvertently stuck open relief valves), anticipated transients without scram, and loss of coolant accidents

  11. Proceedings of the CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Diercks, D.R. [Argonne National Lab., IL (United States)

    1997-02-01

    The objective of the workshop was to provide a working forum for the exchange of information by contributing experts on current issues related to PWR steam generator tube integrity. One hundred persons from 15 countries attended the workshop, including 36 from regulatory and nuclear policy agencies, 28 from research and development laboratories, 18 from nuclear vendors and consulting firms, and 18 from electrical utilities. The workshop opened with a plenary session; the first part of the session covered international steam generator regulatory practices and issues, featuring speakers from regulatory bodies in Belgium, France, Japan, Spain, and the US. In Part 2 of the plenary session, comprehensive technical overviews on steam generator tubing degradation, inspection, and integrity were presented by authorities in these fields from the US, France, and Belgium. Parallel working sessions on the second and third days of the workshop then developed findings and recommendations in the areas of (1) tubing degradation, (2) tubing inspection, (3) tubing integrity, (4) preventative and corrective measures, and (5) operational aspects and risk analysis. On the final day of the workshop, the working-session facilitators presented summaries of their sessions to the workshop attendees. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  12. Proceedings of the CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants

    International Nuclear Information System (INIS)

    Diercks, D.R.

    1997-02-01

    The objective of the workshop was to provide a working forum for the exchange of information by contributing experts on current issues related to PWR steam generator tube integrity. One hundred persons from 15 countries attended the workshop, including 36 from regulatory and nuclear policy agencies, 28 from research and development laboratories, 18 from nuclear vendors and consulting firms, and 18 from electrical utilities. The workshop opened with a plenary session; the first part of the session covered international steam generator regulatory practices and issues, featuring speakers from regulatory bodies in Belgium, France, Japan, Spain, and the US. In Part 2 of the plenary session, comprehensive technical overviews on steam generator tubing degradation, inspection, and integrity were presented by authorities in these fields from the US, France, and Belgium. Parallel working sessions on the second and third days of the workshop then developed findings and recommendations in the areas of (1) tubing degradation, (2) tubing inspection, (3) tubing integrity, (4) preventative and corrective measures, and (5) operational aspects and risk analysis. On the final day of the workshop, the working-session facilitators presented summaries of their sessions to the workshop attendees. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  13. Structural integrity analysis of an Ignalina nuclear power plant building subjected to an airplane crash

    Energy Technology Data Exchange (ETDEWEB)

    Dundulis, Gintautas [Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, 3 Breslaujos, 44403 Kaunas-35 (Lithuania)]. E-mail: gintas@isag.lei.lt; Kulak, Ronald F. [RFK Engineering Mechanics Consultants (United States); Marchertas, Algirdas [Northern Illinois University (United States); Uspuras, Eugenijus [Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, 3 Breslaujos, 44403 Kaunas-35 (Lithuania)

    2007-08-15

    Recent terrorist attacks using commandeered commercial airliners on civil structures have raised the issue of the ability of nuclear power plants to survive the consequences of an airliner crash. The structural integrity analysis due to the effects of an aircraft crash on an Ignalina nuclear power plant (INPP) accident localization system (ALS) building is the subject of this paper. A combination of the finite element method and empirical relationships were used for the analysis. A global structural integrity analysis was performed for a portion of the ALS building using the dynamic loading from an aircraft crash impact model. The local effects caused by impact of the aircraft's engine on the building wall were evaluated independently by using an empirical formula. The results from the crash analysis of a twin engine commercial aircraft show that the impacted reinforced concrete wall of the ALS building will not have through-the-wall concrete failure, and the reinforcement will not fail. Strain-rate effects were found to delay the onset of cracking. Therefore, the structural integrity of the impacted wall of the INPP ALS building will be maintained during the crash event studied.

  14. An integrated computer-based procedure for teamwork in digital nuclear power plants.

    Science.gov (United States)

    Gao, Qin; Yu, Wenzhu; Jiang, Xiang; Song, Fei; Pan, Jiajie; Li, Zhizhong

    2015-01-01

    Computer-based procedures (CBPs) are expected to improve operator performance in nuclear power plants (NPPs), but they may reduce the openness of interaction between team members and harm teamwork consequently. To support teamwork in the main control room of an NPP, this study proposed a team-level integrated CBP that presents team members' operation status and execution histories to one another. Through a laboratory experiment, we compared the new integrated design and the existing individual CBP design. Sixty participants, randomly divided into twenty teams of three people each, were assigned to the two conditions to perform simulated emergency operating procedures. The results showed that compared with the existing CBP design, the integrated CBP reduced the effort of team communication and improved team transparency. The results suggest that this novel design is effective to optim team process, but its impact on the behavioural outcomes may be moderated by more factors, such as task duration. The study proposed and evaluated a team-level integrated computer-based procedure, which present team members' operation status and execution history to one another. The experimental results show that compared with the traditional procedure design, the integrated design reduces the effort of team communication and improves team transparency.

  15. Are Brazil nuts attractive?

    Science.gov (United States)

    Sanders, Duncan A; Swift, Michael R; Bowley, R M; King, P J

    2004-11-12

    We present event-driven simulation results for single and multiple intruders in a vertically vibrated granular bed. Under our vibratory conditions, the mean vertical position of a single intruder is governed primarily by a buoyancylike effect. Multiple intruders also exhibit buoyancy governed behavior; however, multiple neutrally buoyant intruders cluster spontaneously and undergo horizontal segregation. These effects can be understood by considering the dynamics of two neutrally buoyant intruders. We have measured an attractive force between such intruders which has a range of five intruder diameters, and we provide a mechanistic explanation for the origins of this force.

  16. Contributions to Integral Nuclear Data in ICSBEP and IRPhEP since ND 2013

    Energy Technology Data Exchange (ETDEWEB)

    Bess, John D.; Briggs, J. Blair; Gulliford, Jim

    2016-09-01

    The status of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) was last discussed directly with the international nuclear data community at ND2013. Since ND2013, integral benchmark data that are available for nuclear data testing has continued to increase. The status of the international benchmark efforts and the latest contributions to integral nuclear data for testing is discussed. Select benchmark configurations that have been added to the ICSBEP and IRPhEP Handbooks since ND2013 are highlighted. The 2015 edition of the ICSBEP Handbook now contains 567 evaluations with benchmark specifications for 4,874 critical, near-critical, or subcritical configurations, 31 criticality alarm placement/shielding configuration with multiple dose points apiece, and 207 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications. The 2015 edition of the IRPhEP Handbook contains data from 143 different experimental series that were performed at 50 different nuclear facilities. Currently 139 of the 143 evaluations are published as approved benchmarks with the remaining four evaluations published in draft format only. Measurements found in the IRPhEP Handbook include criticality, buckling and extrapolation length, spectral characteristics, reactivity effects, reactivity coefficients, kinetics, reaction-rate distributions, power distributions, isotopic compositions, and/or other miscellaneous types of measurements for various types of reactor systems. Annual technical review meetings for both projects were held in April 2016; additional approved benchmark evaluations will be included in the 2016 editions of these handbooks.

  17. Proceeding of 26th domestic symposium on present and future of integrity monitoring technology in nuclear power generation facilities

    International Nuclear Information System (INIS)

    2000-06-01

    As the 26th domestic symposium of Atomic Energy Research Committee, the Japan Welding Engineering Society, the symposium was held titled as 'Current status and future of integrity monitoring techniques in nuclear power facilities'. Six speakers gave lectures titled as 'Maintenance and integrity monitoring in nuclear power plants', 'Present status of fatigue and creep-fatigue monitoring techniques in the US', 'Fatigue monitoring system in Tsuruga-1 nuclear power station', 'Vibration monitoring technique of rotational machine', 'SCC monitoring with electrochemical noise analysis' and Monitoring technique for corrosive environments and crack shape'. (T. Tanaka)

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  19. A study of non destructive integrity assessment method for structural materials of nuclear reactor. Part 2

    International Nuclear Information System (INIS)

    Totsuka, Nobuo; Matsuzaki, Akihiro

    2011-01-01

    The hardness measurement is one of the most effective way for non destructive integrity assessment evaluating structural materials of nuclear power plants before and after suffering an earthquake. Then an actual evaluation method and effectiveness of the method using portable hardness tester has been reported in the previous Journal. In this study, the developing method which can evaluate more accurately the amount of plastic deformation of the material caused by an earthquake has been reported, based on the experimental results about the hardness change of the material considering the thermal aging due to the plant operation and the cyclic deformation suffered by an earthquake. (author)

  20. Toward an Evolutive and Tightly Integrated Information System for Nuclear Materials Management

    Energy Technology Data Exchange (ETDEWEB)

    Dessoude, O. [Euriware (Areva Group), 25 avenue de Tourville, Equeurdreville, 50100 (France)

    2009-06-15

    From a nuclear materials management standpoint, spent-fuel recycling is considered a very challenging activity. This challenge has its positive counterpart as a lot has been learned from confronting a large variety of nuclear materials, complex material transfers and transformations. Since the inception of its computerized nuclear materials management system, AREVA NC La Hague has relied upon its IT subsidiary EURIWARE for software design and development. In 2003, the founding milestone was the implementation of the new GMP software package (Gestion des Matieres et des Produits - Materials and Products Management). GMP was underpinned by the following principles: reliability, transparency and close integration with the process control layer, so as to mitigate human errors and keep the management process smooth and efficient. In 2005, another major milestone was reached with CMNR (Comptabilite des Matieres Nucleaires Reglementaire - Regulatory Nuclear Materials Accountancy), a system in charge of local accounting and multi-site consolidation at corporate level. In spite of an auspicious start, GMP came up against the same stumbling block as many information systems: the multiplication of interfaces and technologies (entropy increasing over time). For the sake of maintenance, evolutions and performance, AREVA has decided a progressive modernization of its Nuclear Materials Management (NMM) information system. The underlying principle is a clear separation between the main functions: - Physical Follow-up, performed at the plant-level, - Regulatory Accountancy (for IRSN, EURATOM and IAEA safeguards), offering consolidation at the corporate level, - Patrimonial Accountancy (allocation of materials and conditioned wastes to AREVA's customers). The pivotal piece of this multi-year programme is the implementation of a dedicated data repository. We describe its main building blocks and demonstrate how it helps in managing changes to regulation, products, customers and

  1. Reactors licensing: proposal of an integrated quality and environment regulatory structure for nuclear research reactors in Brazil

    International Nuclear Information System (INIS)

    Serra, Reynaldo Cavalcanti

    2014-01-01

    A new integrated regulatory structure based on quality and integrated issues has been proposed to be implemented on the licensing process of nuclear research reactors in Brazil. The study starts with a literature review about the licensing process in several countries, all of them members of the International Atomic Energy Agency. After this phase it is performed a comparative study with the Brazilian licensing process to identify good practices (positive aspects), the gaps on it and to propose an approach of an integrated quality and environmental management system, in order to contribute with a new licensing process scheme in Brazil. The literature review considered the following research nuclear reactors: Jules-Horowitz and OSIRIS (France), Hanaro (Korea), Maples 1 and 2 (Canada), OPAL (Australia), Pallas (Holand), ETRR-2 (Egypt) and IEA-R1 (Brazil). The current nuclear research reactors licensing process in Brazil is conducted by two regulatory bodies: the Brazilian National Nuclear Energy Commission (CNEN) and the Brazilian Institute of Environment and Renewable Natural Resources (IBAMA). CNEN is responsible by nuclear issues, while IBAMA by environmental one. To support the study it was applied a questionnaire and interviews based on the current regulatory structure to four nuclear research reactors in Brazil. Nowadays, the nuclear research reactor’s licensing process, in Brazil, has six phases and the environmental licensing process has three phases. A correlation study among these phases leads to a proposal of a new quality and environmental integrated licensing structure with four harmonized phases, hence reducing potential delays in this process. (author)

  2. Issues of integrating high-tech concepts into nuclear power plant operation

    International Nuclear Information System (INIS)

    Kisner, R.A.; Carter, R.J.; Lindsay, R.W.

    1990-01-01

    The stockpile of new ideas continues to grow for monitoring nuclear power plant parameters, characteristics, and vital signs and for controlling systems, subsystems, and components. This wide selection of monitoring and control software increases the difficulty of designing an integrated control room. As plant control room operators increase their reliance on computerized systems, including real-time plant data and data base systems, the integration of monitoring, diagnostics, and control software into uniform and seamless environment becomes imperative. A systematic approach to evaluating the usefulness of such high-tech control concepts is needed. This paper concentrates on methods to evaluate control concepts by assessing factors that determine a system's potential effectiveness within the context of the overall environment, including both human and machine components. Although not an in-depth study, this paper serves to outline several measures of utility. 21 refs., 3 figs., 2 tabs

  3. Integrated safety assessment report: Integrated Safety Assessment Program: Millstone Nuclear Power Station, Unit 1 (Docket No. 50-245): Draft report

    International Nuclear Information System (INIS)

    1987-04-01

    The Integrated Safety Assessment Program (ISAP) was initiated in November 1984, by the US Nuclear Regulatory Commission to conduct integrated assessments for operating nuclear power reactors. The integrated assessment is conducted in a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. In addition, procedures will be established to allow for a periodic updating of the schedules to account for licensing issues that arise in the future. This report documents the review of Millstone Nuclear Power Station, Unit No. 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit No. 1, is one of two plants being reviewed under the pilot program for ISAP. This report indicates how 85 topics selected for review were addressed. This report presents the staff's recommendations regarding the corrective actions to resolve the 85 topics and other actions to enhance plant safety. The report is being issued in draft form to obtain comments from the licensee, nuclear safety experts, and the Advisory Committee for Reactor Safeguards (ACRS). Once those comments have been resolved, the staff will present its positions, along with a long-term implementation schedule from the licensee, in the final version of this report

  4. The practical implementation of integrated safety management for nuclear safety analysis and fire hazards analysis documentation

    International Nuclear Information System (INIS)

    COLLOPY, M.T.

    1999-01-01

    In 1995 Mr. Joseph DiNunno of the Defense Nuclear Facilities Safety Board issued an approach to describe the concept of an integrated safety management program which incorporates hazard and safety analysis to address a multitude of hazards affecting the public, worker, property, and the environment. Since then the U S . Department of Energy (DOE) has adopted a policy to systematically integrate safety into management and work practices at all levels so that missions can be completed while protecting the public, worker, and the environment. While the DOE and its contractors possessed a variety of processes for analyzing fire hazards at a facility, activity, and job; the outcome and assumptions of these processes have not always been consistent for similar types of hazards within the safety analysis and the fire hazard analysis. Although the safety analysis and the fire hazard analysis are driven by different DOE Orders and requirements, these analyses should not be entirely independent and their preparation should be integrated to ensure consistency of assumptions, consequences, design considerations, and other controls. Under the DOE policy to implement an integrated safety management system, identification of hazards must be evaluated and agreed upon to ensure that the public. the workers. and the environment are protected from adverse consequences. The DOE program and contractor management need a uniform, up-to-date reference with which to plan. budget, and manage nuclear programs. It is crucial that DOE understand the hazards and risks necessarily to authorize the work needed to be performed. If integrated safety management is not incorporated into the preparation of the safety analysis and the fire hazard analysis, inconsistencies between assumptions, consequences, design considerations, and controls may occur that affect safety. Furthermore, confusion created by inconsistencies may occur in the DOE process to grant authorization of the work. In accordance with

  5. Integrated CAE system for nuclear power plants. Development of piping design check system

    International Nuclear Information System (INIS)

    Narikawa, Noboru; Sato, Teruaki

    1994-01-01

    Toshiba Corporation has developed and operated the integrated CAE system for nuclear power plants, the core of which is the engineering data base to manage accurately and efficiently enormous amount of data on machinery, equipment and piping. As the first step of putting knowledge base system to practical use, piping design check system has been developed. By automatically checking up piping design, this system aims at the prevention of overlooking mistakes, efficient design works and the overall quality improvement of design. This system is based on the thought that it supports designers, and final decision is made by designers. This system is composed of the integrated data base, a two-dimensional CAD system and three-dimensional CAD system. The piping design check system is one of the application systems of the integrated CAE system. Object-oriented programming is the base of the piping design check system, and design knowledge and CAD data are necessary. As to the method of realizing the check system, the flow of piping design, the checkup functions, the checkup of interference and attribute base, and the integration of the system are explained. (K.I)

  6. DEVELOPING AN INTEGRATED NATIONAL STRATEGY FOR THE DISPOSITION OF SPENT NUCLEAR FUEL

    International Nuclear Information System (INIS)

    Gelles, C.M.

    2003-01-01

    This paper summarizes the Department of Energy's (DOE's) current efforts to strengthen its activities for the management and disposition of DOE-owned spent nuclear fuel (SNF). In August 2002 an integrated, ''corporate project'' was initiated by the Office of Environmental Management (EM) to develop a fully integrated strategy for disposition of the approximately ∼250,000 DOE SNF assemblies currently managed by EM. Through the course of preliminary design, the focus of this project rapidly evolved to become DOE-wide. It is supported by all DOE organizations involved in SNF management, and represents a marked change in the way DOE conducts its business. This paper provides an overview of the Corporate Project for Integrated/Risk-Driven Disposition of SNF (Corporate SNF Project), including a description of its purpose, scope and deliverables. It also summarizes the results of the integrated project team's (IPT's) conceptual design efforts, including the identification of project/system requirements and alternatives. Finally, this paper highlights the schedule of the corporate project, and its progress towards development of a DOE corporate strategy for SNF disposition

  7. Passive safety systems reliability and integration of these systems in nuclear power plant PSA

    International Nuclear Information System (INIS)

    La Lumia, V.; Mercier, S.; Marques, M.; Pignatel, J.F.

    2004-01-01

    Innovative nuclear reactor concepts could lead to use passive safety features in combination with active safety systems. A passive system does not need active component, external energy, signal or human interaction to operate. These are attractive advantages for safety nuclear plant improvements and economic competitiveness. But specific reliability problems, linked to physical phenomena, can conduct to stop the physical process. In this context, the European Commission (EC) starts the RMPS (Reliability Methods for Passive Safety functions) program. In this RMPS program, a quantitative reliability evaluation of the RP2 system (Residual Passive heat Removal system on the Primary circuit) has been realised, and the results introduced in a simplified PSA (Probabilistic Safety Assessment). The scope is to get out experience of definition of characteristic parameters for reliability evaluation and PSA including passive systems. The simplified PSA, using event tree method, is carried out for the total loss of power supplies initiating event leading to a severe core damage. Are taken into account: failures of components but also failures of the physical process involved (e.g. natural convection) by a specific method. The physical process failure probabilities are assessed through uncertainty analyses based on supposed probability density functions for the characteristic parameters of the RP2 system. The probabilities are calculated by MONTE CARLO simulation coupled to the CATHARE thermalhydraulic code. The yearly frequency of the severe core damage is evaluated for each accident sequence. This analysis has identified the influence of the passive system RP2 and propose a re-dimensioning of the RP2 system in order to satisfy the safety probabilistic objectives for reactor core severe damage. (authors)

  8. Rules of Attraction

    Science.gov (United States)

    2004-01-01

    This image composite shows two of the Mars Exploration Rover Opportunity's magnets, the 'capture' magnet (upper portion of left panel) and the 'filter' magnet (lower portion of left panel). Scientists use these tools to study the origins of martian dust in the atmosphere. The left panel was taken by the rover's panoramic camera. The four panels to the right, taken by the microscopic imager, show close-up views of the two magnets. The bull's-eye appearance of the capture magnet is a result of alternating magnetic fields, which are used to increase overall magnetic force. The filter magnet lacks these alternating fields and consequently produces a weaker magnetic force. This weaker force selectively attracts only strong magnetic particles. Scientists were surprised by the large dark particles on the magnets because airborne particles are smaller in size. They theorize that these spots might be aggregates of small particles that clump together in a magnetic field.

  9. Small Island Visitor Attractions

    Directory of Open Access Journals (Sweden)

    Haven Allahar

    2015-03-01

    Full Text Available This article proposes a process framework for developing and managing visitor attractions (VA in small island developing states with Trinidad and Tobago, a two-island state in the Caribbean, as the case study. An extensive literature review was conducted, supported by field observations, individual depth interviews, and small and large focus group meetings. The process framework identified four sets of processes: national policy formulation and legislation; inventory, classification, evaluation, and ranking of VA; general operations management involving project management activities; and site specific activities of development, operations, and maintenance. The value of the framework lies in the fact that no similar framework applicable to small islands was covered in the literature and validation was obtained from a panel of experts and a cross section of tourism stakeholders in Tobago.

  10. Control of nuclear β-dystroglycan content is crucial for the maintenance of nuclear envelope integrity and function.

    Science.gov (United States)

    Vélez-Aguilera, Griselda; de Dios Gómez-López, Juan; Jiménez-Gutiérrez, Guadalupe E; Vásquez-Limeta, Alejandra; Laredo-Cisneros, Marco S; Gómez, Pablo; Winder, Steve J; Cisneros, Bulmaro

    2018-02-01

    β-Dystroglycan (β-DG) is a plasma membrane protein that has ability to target to the nuclear envelope (NE) to maintain nuclear architecture. Nevertheless, mechanisms controlling β-DG nuclear localization and the physiological consequences of a failure of trafficking are largely unknown. We show that β-DG has a nuclear export pathway in myoblasts that depends on the recognition of a nuclear export signal located in its transmembrane domain, by CRM1. Remarkably, NES mutations forced β-DG nuclear accumulation resulting in mislocalization and decreased levels of emerin and lamin B1 and disruption of various nuclear processes in which emerin (centrosome-nucleus linkage and β-catenin transcriptional activity) and lamin B1 (cell cycle progression and nucleoli structure) are critically involved. In addition to nuclear export, the lifespan of nuclear β-DG is restricted by its nuclear proteasomal degradation. Collectively our data show that control of nuclear β-DG content by the combination of CRM1 nuclear export and nuclear proteasome pathways is physiologically relevant to preserve proper NE structure and activity. Copyright © 2017 Elsevier B.V. All rights reserved.

  11. Integration of the security systems in the architectural design of nuclear and important buildings in Egypt

    International Nuclear Information System (INIS)

    Algohary, S.

    2007-01-01

    The new and emerging threats to buildings and infrastructure which are faced by todays engineering design and facility management community in Egypt demand new approaches and solutions that are innovative and increasingly based on risk management principles. In the wake of the damage of Taba hotel in south Sinai (2004) and Sharm El-Sheik hotels in Egypt (July, 2005), there was a growing awareness of public vulnerability to terrorist attacks. This awareness leads to increase the expectations form and responsibilities of the architects, engineers and construction professionals This study reviews and assesses different types of threats to nuclear and important buildings. It identifies also the architectural design, vulnerability and risk management that can enhance security. It also introduces a new approach for integration of architectural design and security in nuclear and important buildings in Egypt. The results shows that escalating threats and risks to important buildings and infrastructures change the role of planners, architects, engineers and builders by increasing the focus on the importance of applying viable security principles to the building designs. Architects in Egypt can assume an important role in improving the life-safety features of important buildings by increasing and integrating new security principles and approaches to improve the security and performance of the buildings against man made disasters

  12. Functional integral representation of the nuclear many-body grand partition function

    International Nuclear Information System (INIS)

    Kerman, A.K.; Troudet, T.

    1984-01-01

    A local functional integral formulation of the nuclear many-body problem is proposed which is a generalization of the method previously developed. Its most interesting feature is that it allows an expansion of the many-body evolution operator around any arbitrary mean-field which takes into account the pairing correlations between the nucleons. This is explicitly illustrated for the nuclear many-body grand partition function for which special attention is paid to the static temperature-dependent Hartree-Fock-Bogolyubov (H.F.B.) approximation. Indeed, the temperature-dependent H.F.B. configuration appears to be the optimal choice from a variational point of view among all the possible independent quasi-particle motion approximations. An analytic approximation of the energy level density rho (E,A) is given using explicitly the arbitrariness in the choice of the mean-field and a possible numerical application is proposed. Finally, a new compact formulation of our functional integral that might be useful for future Monte Carlo calculations is proposed

  13. Introducing Knowledge Management into the Integrated Management System of Nuclear Organizations

    International Nuclear Information System (INIS)

    Yanev, Y.; Brandner, A.; Kosilov, A.

    2016-01-01

    Full text: The analysis for introducing knowledge management into an integrated management system in nuclear organizations, conducted by NKMI, and discussed in a number of meetings in IAEA and other organizations has shown that currently there is no full and comprehensive implementation of KM in IMS. NKMI has suggested and developed a common, systematic approach for introducing Knowledge Management in the IMS of a nuclear regulatory organization, based on the concept of competence, graded approach and continuous improvement. The approach is based on the concept of integrating an initial review of all knowledge and competence needed for effective and efficient process implementation including a gap analysis and provision of compensatory measures. Knowledge resources are represented as a knowledge resource matrix, which are necessary to complete a given process successfully. The “performance” of the available knowledge resources contribute to an efficient regulatory process is also reviewed at the end of process implementation where relevant decision for enhancement of knowledge and competence are taken, including capturing, preserving, sharing and reuse of new knowledge, gained through the process implementation. The “knowledge resource matrix” approach is fully based on IAEA recommendation and has already been applied in a number of regulatory processes. (author

  14. Integrated program management for major nuclear decommissioning and environmental remediation projects - 59068

    International Nuclear Information System (INIS)

    Lehew, John

    2012-01-01

    Document available in abstract form only. Full text of publication follows: CH2M HILL Plateau Remediation Company (CH2M HILL) is the U.S. Department of Energy's (DOE) contractor responsible for the safe, environmental cleanup of the Hanford Sites Central Plateau, sections of the Columbia River Corridor and the Hanford Reach National Monument. The 586-square-mile Hanford Site is located along the Columbia River in southeastern Washington, U.S.A. A plutonium production complex, housing the largest volume of radioactive and contaminated waste in the nation, with nine nuclear reactors and associated processing facilities, Hanford played a pivotal role in the nation's defense for more than 40 years, beginning in the 1940's with the Manhattan Project. Today, under the direction of the DOE, Hanford is engaged in one of the world's largest environmental cleanup project. The Plateau Remediation Contract is a 10-year project paving the way for closure of the Hanford Site. The site through its location, climate, geology and proximity to the Columbia River in combination with the results of past nuclear operations presents a highly complex environmental remediation challenge. The complexity is not only due to the technical issues associated with decommissioning nuclear facilities, remediating soil contamination sites, dispositioning legacy waste and fuel materials and integrating these with the deep vadose zone and groundwater remediation

  15. Path-integral isomorphic Hamiltonian for including nuclear quantum effects in non-adiabatic dynamics

    Science.gov (United States)

    Tao, Xuecheng; Shushkov, Philip; Miller, Thomas F.

    2018-03-01

    We describe a path-integral approach for including nuclear quantum effects in non-adiabatic chemical dynamics simulations. For a general physical system with multiple electronic energy levels, a corresponding isomorphic Hamiltonian is introduced such that Boltzmann sampling of the isomorphic Hamiltonian with classical nuclear degrees of freedom yields the exact quantum Boltzmann distribution for the original physical system. In the limit of a single electronic energy level, the isomorphic Hamiltonian reduces to the familiar cases of either ring polymer molecular dynamics (RPMD) or centroid molecular dynamics Hamiltonians, depending on the implementation. An advantage of the isomorphic Hamiltonian is that it can easily be combined with existing mixed quantum-classical dynamics methods, such as surface hopping or Ehrenfest dynamics, to enable the simulation of electronically non-adiabatic processes with nuclear quantum effects. We present numerical applications of the isomorphic Hamiltonian to model two- and three-level systems, with encouraging results that include improvement upon a previously reported combination of RPMD with surface hopping in the deep-tunneling regime.

  16. Integration of safety culture in transient analyses for nuclear power plants

    International Nuclear Information System (INIS)

    Stosic, Zoran V.; Stoll, Uwe

    2009-01-01

    In the nuclear field Safety Culture is the arrangement of attitudes and characteristics in individuals and organisations which determines first and foremost that nuclear power plant safety issues receive adequate attention due to their outstanding significance. It differs from general Corporate Culture via its concept of core hazards and the potentially large effects associated with the release of radioactivity. One can talk about positive and negative Safety Cultures. A positive Safety Culture assumes that the whole is more than the sum of the parts. The different parts interact to increase the overall effectiveness. In a negative Safety Culture the opposite is the case, with the action of some individuals restricted by the cynicism of others. Some examples of issues that contribute to a negative safety culture are: non-adherence to the established instructions and procedures, unclear definition of responsibilities, disinterest and inattentiveness, overestimation of own capabilities and arrogance, unclear rules, and mistrust between involved organisations. In addition to differentiation and importance of Safety Culture, necessary commitment levels, safety management framework, the paper discusses integration of Safety Culture in transient analyses of nuclear power plants. In this course the commitment to Safety Culture is defined as: a good Safety Culture depends on the continuous commitment and fulfilment of all involved organizations, persons and processes without any exception. (author)

  17. Hadronization of quark-diquark model for nucleon structure and nuclear force by path integral

    International Nuclear Information System (INIS)

    Nagata, Keitaro

    2003-01-01

    One of the central issues of the hadron physics is how to interpret the properties and the origin of nuclear force. Nuclear force is in principle the manifestation of dynamics of quarks and gluons but no trial has been successful yet in describing the nuclear force by using QCD, the fundamental theory of the strong interactions. Phenomenon related to the chiral symmetry and the spontaneous breaking of the chiral symmetry is one of the important phenomena for the understanding of hadron physics. Nambu-Jona-Lasinio (NJL) model is one of the quark system models to explain the phenomena concerning the chiral symmetry. Although the method to deduce the Lagrangian describing mesons by applying the path integral to NJL model has been well known as the bosonization, it has been difficult to extend it to baryons because baryons are three-body system. In this paper, a method is reported to deduce Lagrangian which describes baryon-meson from quark-diquark Lagrangian by assuming that baryons are the bound states of quark and diquark. (S. Funahashi)

  18. Basic data, computer codes and integral experiments: The tools for modelling in nuclear technology

    International Nuclear Information System (INIS)

    Sartori, E.

    2001-01-01

    When studying applications in nuclear technology we need to understand and be able to predict the behavior of systems manufactured by human enterprise. First, the underlying basic physical and chemical phenomena need to be understood. We have then to predict the results from the interplay of the large number of the different basic events: i.e. the macroscopic effects. In order to be able to build confidence in our modelling capability, we need then to compare these results against measurements carried out on such systems. The different levels of modelling require the solution of different types of equations using different type of parameters. The tools required for carrying out a complete validated analysis are: - The basic nuclear or chemical data; - The computer codes, and; - The integral experiments. This article describes the role each component plays in a computational scheme designed for modelling purposes. It describes also which tools have been developed and are internationally available. The role of the OECD/NEA Data Bank, the Radiation Shielding Information Computational Center (RSICC), and the IAEA Nuclear Data Section are playing in making these elements available to the community of scientists and engineers is described. (author)

  19. Open-Source Integrated Design-Analysis Environment For Nuclear Energy Advanced Modeling & Simulation Final Scientific/Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    O' Leary, Patrick [Kitware, Inc., Clifton Park, NY (United States)

    2017-01-30

    The framework created through the Open-Source Integrated Design-Analysis Environment (IDAE) for Nuclear Energy Advanced Modeling & Simulation grant has simplify and democratize advanced modeling and simulation in the nuclear energy industry that works on a range of nuclear engineering applications. It leverages millions of investment dollars from the Department of Energy's Office of Nuclear Energy for modeling and simulation of light water reactors and the Office of Nuclear Energy's research and development. The IDEA framework enhanced Kitware’s Computational Model Builder (CMB) while leveraging existing open-source toolkits and creating a graphical end-to-end umbrella guiding end-users and developers through the nuclear energy advanced modeling and simulation lifecycle. In addition, the work deliver strategic advancements in meshing and visualization for ensembles.

  20. Design of integrated passive safety system (IPSS) for ultimate passive safety of nuclear power plants

    International Nuclear Information System (INIS)

    Chang, Soon Heung; Kim, Sang Ho; Choi, Jae Young

    2013-01-01

    Highlights: • We newly propose the design concept of integrated passive safety system (IPSS). • It has five safety functions for decay heat removal and severe accident mitigation. • Simulations for IPSS show that core melt does not occur in accidents with SBO. • IPSS can achieve the passive in-vessel retention and ex-vessel cooling strategy. • The applicability of IPSS is high due to the installation outside the containment. -- Abstract: The design concept of integrated passive safety system (IPSS) which can perform various passive safety functions is proposed in this paper. It has the various functions of passive decay heat removal system, passive safety injection system, passive containment cooling system, passive in-vessel retention and cavity flooding system, and filtered venting system with containment pressure control. The objectives of this paper are to propose the conceptual design of an IPSS and to estimate the design characters of the IPSS with accident simulations using MARS code. Some functions of the IPSS are newly proposed and the other functions are reviewed with the integration of the functions. Consequently, all of the functions are modified and integrated for simplicity of the design in preparation for beyond design based accidents (BDBAs) focused on a station black out (SBO). The simulation results with the IPSS show that the decay heat can be sufficiently removed in accidents that occur with a SBO. Also, the molten core can be retained in a vessel via the passive in-vessel retention strategy of the IPSS. The actual application potential of the IPSS is high, as numerous strong design characters are evaluated. The installation of the IPSS into the original design of a nuclear power plant requires minimal design change using the current penetrations of the containment. The functions are integrated in one or two large tanks outside the containment. Furthermore, the operation time of the IPSS can be increased by refilling coolant from the

  1. NST and NST integration: nuclear science and technique and nano science and technique

    International Nuclear Information System (INIS)

    Zhao Yuliang; Chai Zhifang; Liu Yuanfang

    2008-01-01

    Nuclear science is considered as a big science and also the frontier in the 20 th century, it developed many big scientific facilities and many technique platforms (e.g., nuclear reactor, synchrotron radiation, accelerator, etc.) Nuclear Science and Technology (NST) provide us with many unique tools such as neutron beams, electron beams, gamma rays, alpha rays, beta rays, energetic particles, etc. These are efficient and essential probes for studying many technique and scientific issues in the fields of new materials, biological sciences, environmental sciences, life sciences, medical science, etc. Nano Science and Technology (NST) is a newly emerging multidisciplinary science and the frontier in the 21 st century, it is expected to dominate the technological revolution in diverse aspects of our life. It involves diverse fields such as nanomaterials, nanobiological sciences, environmental nanotechnology, nanomedicine, etc. nanotechnology was once considered as a futuristic science with applications several decades in the future and beyond. But, the rapid development of nanotechnology has broken this prediction. For example, diverse types of manufactured nanomaterials or nanostructures have been currently utilized in industrial products, semiconductors, electronics, stain-resistant clothing, ski wax, catalysts, other commodity products such as food, sunscreens, cosmetics, automobile parts, etc., to improve their performance of previous functions, or completely create novel functions. They will also be increasingly utilized in medicines for purposes of clinic therapy, diagnosis, and drug delivery. In the talk, we will discuss the possibility of NST-NST integration: how to apply the unique probes of advanced radiochemical and nuclear techniques in nanoscience and nanotechnology. (authors)

  2. Ethical and social aspects of integral risk assessment in reference to nuclear energy

    International Nuclear Information System (INIS)

    Schwarz, D.

    1991-01-01

    As a rule, the risks connected with the use of nuclear energy are assessed as isolated factors. Sterotypically the economic benefits and residual risks are weighed against one another and assessed differently. Within the framework of an integral understanding of the problem, the significance of nuclear energy should be considered to be of prime priority when it comes to the serious problems which humanity is confronted with, i.e.: - ecological stability, - climatic stability, - keeping peace, - prevention of large-scale epidemics, - conservation of our resources for the generations to come, - making existence fit for human beings. The author comes to the conclusion that the risks which would result from dispensing with nuclear energy world-wide are a millionfold greater than are the risks which would result from extending the use of nuclear energy world-wide, not only as regards the loss of human lives, but also as regards the amount of land which might become uninhabitable long-term. The author advocates employing ethical arguments which are based on ethical goals and are rational, economical and promise to show the best way of fulfilling mutual ehtical goals satisfactorily in an objective way. The author sees problems as regards the distortion of truth and its misuse by cynics, opportunists, etc. Social aspects must be subjected to ethical scrutiny as well. On the whole it is important to overcome deficits in the communication between technically and scientifically oriented people and those who view it as their task to reflect upon the meaning behind the issue at hand (clergymen, journalists, politicians, etc.). (orig./HSCH) [de

  3. Transition from quality assurance to an integrated management system for nuclear organizations

    International Nuclear Information System (INIS)

    Dua, Shami

    2008-01-01

    The integrated performance- based approach to management systems is a business imperative for the nuclear industry to maintain and enhance its share in the energy sector. The compliance approach has served the industry well to protect its employed, neighbourhood and public at large. It is well recognized that industry has to build on this experience and move to the next level. The model described in this paper provides a fairly flexible approach to move towards a more integrated performance based approach to achieve both the compliance and business related goals and objectives. Compliance with quality and safety requirements must remain a key focus for the industry. The model presented provides a practical approach to develop the business and compliance processes and documentation that can be integrated at the job and project execution levels. The product and business performance objectives will be embedded into the system documentation and implementation at all levels by the responsible line units. The model can be easily adapted to meet the requirements of applicable codes and standards and lends itself to obtain ISO and other system and product based certifications. The approach is consistent with the new IAEA direction on the management system requirements as covered in its new series of standards under GS-R-3. As IAEA is planning a number of regional workshops, nuclear organizations planning to transition to the IMS approach should participate and benefit from these workshops. This will further enhance their understanding and application of the IMS concepts and methodologies. IAEA conducted a joint workshop with FORATOM in Vienna, Austria in November 2007 and another is planned in October 2008 jointly with KHNP and PNC in Busan, S.Korea. (author)

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  5. Nuclear Regulatory Commission staff approaches to improving the integration of regulatory guidance documents and prelicensing reviews

    International Nuclear Information System (INIS)

    Johnson, R.L.

    1994-01-01

    The Nuclear Regulatory Commission staff is conducting numerous activities to improve the integration of its regulatory guidance documents (i.e., License Application Review Plan (LARP) and open-quotes Format and Content for the License Application for the High-Level Waste repositoryclose quotes (FCRG)) and pre-license application (LA) reviews. Those activities related to the regulatory guidance documents consist of: (1) developing an hierarchy of example evaluation findings for LARP; (2) identifying LARP review plan interfaces; (3) conducting an integration review of LARP review strategies; (4) correlating LARP to the ongoing technical program; and (5) revising the FCRG. Some of the more important strategies the staff is using to improve the integration of pre-LA reviews with the LA review include: (1) use of the draft LARP to guide the staff's pre-LA reviews; (2) focus detailed pre-LA reviews on key technical uncertainties; (3) identify and track concerns with DOE's program; and (4) use results of pre-LA reviews in LA reviews. The purpose of this paper is to describe these ongoing activities and strategies and discuss some of the new work that is planned to be included in LARP Revision 1 and the final FCRG, which are scheduled to be issued in late 1994. These activities reflect both the importance the staff has placed on integration and the staff's approach to improving integration in these areas. The staff anticipates that the results of these activities, when incorporated in the FCRG, LARP, and pre-LA reviews, will improve its guidance for DOE's ongoing site characterization program and LA annotated outline development

  6. Development of integral type forgings for steam generator of nuclear power plant

    International Nuclear Information System (INIS)

    Suzuki, Komei; Sato, Ikuo; Murai, Etsuo

    1992-01-01

    The use of integral type steel forgings for the construction of pressure vessel enhances the structural integrity of components and makes the fabrication of components and the execution of in-service inspection (ISI) easier than those fabrication from plate and casting materials. Such steel forgings have been realized for steam generator (SG) for nuclear power plant as follows : (1) Forged shell ring : change from welding fabrication of formed plates to forging ; (2) Forged conical shell ring : ditto ; (3) Forged head integral with nozzles (s) : (i) Primary head : change from casting to forging ; (ii) Secondary head : change from welding fabrication of formed plates to forging. These steel forgings have been realized by recent development in manufacturing technologies, such as steel making, forging processes and heat treatment which are vital to the quality of steel forgings. Some examples of recent typical high quality steel forgings developed by the Japan Steel Works, Ltd. (JSW) are introduced, and the main points of the manufacturing technique and the quality attained are also described. (author)

  7. Integral nuclear power reactor with natural coolant circulation. Investigation of passive RHR system

    International Nuclear Information System (INIS)

    Samoilov, O.B.; Kuul, V.S.; Malamud, V.A.; Tarasov, G.I.

    1996-01-01

    The development of a small power (up to 240 MWe) integral PWR for nuclear co-generation power plants has been carried out. The distinctive features of this advanced reactor are: primary circuit arrangement in a single pressure vessel; natural coolant circulation; passive safety systems with self-activated control devices; use of a second (guard) vessel housing the reactor; favourable conditions for the most severe accident management. A passive steam condensing channel has been developed which is activated by the direct action of the primary circuit pressure without an automatic controlling action or manual intervention for emergency cooling of an integral reactor with an in-built pressurizer. In an emergency situation as pressure rises in the reactor a self-activated device blows out non-condensable gases from the condenser tube bundle and returns them in the steam-condensing mode of the operation with the returing primary coolant condensate into the reactor. The thermo-physical test facility is constructed and the experimental development of the steam-condensing channels is performed aiming at the verification of mathematical models for these channels operation in integral reactors both at loss-of-heat removal and LOCA accidents. (orig.)

  8. The recent activities of nuclear power globalization. Our provision against global warming by global deployment of our own technologies as integrated nuclear power plant supply company'

    International Nuclear Information System (INIS)

    Yamauchi, Kiyoshi; Suzuki, Shigemitsu

    2008-01-01

    Mitsubishi Heavy Industries, Ltd. (MHI) is striving to expand and spread nuclear power plants as an 'Integrated Nuclear Power Plant Supply Company' based on its engineering, manufacturing, and technological support capabilities. The company also has ample experience in the export of major components. MHI is accelerating its global deployment through the market introduction of large-sized strategic reactor US-APWR, the joint development of a mid-sized strategic reactor ATMEA1 with AREVA, and a small strategic reactor PBMR. The company also plans to internationally deploy technologies for the nuclear fuel cycle. We present here the leading-edge trends in the global deployment of these nuclear businesses, all of which help to solve the energy and environmental issues in the world. (author)

  9. Nuclear importation, exportation and production within the framework of the law of the communities or zones of integration

    International Nuclear Information System (INIS)

    Bertone, L.

    1986-01-01

    The article starts from the hypothesis that a harmonisation of regulations concerning the international commerce of nuclear technology would be more useful, if in a first period it is managed on the level of communities (Euratom) or integration zones (ALADI). European and South-American regulations as well as certain aspects of the North-South-cooperation are presented. As yet, a universal cooperation in the field of nuclear material is refused. (CW) [de

  10. Making vasectomy attractive.

    Science.gov (United States)

    Herndon, N

    1992-08-01

    In 1989, Pro-Pater, a private, nonprofit family planning organization in Brazil, used attractive ads with the message Vasectomy, An Act of Love to promote vasectomy. The number of vasectomies performed/day at Pro-Pater clinics increased from 11 to 20 during the publicity campaign and fell after the ads stopped but continued at higher levels. Word of mouth communication among friends, neighbors, and relatives who had vasectomies maintained these high levels. This type of communication reduced the fear that often involves vasectomies because men hear from men they know and trust that vasectomies are harmless and do not deprive them of potency. In Sao Paulo, the percentage of men familiar with vasectomies and how they are performed increased after the campaign, but in Salvador, knowledge did not increase even though the number of vasectomies in Pro-Pater clinics increased. Organizations in Colombia and Guatemala have also been effective in educating men about vasectomies. These successes were especially relevant in Latin American where machismo has been an obstacle of family planning programs. The no-scalpel technique 1st introduced in China in 1974 reduces the fear of vasectomy and has fewer complications than the conventional technique. Further trained physicians can perform the no-scalpel technique in about 10 minutes compared with 15 minutes for the conventional technique. In 1987 during a 1-day festival in Thailand, physicians averaged 57 no-scalpel vasectomies/day compared with only 33 for conventional vasectomies. This technique has not spread to Guatemala, Brazil, Colombia, the US, and some countries in Asia and Africa. Extensive research does not indicate that vasectomy has an increased risk of testicular cancer, prostate cancer, and myocardial infarction. Physicians are working on ways to improve vasectomy.

  11. Integrated Cost and Schedule Control Systems for Nuclear Power Plant Construction: Leveraging Strategic Advantages to Owners and EPC Firms

    Directory of Open Access Journals (Sweden)

    Youngsoo Jung

    2015-01-01

    Full Text Available As the owners expect that the cost and time for nuclear power plant construction would decrease with new entrants into the market, there will be severer competition in the nuclear industry. In order to achieve performance improvement and to attain competitive advantages under the globalized competition, practitioners and researchers in the nuclear industry have recently exerted efforts to develop an advanced and efficient management methodology for the nuclear mega-projects. Among several candidates, integrated cost and schedule control system is of great concern because it can effectively manage the three most important project performances including cost, time, and quality. In this context, the purpose of this paper is to develop a project numbering system (PNS of integrated cost and schedule control system for nuclear power plant construction. Distinct attributes of nuclear power plant construction were investigated first in order to identify influencing variables that characterize real-world implementation of advanced cost and schedule controls. A scenario was then developed and analysed to simulate a case-project. By using this case-project, proposed management requirements, management methods, measurement techniques, data structure, and data collection methods for integrated cost and schedule PNS were illustrated. Finally, findings and implications are outlined, and recommendations for further research are presented.

  12. Effects of integrated designs of alarm and process information on diagnosis performance in digital nuclear power plants.

    Science.gov (United States)

    Wu, Xiaojun; She, Manrong; Li, Zhizhong; Song, Fei; Sang, Wei

    2017-12-01

    In the main control rooms of nuclear power plants (NPPs), operators frequently switch between alarm displays and system-information displays to incorporate information from different screens. In this study, we investigated two integrated designs of alarm and process information - integrating alarm information into process displays (denoted as Alarm2Process integration) and integrating process information into alarm displays (denoted as Process2Alarm integration). To analyse the effects of the two integration approaches and time pressure on the diagnosis performance, a laboratory experiment was conducted with ninety-six students. The results show that compared with the non-integrated case, Process2Alarm integration yields better diagnosis performance in terms of diagnosis accuracy, time required to generate correct hypothesis and completion time. In contrast, the Alarm2Process integration leads to higher levels of workload, with no improvement in diagnosis performance. The diagnosis performance of Process2Alarm integration was consistently better than that of Alarm2Process integration, regardless of the levels of time pressure. Practitioner Summary: To facilitate operator's synthesis of NPP information when performing diagnosis tasks, we proposed to integrate process information into alarm displays. The laboratory validation shows that the integration approach significantly improves the diagnosis performance for both low and high time-pressure levels.

  13. A Development Framework for Software Security in Nuclear Safety Systems: Integrating Secure Development and System Security Activities

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jaekwan; Suh, Yongsuk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-02-15

    The protection of nuclear safety software is essential in that a failure can result in significant economic loss and physical damage to the public. However, software security has often been ignored in nuclear safety software development. To enforce security considerations, nuclear regulator commission recently issued and revised the security regulations for nuclear computer-based systems. It is a great challenge for nuclear developers to comply with the security requirements. However, there is still no clear software development process regarding security activities. This paper proposes an integrated development process suitable for the secure development requirements and system security requirements described by various regulatory bodies. It provides a three-stage framework with eight security activities as the software development process. Detailed descriptions are useful for software developers and licensees to understand the regulatory requirements and to establish a detailed activity plan for software design and engineering.

  14. Application of integrated computer-aided engineering for design, construction and operation of nuclear power plant: practice and prospects

    International Nuclear Information System (INIS)

    Min, K.S.; Lee, B.H.

    1988-01-01

    Computer-aided-engineering (CAE) is an essential tool for modern nuclear power plant engineering. It greatly varies in definition, application, and technology from project to project and company to company. Despite the fast growing technologies and applications of CAE, its complexity and variety have thrown another puzzle to management of a nuclear project. Without due consideration of an integrated CAE system in early planning stage, the overall efficiency of a nuclear project would slow down due to the inefficiency in data flow. In this application are discussed under the Korea Power engineering Company philosophy in CAE approach

  15. RATU2 - The Finnish research programme on the structural integrity of nuclear power plants. Synthesis of achievements 1995-1998

    International Nuclear Information System (INIS)

    Solin, J.; Sarkimo, M.; Asikainen, M.; Aavall, Aa.

    1998-01-01

    The symposium summarises the scientific and technical achievements within the Finnish Research programme on the structural integrity of nuclear power plants (RATU2). The programme began in 1995 and will be accomplished at the end of 1998. The annual volume of this programme represented approximately 6 % of the total nuclear energy R and D in Finland. The research programme was mainly publicly funded and supplied impartial expertise for the regulation of nuclear energy. It also played an important role in the education of new experts, technology transfer and the international exchange of scientific results. (orig.)

  16. Self-pressurization analysis of the natural circulation integral nuclear reactor using a new dynamic model

    Directory of Open Access Journals (Sweden)

    Ali Farsoon Pilehvar

    2018-06-01

    Full Text Available Self-pressurization analysis of the natural circulation integral nuclear reactor through a new dynamic model is studied. Unlike conventional pressurized water reactors, this reactor type controls the system pressure using saturated coolant water in the steam dome at the top of the pressure vessel. Self-pressurization model is developed based on conservation of mass, volume, and energy by predicting the condensation that occurs in the steam dome and the flashing inside the chimney using the partial differential equation. A simple but functional model is adopted for the steam generator. The obtained results indicate that the variable measurement is consistent with design data and that this new model is able to predict the dynamics of the reactor in different situations. It is revealed that flashing and condensation power are in direct relation with the stability of the system pressure, without which pressure convergence cannot be established. Keywords: Condensation Power, Flashing Phenomenon, Natural Circulation, Self-Pressurization, Small Modular Reactor

  17. Integration of error tolerance into the design of control rooms of nuclear power plants

    International Nuclear Information System (INIS)

    Sepanloo, Kamran

    1998-08-01

    Many complex technological systems' failures have been attributed to human errors. Today, based on extensive research on the role of human element in technological systems it is known that human error can not totally be eliminated in modern, flexible, or changing work environments by conventional style design strategies(e.g. defence in depth), or better instructions nor should they be. Instead, the operators' ability to explore degrees of freedom should be supported and means for recovering from the effects of errors should be included. This calls for innovative error tolerant design of technological systems. Integration of error tolerant concept into the design, construction, startup, and operation of nuclear power plants provides an effective means of reducing human error occurrence during all stages of life of it and therefore leads to considerable enhancement of plant's safety

  18. Application of high efficiency and reliable 3D-designed integral shrouded blades to nuclear turbines

    International Nuclear Information System (INIS)

    Watanabe, Eiichiro; Ohyama, Hiroharu; Tashiro, Hikaru; Sugitani, Toshiro; Kurosawa, Masaru

    1998-01-01

    Mitsubishi Heavy Industries, Ltd. has recently developed new blades for nuclear turbines, in order to achieve higher efficiency and higher reliability. The 3D aerodynamic design for 41 inch and 46 inch blades, their one piece structural design (integral-shrouded blades: ISB), and the verification test results using a model steam turbine are described in this paper. The predicted efficiency and lower vibratory stress have been verified. Based on these 60Hz ISB, 50Hz ISB series are under development using 'the law of similarity' without changing their thermodynamic performance and mechanical stress levels. Our 3D-designed reaction blades which are used for the high pressure and low pressure upstream stages, are also briefly mentioned. (author)

  19. An integrated software testing framework for FGA-based controllers in nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Jae Yeob; Kim, Eun Sub; Yoo, Jun Beom; Lee, Young Jun; Choi, Jong Gyun

    2016-01-01

    Field-programmable gate arrays (FPGAs) have received much attention from the nuclear industry as an alternative platform to programmable logic controllers for digital instrumentation and control. The software aspect of FPGA development consists of several steps of synthesis and refinement, and also requires verification activities, such as simulations that are performed individually at each step. This study proposed an integrated software-testing framework for simulating all artifacts of the FPGA software development simultaneously and evaluating whether all artifacts work correctly using common oracle programs. This method also generates a massive number of meaningful simulation scenarios that reflect reactor shutdown logics. The experiment, which was performed on two FPGA software implementations, showed that it can dramatically save both time and costs

  20. CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC

    International Nuclear Information System (INIS)

    Wu, Y.; Song, J.; Zheng, H.; Sun, G.; Hao, L.; Long, P.; Hu, L.

    2013-01-01

    SuperMC is a (Computer-Aided-Design) CAD-based Monte Carlo (MC) program for integrated simulation of nuclear systems developed by FDS Team (China), making use of hybrid MC-deterministic method and advanced computer technologies. The design aim, architecture and main methodology of SuperMC are presented in this paper. The taking into account of multi-physics processes and the use of advanced computer technologies such as automatic geometry modeling, intelligent data analysis and visualization, high performance parallel computing and cloud computing, contribute to the efficiency of the code. SuperMC2.1, the latest version of the code for neutron, photon and coupled neutron and photon transport calculation, has been developed and validated by using a series of benchmarking cases such as the fusion reactor ITER model and the fast reactor BN-600 model

  1. An integrated framework for effective reduction of occupational radiation exposure in a nuclear power plant

    International Nuclear Information System (INIS)

    Joo, Hyun Moon; Hak, Soo Kim; Young, Ho Cho; Chang, Sun Kang

    1998-01-01

    For effective reduction of occupational radiation exposure in a nuclear power plant, it is necessary to identify repetitive high radiation jobs during maintenance and refueling operation and comprehensively assess them. An integrated framework for effective reduction of occupational radiation exposure is proposed in this study. The framework consists of three parts; data collection, statistical analysis, and ALARA findings. A PC-based database program, INSTORE, is used for data collection and reduction, and the Rank Sum Method is used in identifying high radiation jobs. As a case study, the data accumulated in Kori Units 3 and 4 have been analyzed. The results of this study show that the radiation job classifications of SG related work have much effect on annual ORE collective dose in Kori Units 3 and 4. As an example of ALARA findings, hence, the improvements for the radiation job classifications of SG related work are summarized

  2. An integrity evaluation method of the pressure vessel of nuclear reactors under pressurized thermal shock

    International Nuclear Information System (INIS)

    Matsubara, Masaaki; Okamura, Hiroyuki.

    1987-01-01

    Present paper proposes a new algorithm of the integrity evaluation of the pressure vessel of nuclear reactors under pressurized thermal shock, PTS. This method enables us to do an effective evaluation by superimposing proposed ''PTS state-transient curves'' and ''toughness transient curves'', and is superior to a conventional one in the following points; (1) easy to get an overall view of the result of PTS event for the variations of several parameters, (2) possible to evaluate a safety margin for irradiation embrittlement, and (3) enable to construct an Expert-friendly evaluation system. In addition, the paper shows that we can execute a safety assurance test by using a flat plate model with the same thickness as that of real plant. (author)

  3. Reactor pressure vessel structural integrity research in the US Nuclear Regulatory Commission HSST and HSSI Programs

    International Nuclear Information System (INIS)

    Pennell, W.E.; Corwin, W.R.

    1994-01-01

    This report discusses development on the technology used to assess the safety of irradiation-embrittled nuclear reactor pressure vessels containing flaws. Fracture mechanics tests on reactor pressure vessel steel have shown that local brittle zones do not significantly degrade the material fracture toughness, constraint relaxation at the crack tip of shallow surface flaws results in increased fracture toughness, and biaxial loading reduces but does not eliminate the shallow-flaw fracture toughness elevation. Experimental irradiation investigations have shown that the irradiation-induced shift in Charpy V-notch versus temperature behavior may not be adequate to conservatively assess fracture toughness shifts due to embrittlement and the wide global variations of initial chemistry and fracture properties of a nominally uniform material within a pressure vessel may confound accurate integrity assessments that require baseline properties

  4. Beyond initial attraction: physical attractiveness in newlywed marriage.

    Science.gov (United States)

    McNulty, James K; Neff, Lisa A; Karney, Benjamin R

    2008-02-01

    Physical appearance plays a crucial role in shaping new relationships, but does it continue to affect established relationships, such as marriage? In the current study, the authors examined how observer ratings of each spouse's facial attractiveness and the difference between those ratings were associated with (a) observations of social support behavior and (b) reports of marital satisfaction. In contrast to the robust and almost universally positive effects of levels of attractiveness on new relationships, the only association between levels of attractiveness and the outcomes of these marriages was that attractive husbands were less satisfied. Further, in contrast to the importance of matched attractiveness to new relationships, similarity in attractiveness was unrelated to spouses' satisfaction and behavior. Instead, the relative difference between partners' levels of attractiveness appeared to be most important in predicting marital behavior, such that both spouses behaved more positively in relationships in which wives were more attractive than their husbands, but they behaved more negatively in relationships in which husbands were more attractive than their wives. These results highlight the importance of dyadic examinations of the effects of spouses' qualities on their marriages.

  5. Judging attractiveness: Biases due to raters’ own attractiveness and intelligence

    Directory of Open Access Journals (Sweden)

    Stacy Yen-Lin Sim

    2015-12-01

    Full Text Available Tennis and Dabbs (1975 reported that physically attractive males showed a positivity bias when rating the attractiveness of others. The opposite pattern was observed for females. We attempted to replicate and extend these findings by: (1 using self-assessed attractiveness rather than the experimentally derived attractiveness measure used in previous research, (2 using face-to-face interactions with targets as opposed to using photographs, and (3 examining the effect of another ego-involving attribute: intelligence. Consistent with previous research, attractiveness judgments made by men, but not women, correlated positively with their own self-perceived level of attractiveness (r = .51, p < .001. Attractiveness judgments made by women, but not men, correlated negatively with their intelligence (r = −.32, p = .001. Judgments of attractiveness are thus biased by a rater’s own attributes (e.g. attractiveness and intelligence, but these effects are not generalizable across men and women raters, and may be driven by different mechanisms.

  6. Integration of the advanced transparency framework to advanced nuclear systems : enhancing Safety, Operations, Security and Safeguards (SOSS)

    International Nuclear Information System (INIS)

    Mendez, Carmen Margarita; Rochau, Gary Eugene; Cleary, Virginia D.

    2008-01-01

    The advent of the nuclear renaissance gives rise to a concern for the effective design of nuclear fuel cycle systems that are safe, secure, nonproliferating and cost-effective. We propose to integrate the monitoring of the four major factors of nuclear facilities by focusing on the interactions between Safeguards, Operations, Security, and Safety (SOSS). We proposed to develop a framework that monitors process information continuously and can demonstrate the ability to enhance safety, operations, security, and safeguards by measuring and reducing relevant SOSS risks, thus ensuring the safe and legitimate use of the nuclear fuel cycle facility. A real-time comparison between expected and observed operations provides the foundation for the calculation of SOSS risk. The automation of new nuclear facilities requiring minimal manual operation provides an opportunity to utilize the abundance of process information for monitoring SOSS risk. A framework that monitors process information continuously can lead to greater transparency of nuclear fuel cycle activities and can demonstrate the ability to enhance the safety, operations, security and safeguards associated with the functioning of the nuclear fuel cycle facility. Sandia National Laboratories (SNL) has developed a risk algorithm for safeguards and is in the process of demonstrating the ability to monitor operational signals in real-time though a cooperative research project with the Japan Atomic Energy Agency (JAEA). The risk algorithms for safety, operations and security are under development. The next stage of this work will be to integrate the four algorithms into a single framework

  7. Perturbed path integrals in imaginary time: Efficiently modeling nuclear quantum effects in molecules and materials

    Science.gov (United States)

    Poltavsky, Igor; DiStasio, Robert A.; Tkatchenko, Alexandre

    2018-03-01

    Nuclear quantum effects (NQE), which include both zero-point motion and tunneling, exhibit quite an impressive range of influence over the equilibrium and dynamical properties of molecules and materials. In this work, we extend our recently proposed perturbed path-integral (PPI) approach for modeling NQE in molecular systems [I. Poltavsky and A. Tkatchenko, Chem. Sci. 7, 1368 (2016)], which successfully combines the advantages of thermodynamic perturbation theory with path-integral molecular dynamics (PIMD), in a number of important directions. First, we demonstrate the accuracy, performance, and general applicability of the PPI approach to both molecules and extended (condensed-phase) materials. Second, we derive a series of estimators within the PPI approach to enable calculations of structural properties such as radial distribution functions (RDFs) that exhibit rapid convergence with respect to the number of beads in the PIMD simulation. Finally, we introduce an effective nuclear temperature formalism within the framework of the PPI approach and demonstrate that such effective temperatures can be an extremely useful tool in quantitatively estimating the "quantumness" associated with different degrees of freedom in the system as well as providing a reliable quantitative assessment of the convergence of PIMD simulations. Since the PPI approach only requires the use of standard second-order imaginary-time PIMD simulations, these developments enable one to include a treatment of NQE in equilibrium thermodynamic properties (such as energies, heat capacities, and RDFs) with the accuracy of higher-order methods but at a fraction of the computational cost, thereby enabling first-principles modeling that simultaneously accounts for the quantum mechanical nature of both electrons and nuclei in large-scale molecules and materials.

  8. ABNT NBR ISO 26000 priorities to integrate the social responsibilities in peaceful use of nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Biazini Filho, Francisco L.; Sordi, Gian-Maria, E-mail: gian@atomo.com.br, E-mail: Francisco.biazini@usp.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    The aim of this paper is to indicate the priorities in the themes and issues to integrate the social responsibilities (SR) in of the peaceful use of nuclear energy. The ABNT NBR ISO 26000 - Guidance on Social Responsibility{sub (1)}. Social responsibility should be an integral part of core organizational strategy, with assigned responsibilities and accountability at all appropriate levels of the organization. It should be reflected in decision making and considered in implementing activities. The process suggested is: 1 - determining relevance; 2 - determining significance and 3 - establishing priorities for addressing issues. The relevancies of each issue are established for us, in this paper, from the activities of the peaceful use of nuclear energy. For each relevant issue the priority are established and are: Core subject : The environment 6.5: Issue 1 : Prevention of pollution 6.5.3: Offers guidances to recognized authority sources on how to measure, assess, prevent or control the most common forms of pollution, including emissions to air, discharge waters, toxic products, waste management, biological agents, odors, visual pollution, among others. Core subject : The environment 6.5: Issue 2 : Sustainable resource use 6.5.4: Presents a series of actions aimed at the more smart use of resources, including energy efficiency, conservation, access and use of water, and extracting the most efficiency in the use of materials, renewable or not, reusing or recycling these resources whenever possible. Core subject : Community involvement and development 6.8: Issue 6 : Health 6.8.8: The organization must appreciate to eliminate the negative impacts of their activities on people's health, contributing as possible pair increase access to medicines and sanitation, as well as raise awareness about the disease as much as healthy lifestyles. In the next jobs we should consider the following to determine whether an action to address these 3 issues. (author)

  9. ABNT NBR ISO 26000 priorities to integrate the social responsibilities in peaceful use of nuclear energy

    International Nuclear Information System (INIS)

    Biazini Filho, Francisco L.; Sordi, Gian-Maria

    2013-01-01

    The aim of this paper is to indicate the priorities in the themes and issues to integrate the social responsibilities (SR) in of the peaceful use of nuclear energy. The ABNT NBR ISO 26000 - Guidance on Social Responsibility (1) . Social responsibility should be an integral part of core organizational strategy, with assigned responsibilities and accountability at all appropriate levels of the organization. It should be reflected in decision making and considered in implementing activities. The process suggested is: 1 - determining relevance; 2 - determining significance and 3 - establishing priorities for addressing issues. The relevancies of each issue are established for us, in this paper, from the activities of the peaceful use of nuclear energy. For each relevant issue the priority are established and are: Core subject : The environment 6.5: Issue 1 : Prevention of pollution 6.5.3: Offers guidances to recognized authority sources on how to measure, assess, prevent or control the most common forms of pollution, including emissions to air, discharge waters, toxic products, waste management, biological agents, odors, visual pollution, among others. Core subject : The environment 6.5: Issue 2 : Sustainable resource use 6.5.4: Presents a series of actions aimed at the more smart use of resources, including energy efficiency, conservation, access and use of water, and extracting the most efficiency in the use of materials, renewable or not, reusing or recycling these resources whenever possible. Core subject : Community involvement and development 6.8: Issue 6 : Health 6.8.8: The organization must appreciate to eliminate the negative impacts of their activities on people's health, contributing as possible pair increase access to medicines and sanitation, as well as raise awareness about the disease as much as healthy lifestyles. In the next jobs we should consider the following to determine whether an action to address these 3 issues. (author)

  10. Integrity assessment of grouted posttensioning cables and reinforced concrete of a nuclear containment building

    Science.gov (United States)

    Philipose, K.; Shenton, B.

    2011-04-01

    The Containment Buildings of CANDU Nuclear Generating Stations were designed to house nuclear reactors and process equipment and also to provide confinement of releases from a potential nuclear accident such as a Loss Of Coolant Accident (LOCA). To meet this design requirement, a post-tensioning system was designed to induce compressive stresses in the structure to counteract the internal design pressure. The CANDU reactor building at Gentilly-1 (G-1), Quebec, Canada (250 MWe) was built in the early 1970s and is currently in a decommissioned state. The structure at present is under surveillance and monitoring. In the year 2000, a field investigation was conducted as part of a condition assessment and corrosion was detected in some of the grouted post-tension cable strands. However, no further work was done at that time to determine the cause, nature, impact and extent of the corrosion. An investigation of the Gentilly-1 containment building is currently underway to assess the condition of grouted post-tensioning cables and reinforced concrete. At two selected locations, concrete and steel reinforcements were removed from the containment building wall to expose horizontal cables. Individual cable strands and reinforcement bars were instrumented and measurements were taken in-situ before removing them for forensic examination and destructive testing to determine the impact of ageing and corrosion. Concrete samples were also removed and tested in a laboratory. The purpose of the field investigation and laboratory testing, using this structure as a test bed, was also to collect material ageing data and to develop potential Nondestructive Examination (NDE) methods to monitor Containment Building Integrity. The paper describes the field work conducted and the test results obtained for concrete, reinforcement and post-tensioning cables.

  11. Integrity assessment of grouted posttensioning cables and reinforced concrete of a nuclear containment building

    Directory of Open Access Journals (Sweden)

    Shenton B.

    2011-04-01

    Full Text Available The Containment Buildings of CANDU Nuclear Generating Stations were designed to house nuclear reactors and process equipment and also to provide confinement of releases from a potential nuclear accident such as a Loss Of Coolant Accident (LOCA. To meet this design requirement, a post-tensioning system was designed to induce compressive stresses in the structure to counteract the internal design pressure. The CANDU reactor building at Gentilly-1 (G-1, Quebec, Canada (250 MWe was built in the early 1970s and is currently in a decommissioned state. The structure at present is under surveillance and monitoring. In the year 2000, a field investigation was conducted as part of a condition assessment and corrosion was detected in some of the grouted post-tension cable strands. However, no further work was done at that time to determine the cause, nature, impact and extent of the corrosion. An investigation of the Gentilly-1 containment building is currently underway to assess the condition of grouted post-tensioning cables and reinforced concrete. At two selected locations, concrete and steel reinforcements were removed from the containment building wall to expose horizontal cables. Individual cable strands and reinforcement bars were instrumented and measurements were taken in-situ before removing them for forensic examination and destructive testing to determine the impact of ageing and corrosion. Concrete samples were also removed and tested in a laboratory. The purpose of the field investigation and laboratory testing, using this structure as a test bed, was also to collect material ageing data and to develop potential Nondestructive Examination (NDE methods to monitor Containment Building Integrity. The paper describes the field work conducted and the test results obtained for concrete, reinforcement and post-tensioning cables.

  12. Design of proportional-integral-derivative type optimal controller for a nuclear reactor

    International Nuclear Information System (INIS)

    Pal, Jayanta

    1976-01-01

    A theoretic approach to the design of a proportional integral derivative (PID) type optimal controller for a nuclear reactor is considered. A linearized version of the state-space model of a nuclear-reactor-plant is investigated which shows very 'sluggish' response (settling time of the order of 600 seconds) to changes in the power demand and frequency. It is shown that with a judicious choice of state variables a PID type optimal controller realisation is possible. A controller is designed to minimise the effects of (a) a sudden increase or decrease in the electrical power demand (b) change in frequency at grid. The above controller, designed for a tracking problem, reduces the steady-state error (in response to a step input) to zero and the dynamics of the system become 'faster' (setting time of the order of 100 seconds). The controller is also insensitive to changes in system parameters. The superiority in the performance of the system with the optimal PID controller as compared with that of the conventional regulator is conclusively established. (author)

  13. Strategy for establishing integrated l and c reliability of operating nuclear power plants in korea

    International Nuclear Information System (INIS)

    Kang, H. T.; Chung, H. Y.; Lee, Y. H.

    2008-01-01

    Korea hydro and nuclear power co. (KHNP) are in progress of developing a integrated I and C reliability establishing strategy for managing l and C obsolescence and phasing in new technology that both meets the needs of the fleet and captures the benefits of applying proven solutions to multiple plants, with reduced incremental costs. In view of this, we are developing I and C component management which covers major failure mode, symptom of performance degradation, condition-based or time-based preventive management (PM), monitoring, and failure finding and correction based on equipment reliability (ER). Furthermore, for the l and C system replacement management, we are in progress of 3-year-long I and C systems upgrade fundamental designing in developing the long-term major l and C systems implementation plan to improve plant operations, eliminate operator challenges, reduce maintenance costs, and cope with the challenges of component obsolescence. For accomplishing I and C digital upgrade in near future, we chose demonstration plant, Younggwang (YGN) unit 3 and 4 which are Korean Standard Nuclear Power Plant (KSNP). In this paper, we established the long term reliability strategy of I and C system based on ER in component replacement and furthermore I and C systems digital upgrade in system replacement. (authors)

  14. Update on impact effects in nuclear plants Part I--overview and need for integrated approach

    International Nuclear Information System (INIS)

    Sliter, G.E.; Ravindra, M.K.

    1984-01-01

    In this paper, an ASCE working group on impact effects in nuclear plants updates the review of this technology contained in a five-yearold ASCE report. In Part I, an overview is given of the impact conditions addressed in nuclear plant design against missiles generated by such postulated extreme events as tornados, turbine failures, pipe ruptures, aircraft crashes, and drops of heavy objects from lifting devices. The conclusion of a brief evaluation of the state of the art in predicting structural response for the various missile impact types is that two of them--pipe whip and heavy object drop--would benefit most by further development of design and analysis methods. Parts II and III of this paper review current practice and identify its limitations for these two impact types. Part I continues with a discussion of the general characteristics of impacts and the structural response they produce and concludes with a recommendation for and brief description of an ''integrated approach'' for treating impact effects. The adoption of this systematic approach in future development of impact technology would guide engineers in the use of the most appropriate and accurate available techniques for designing against a particular impact event

  15. Integrated data base report - 1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1997-12-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are reported as of the end of fiscal year (FY) 1996, which is September 30, 1996. Commercial SNF and commercial uranium mill tailings inventories are reported on an end-of-calendar year (CY) basis. All SNF and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are SNF, high-level waste, transuranic waste, low-level waste, uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through FY 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions

  16. Basic Study of Establishment of Quality Assurance Processes to Develop an Integrated Quality Assurance System for Nuclear Power Plant Construction

    International Nuclear Information System (INIS)

    Lim, Byungki; Moon, Byeongsuk; Lee, Jae Kyoung

    2014-01-01

    An integrated quality assurance system has necessitated carrying out quality assurance programs in a systematic manner because the opportunities to expand business in overseas markets have increased since the export of a nuclear power plant to UAE in 2009. In this study, we use PDCA method to systematically analyze the quality assurance procedures that were used in previous projects for constructing nuclear power plants. We reached a classification system of quality assurance processes at each phase of nuclear power plant construction by integrating similar work related to quality such as planning, design, equipment manufacturing, construction and start-up. We also established a hierarchy of quality assurance processes to develop an integrated quality assurance system as a technology goal to be developed later. To obtain most updated quality assurance activities, a quality assurance process is structured by integrating similar works analyzed from quality assurance procedures through PDCA cycle method. At the implementation phase of Hierarchy of quality processes and sequence of processes for constructing nuclear power plant are established in this study. Integrated quality assurance system is to be developed by connecting organizations as well as stakeholders such as owners, Architect engineering, suppliers, contractors, and sub-contractors to carry out assigned work efficiently

  17. Basic Study of Establishment of Quality Assurance Processes to Develop an Integrated Quality Assurance System for Nuclear Power Plant Construction

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Byungki; Moon, Byeongsuk; Lee, Jae Kyoung [Korea Hydro and Nuclear Power Co. Ltd., Daejeon (Korea, Republic of)

    2014-05-15

    An integrated quality assurance system has necessitated carrying out quality assurance programs in a systematic manner because the opportunities to expand business in overseas markets have increased since the export of a nuclear power plant to UAE in 2009. In this study, we use PDCA method to systematically analyze the quality assurance procedures that were used in previous projects for constructing nuclear power plants. We reached a classification system of quality assurance processes at each phase of nuclear power plant construction by integrating similar work related to quality such as planning, design, equipment manufacturing, construction and start-up. We also established a hierarchy of quality assurance processes to develop an integrated quality assurance system as a technology goal to be developed later. To obtain most updated quality assurance activities, a quality assurance process is structured by integrating similar works analyzed from quality assurance procedures through PDCA cycle method. At the implementation phase of Hierarchy of quality processes and sequence of processes for constructing nuclear power plant are established in this study. Integrated quality assurance system is to be developed by connecting organizations as well as stakeholders such as owners, Architect engineering, suppliers, contractors, and sub-contractors to carry out assigned work efficiently.

  18. Creating beauty: creativity compensates for low physical attractiveness when individuals assess the attractiveness of social and romantic partners.

    Science.gov (United States)

    Watkins, Christopher D

    2017-04-01

    Although creativity is attractive in a potential mate, it is unclear (i) whether the effects of creativity on attractiveness generalize to other social contexts and (ii) whether creativity has equivalent effects on men's and women's attractiveness. As social knowledge of creativity may either enhance or 'offset' the appeal of social partners who differ in physical attractiveness, three repeated measures experiments were conducted to directly address these issues. Here, participants rated a series of face-text pairs for attractiveness on trials that differed in one of four combinations of facial attractiveness (attractive and less attractive) and creativity (creative and less creative), rating story-tellers in two experiments (short interpretations of an identical painting) and creative ideas in a further experiment (alternative uses for an everyday object). Regardless of the sex of the judge, creativity and facial attractiveness had independent effects on men's overall attractiveness (initial experiment) and, in further experiments, more substantial effects on the attractiveness of men with less attractive faces than men with attractive faces (when using a different measure of creativity) and specific effects on the attractiveness of individuals with less attractive faces (when using different face stimuli). Collectively, across three experiments, these findings suggest that creativity may compensate for putative cues to lower biological 'quality' and that the benefits of creativity to social groups more generally enhance attraction to creative men (in two experiments) and creative men and women (one experiment). More broadly, the data suggest that species can integrate knowledge of cognitive intelligence with visual cues to biological 'quality' to facilitate mate and/or ally choice.

  19. Nuclear education in Russia: Status, peculiarities, problems and perspectives

    International Nuclear Information System (INIS)

    Onykiy, B.N.; Kryuchkov, E.F.

    2005-01-01

    The paper is devoted to analysis of Russian nuclear education system: its current status, specific features, difficulties and prospects. Russian higher education system in nuclear engineering has been created simultaneously with the development of nuclear industry, and the system completely satisfied all industrial demands for the specialists of different qualification levels. For the past several decades, nuclear education has lost its attractiveness to young people. The paper discusses the actions to be undertaken for reversing the situation. The paper underlines particularly the special role of international collaboration and all-European integration of nuclear educational programmes for further development of nuclear education all over the world. (author)

  20. Incorporation of Nuclear Knowledge Management to the Integrated System of Quality and Technological Innovation in Cubaenergía

    International Nuclear Information System (INIS)

    Oviedo Rivero, I.; González García, A.; Amado Picasso, M.; Yera López, B.; Contreras, M.; López Núñez, A.; García Rodríguez, B.; Elías Hardy, L. L.; Rivero Blanco, J. M.; Peña Tornet, A.; Quintana Castillo, N.

    2016-01-01

    Full text: Technical knowledge management and innovation become important tools for organizations to meet the needs and expectations of the market and society in general; especially those related to the peaceful use of nuclear energy. Since 2011 Cubaenergia, under the model of the UNE 166002, integrated process management Scientific and Technological Innovation to the requirements of NC-ISO 9001, compliance with national regulations applicable to the sector. In September 2015 the new ISO 9001 includes a clause that makes explicit mention knowledge. Although this clause is not a standard for knowledge management nor does it imply its obligatory; Cubaenergia decided to expand its integrated management system to include the Nuclear Knowledge Management system. In this article the conceptual framework for the integration of these three systems, diagnosis in the organization and the proposed design and implementation plan of management knowledge management integrated analyzes R&D and the quality management system in Cubaenergía. (author

  1. Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lyssakov, V.N.; Kang, K.S.

    2005-01-01

    These guidelines have been developed under an International Atomic Energy Agency (IAEA) Co-ordinated Research Project (CRP) titled ''Surveillance Programme Results Application to Reactor Pressure Vessel Integrity Assessment.'' The IAEA has sponsored a series of five CRPs that have led to a focus on measuring the best irradiation fracture parameters using relatively small test specimens for assuring structural integrity of reactor pressure vessel (RPV) materials in Nuclear Power Plants (NPPs)

  2. Integrated System for Retrieval, Transportation and Consolidated Storage of Used Nuclear Fuel in the US - 13312

    International Nuclear Information System (INIS)

    Bracey, William; Bondre, Jayant; Shelton, Catherine; Edmonds, Robert

    2013-01-01

    The current inventory of used nuclear fuel assemblies (UNFAs) from commercial reactor operations in the United States totals approximately 65,000 metric tons or approximately 232,000 UNFAs primarily stored at the 104 operational reactors in the US and a small number of decommissioned reactors. This inventory is growing at a rate of roughly 2,000 to 2,400 metric tons each year, (Approx. 7,000 UNFAs) as a result of ongoing commercial reactor operations. Assuming an average of 10 metric tons per storage/transportation casks, this inventory of commercial UNFAs represents about 6,500 casks with an additional of about 220 casks every year. In January 2010, the Blue Ribbon Commission (BRC) [1] was directed to conduct a comprehensive review of policies for managing the back end of the nuclear fuel cycle and recommend a new plan. The BRC issued their final recommendations in January 2012. One of the main recommendations is for the United States to proceed promptly to develop one or more consolidated storage facilities (CSF) as part of an integrated, comprehensive plan for safely managing the back end of the nuclear fuel cycle. Based on its extensive experience in storage and transportation cask design, analysis, licensing, fabrication, and operations including transportation logistics, Transnuclear, Inc. (TN), an AREVA Subsidiary within the Logistics Business Unit, is engineering an integrated system that will address the complete process of commercial UNFA management. The system will deal with UNFAs in their current storage mode in various configurations, the preparation including handling and additional packaging where required and transportation of UNFAs to a CSF site, and subsequent storage, operation and maintenance at the CSF with eventual transportation to a future repository or recycling site. It is essential to proceed by steps to ensure that the system will be the most efficient and serve at best its purpose by defining: the problem to be resolved, the criteria to

  3. Integrated System for Retrieval, Transportation and Consolidated Storage of Used Nuclear Fuel in the US - 13312

    Energy Technology Data Exchange (ETDEWEB)

    Bracey, William; Bondre, Jayant; Shelton, Catherine [Transnuclear, Inc., 7135 Minstrel Way Suite 300, Columbia MD 21045 (United States); Edmonds, Robert [AREVA Federal Services, 7207 IBM Drive, Charlotte NC 28262 (United States)

    2013-07-01

    The current inventory of used nuclear fuel assemblies (UNFAs) from commercial reactor operations in the United States totals approximately 65,000 metric tons or approximately 232,000 UNFAs primarily stored at the 104 operational reactors in the US and a small number of decommissioned reactors. This inventory is growing at a rate of roughly 2,000 to 2,400 metric tons each year, (Approx. 7,000 UNFAs) as a result of ongoing commercial reactor operations. Assuming an average of 10 metric tons per storage/transportation casks, this inventory of commercial UNFAs represents about 6,500 casks with an additional of about 220 casks every year. In January 2010, the Blue Ribbon Commission (BRC) [1] was directed to conduct a comprehensive review of policies for managing the back end of the nuclear fuel cycle and recommend a new plan. The BRC issued their final recommendations in January 2012. One of the main recommendations is for the United States to proceed promptly to develop one or more consolidated storage facilities (CSF) as part of an integrated, comprehensive plan for safely managing the back end of the nuclear fuel cycle. Based on its extensive experience in storage and transportation cask design, analysis, licensing, fabrication, and operations including transportation logistics, Transnuclear, Inc. (TN), an AREVA Subsidiary within the Logistics Business Unit, is engineering an integrated system that will address the complete process of commercial UNFA management. The system will deal with UNFAs in their current storage mode in various configurations, the preparation including handling and additional packaging where required and transportation of UNFAs to a CSF site, and subsequent storage, operation and maintenance at the CSF with eventual transportation to a future repository or recycling site. It is essential to proceed by steps to ensure that the system will be the most efficient and serve at best its purpose by defining: the problem to be resolved, the criteria to

  4. Renewable Energy Country Attractiveness Indices

    International Nuclear Information System (INIS)

    2011-02-01

    Since 2003 Ernst and Young team has been releasing quarterly data that ranks national renewable energy markets, and their suitability for individual technologies. The Country Attractiveness Indices now track the relative attractiveness of 30 countries' renewable energy markets across a selection of technologies each quarter. The Renewable Energy Country Attractiveness Indices publication scores and comments on various technologies, including: on-shore wind, off-shore wind, solar PV, solar CSP, biomass, and geothermal.

  5. Identifying Issues in Applying Integrated Project Delivery to Domestic Nuclear Power Plant Construction Projects

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Joo [Korean Nuclear Society, Daejeon (Korea, Republic of)

    2016-05-15

    Integrated Project Delivery (IPD) is defined as that people, systems, business structures, and practices of key stakeholders are incorporated into a single-team, with a single process, which executes a project in a way of optimizing the project's outcome, increasing values delivered to the end user, reducing waste, and maximizing efficiency throughout the phases of engineering to construction. The researcher had carried out literature review in terms of IPD to identify major characteristics of IPD which are presented in the following section and had compared such characteristics against peculiarities of nuclear power plant (NPP) construction projects in order to shed light on obstacles in possible application of IPD method to domestic NPP construction projects in the coming days. In this research, three (3) major characteristics of IPD were identified: 1) key stakeholders signing one balanced contract, forming de facto one body, sharing risk and reward 2) an integrated project team being formed in the early stage of a project and providing input to minimize time and cost loss from rework downstream 3) team members co-locating, having open and direct communication, making decisions on time, and pursuing the success of the project itself.

  6. Germany's nuclear power plant closures and the integration of electricity markets in Europe

    International Nuclear Information System (INIS)

    Menezes, Lilian M. de; Houllier, Melanie A.

    2015-01-01

    This paper examines the potential implications of national policies that lead to a sudden increase of wind power in the electricity mix for interconnected European electricity markets. More specifically, it examines market integration before and after the closures of eight nuclear power plants that occurred within a period of a few months in Germany during 2011. The short- and- long run interrelationships of daily electricity spot prices, from November 2009 to October 2012, in: APX-ENDEX, BELPEX, EPEX-DE, EPEX-FR, NORDPOOL, OMEL and SWISSIX; and wind power in the German system are analysed. Two MGARCH (Multivariate Generalized Autoregressive Conditional Heteroscedasticity) models with dynamic correlations are used to assess spot market behaviour in the short run, and a fractional cointegration analysis is conducted to investigate changes in the long-run behaviour of electricity spot prices. Results show: positive time-varying correlations between spot prices in markets with substantial shared interconnector capacity; a negative association between wind power penetration in Germany and electricity spot prices in the German and neighbouring markets; and, for most markets, a decreasing speed in mean reversion. -- Highlights: •Associations between spot prices and wind power are time-varying. •Greater spot price and volatility associations across markets are observed. •In the long run, the German market is less integrated with neighbouring markets. •Policies on a local electricity mix can affect spot prices in connected markets

  7. Unit and integration testing of Lustre programs: a case study from the nuclear industry

    International Nuclear Information System (INIS)

    Thevenod-Fosse, P.

    1998-01-01

    LUSTRE belongs to the class of synchronous data flow languages which have been designed for programming reactive and real-time systems having safety-critical requirements. It is implemented in the SCADE tool. SCADE is a software development environment for real-time systems which consists of a graphical and textual editor, and a C code generator. In previous work, a testing approach specific to LUSTRE programs has been defined, which may be applied at either the unit or integration testing levels of a gradual testing process. The paper reports on an industrial case study we have performed to exemplify the feasibility of the testing strategy. The software module, called SRIC (Source Range Instrumentation channel), was developed by SCHNEIDER ELECTRIC in the SCADE environment. SRIC is extracted from a monitoring software system of a nuclear reactor: it approximates 2600 lines of C code automatically generated by SCADE. Section 2 outlines the testing strategy. Then, Section 3 presents the results related to the program SRIC, for which four testing levels were defined (unit testing followed by three successive integration testing levels). First conclusions and direction for future work are proposed in Section 4. (author)

  8. Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC).

    Energy Technology Data Exchange (ETDEWEB)

    Schultz, Peter Andrew

    2011-12-01

    The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. Achieving the objective of modeling the performance of a disposal scenario requires describing processes involved in waste form degradation and radionuclide release at the subcontinuum scale, beginning with mechanistic descriptions of chemical reactions and chemical kinetics at the atomic scale, and upscaling into effective, validated constitutive models for input to high-fidelity continuum scale codes for coupled multiphysics simulations of release and transport. Verification and validation (V&V) is required throughout the system to establish evidence-based metrics for the level of confidence in M&S codes and capabilities, including at the subcontiunuum scale and the constitutive models they inform or generate. This Report outlines the nature of the V&V challenge at the subcontinuum scale, an approach to incorporate V&V concepts into subcontinuum scale modeling and simulation (M&S), and a plan to incrementally incorporate effective V&V into subcontinuum scale M&S destined for use in the NEAMS Waste IPSC work flow to meet requirements of quantitative confidence in the constitutive models informed by subcontinuum scale phenomena.

  9. Integration of knowledge management system for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Iguchi, Yukihiro; Yanagihara, Satoshi

    2016-01-01

    The decommissioning of a nuclear facility is a long term project, handling information which begins from the design, construction and operation. Moreover, the decommissioning project is likely to be extended because of the lack of the waste disposal site especially in Japan. In this situation, because the transfer of knowledge and education to the next generation is a crucial issue, integration and implementation of a system for knowledge management is necessary in order to solve it. For this purpose, the total system of decommissioning knowledge management system (KMS) is proposed. In this system, we have to arrange, organize and systematize the data and information of the plant design, maintenance history, trouble events, waste management records etc. The collected data, information and records should be organized by computer support system e.g. data base system. It becomes a base of the explicit knowledge. Moreover, measures of extracting tacit knowledge from retiring employees are necessary. The experience of the retirees should be documented as much as possible through effective questionnaire or interview process. The integrated knowledge mentioned above should be used for the planning, implementation of dismantlement or education for the future generation. (author)

  10. Integrated societal risk assessment framework for nuclear power and renewable energy sources

    International Nuclear Information System (INIS)

    Lee, Sang Hun; Kang, Hyun Gook

    2015-01-01

    Recently, the estimation of the social cost of energy sources has been emphasized as various novel energy options become feasible in addition to conventional ones. In particular, the social cost of introducing measures to protect power-distribution systems from power-source instability and the cost of accident-risk response for various power sources must be investigated. To account for these risk factors, an integrated societal risk assessment framework, based on power-uncertainty analysis and accident-consequence analysis, is proposed. In this study, we applied the proposed framework to nuclear power plants, solar photovoltaic systems, and wind-turbine generators. The required capacity of gas-turbine power plants to be used as backup power facilities to compensate for fluctuations in the power output from the main power source was estimated based on the performance indicators of each power source. The average individual health risk per terawatt-hours (TWh) of electricity produced by each power source was quantitatively estimated by assessing accident frequency and the consequences of specific accident scenarios based on the probabilistic risk assessment methodology. This study is expected to provide insight into integrated societal risk analysis, and can be used to estimate the social cost of various power sources

  11. Integration of computerized operation support systems on a nuclear power plant environment

    International Nuclear Information System (INIS)

    Jaime, Guilherme D.G.; Almeida, Jose C.S.; Oliveira, Mauro V.

    2015-01-01

    Automation of certain tasks in a Nuclear Power Plant (NPP) control room is expected to result in reduced operators' mental workload, which may induce other benefits such as enhanced situation awareness and improved system performance. The final goal should be higher level of operational safety. Thus, recent works are increasingly assessing automation. The LABIHS compact NPP simulator, though, still operates under strictly manual printed hard-copy procedures, despite of the fact that the simulator incorporates several advancements in design of digitalized Human-Interfaces (HSIs). This work presents the development, implementation and integration of selected components to achieve increased level of computerized/automated operation of the LABIHS compact NPP simulator. Specifically, we discuss three components: (I) Automatic Plant Mode Detection, (II) Automatic Alarm Filtering, and (III) Computerized Procedures. Each one of these components has to be carefully designed/integrated so that one can avoid the undesired effects of some known implementations of automated systems on NPP, such as the reduction in the operator's system awareness, an increase in monitoring workload, and the degradation in manual skills, which could lead to automation-induced system failures. (author)

  12. Integration of computerized operation support systems on a nuclear power plant environment

    Energy Technology Data Exchange (ETDEWEB)

    Jaime, Guilherme D.G.; Almeida, Jose C.S.; Oliveira, Mauro V., E-mail: gdjaime@ien.gov.br, E-mail: jcsa@ien.gov.br, E-mail: mvitor@ien.gov.br [Instituto Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Servico de Sistemas Complexos. Divisao de Engenharia Nuclear

    2015-07-01

    Automation of certain tasks in a Nuclear Power Plant (NPP) control room is expected to result in reduced operators' mental workload, which may induce other benefits such as enhanced situation awareness and improved system performance. The final goal should be higher level of operational safety. Thus, recent works are increasingly assessing automation. The LABIHS compact NPP simulator, though, still operates under strictly manual printed hard-copy procedures, despite of the fact that the simulator incorporates several advancements in design of digitalized Human-Interfaces (HSIs). This work presents the development, implementation and integration of selected components to achieve increased level of computerized/automated operation of the LABIHS compact NPP simulator. Specifically, we discuss three components: (I) Automatic Plant Mode Detection, (II) Automatic Alarm Filtering, and (III) Computerized Procedures. Each one of these components has to be carefully designed/integrated so that one can avoid the undesired effects of some known implementations of automated systems on NPP, such as the reduction in the operator's system awareness, an increase in monitoring workload, and the degradation in manual skills, which could lead to automation-induced system failures. (author)

  13. Integrated disturbance analysis (IDA): A basis for expert systems in nuclear power plants

    International Nuclear Information System (INIS)

    Bastl, W.

    1987-01-01

    In the framework of a project sponsored by the Bundesminister fur Forschung und Technologie (BMFT) and the Rheinisch-Westfalisches Elektrizitatswerk AG (RWE) the concept of Integrated Disturbance Analysis (IDA) has been developed and applied to the Biblis Unit B Nuclear Power Plant. Rather than using the classical approach, which aims at finding the cause of a plant disturbance, the main goal was to make transparent to the operator what it really means for the process, when a set of parameters begins to deviate from its normal state. Therefore the goal was to help the operator to combine the information on the individual process parameters to the complete picture of the evolving transient, thus facilitating the decision about the importance of a disturbance for operational safety. Considering this goal the most important subjects taken care of were: to extend event sequence analysis by means of analog information; to provide adequate modelling of time dependent processes and feedback loops; to integrate IDA information effectively into the existing control room environment

  14. Integrated societal risk assessment framework for nuclear power and renewable energy sources

    Directory of Open Access Journals (Sweden)

    Sang Hun Lee

    2015-06-01

    Full Text Available Recently, the estimation of the social cost of energy sources has been emphasized as various novel energy options become feasible in addition to conventional ones. In particular, the social cost of introducing measures to protect power-distribution systems from power-source instability and the cost of accident-risk response for various power sources must be investigated. To account for these risk factors, an integrated societal risk assessment framework, based on power-uncertainty analysis and accident-consequence analysis, is proposed. In this study, we applied the proposed framework to nuclear power plants, solar photovoltaic systems, and wind-turbine generators. The required capacity of gas-turbine power plants to be used as backup power facilities to compensate for fluctuations in the power output from the main power source was estimated based on the performance indicators of each power source. The average individual health risk per terawatt-hours (TWh of electricity produced by each power source was quantitatively estimated by assessing accident frequency and the consequences of specific accident scenarios based on the probabilistic risk assessment methodology. This study is expected to provide insight into integrated societal risk analysis, and can be used to estimate the social cost of various power sources.

  15. Nuclear Dynamics of a Nearby Seyfert with NIRSpec Integral Field Spectroscopy

    Science.gov (United States)

    Bentz, Misty; Batiste, M.; Onken, C.; Roberts, C.; Valluri, M.; Vasiliev, E.

    2017-11-01

    Integral field spectroscopy has become an invaluable tool for investigating the physical conditions and dynamics deep inside galaxy nuclei. The integral field spectrograph on JWST provides some crucial advantages over those on AO- assisted ground-based telescopes like Gemini and VLT. In particular, JWST will provide a stable and diffraction limited point spread function (PSF) with no seeing halo, and the background will be significantly reduced resulting in shorter exposure times to achieve a benchmark signal-to-noise ratio, even for late-type galaxies that have shallower central cusps and fainter central surface brightnesses, and for which the exposure times required from the ground may be prohibitive. We are particularly interested in comparing black hole masses derived from the modeling of nuclear stellar dynamics to masses derived from reverberation mapping in the same galaxies. With this Early Release Science proposal, we request a small investment of time to clearly demonstrate JWST's capabilities in spatial and spectral resolution relative to the stringent technical requirements for direct black hole mass measurements. The technically demanding nature of the requisite measurements will allow us to explore the limits of what is possible to achieve with the NIRSpec IFU, thus providing technical guidance for a wide range of studies that seek to probe the physics of black hole feeding and feedback and their links to galaxy and black hole co-evolution.

  16. Application of Integrated Neural Network Method to Fault Diagnosis of Nuclear Steam Generator

    International Nuclear Information System (INIS)

    Zhou Gang; Yang Li

    2009-01-01

    A new fault diagnosis method based on integrated neural networks for nuclear steam generator (SG) was proposed in view of the shortcoming of the conventional fault monitoring and diagnosis method. In the method, two neural networks (ANNs) were employed for the fault diagnosis of steam generator. A neural network, which was used for predicting the values of steam generator operation parameters, was taken as the dynamics model of steam generator. The principle of fault monitoring method using the neural network model is to detect the deviations between process signals measured from an operating steam generator and corresponding output signals from the neural network model of steam generator. When the deviation exceeds the limit set in advance, the abnormal event is thought to occur. The other neural network as a fault classifier conducts the fault classification of steam generator. So, the fault types of steam generator are given by the fault classifier. The clear information on steam generator faults was obtained by fusing the monitoring and diagnosis results of two neural networks. The simulation results indicate that employing integrated neural networks can improve the capacity of fault monitoring and diagnosis for the steam generator. (authors)

  17. Integration of neural networks with fuzzy reasoning for measuring operational parameters in a nuclear reactor

    International Nuclear Information System (INIS)

    Ikonomopoulos, A.; Tsoukalas, L.H.

    1993-01-01

    A novel approach is described for measuring variables with operational significance in a complex system such as a nuclear reactor. The methodology is based on the integration of artificial neural networks with fuzzy reasoning. Neural networks are used to map dynamic time series to a set of user-defined linguistic labels called fuzzy values. The process takes place in a manner analogous to that of measurement. Hence, the entire procedure is referred to as virtual measurement and its software implementation as a virtual measuring device. An optimization algorithm based on information criteria and fuzzy algebra augments the process and assists in the identification of different states of the monitored parameter. The proposed technique is applied for monitoring parameters such as performance, valve position, transient type, and reactivity. The results obtained from the application of the neural network-fuzzy reasoning integration in a high power research reactor clearly demonstrate the excellent tolerance of the virtual measuring device to faulty signals as well as its ability to accommodate noisy inputs

  18. Integrated logistic support concept in the design of nuclear power plants

    International Nuclear Information System (INIS)

    Martin-Onraet, M.; Degrave, C.; Meuwisse, C.

    1996-01-01

    Considering its plant operating experience, the analysis of foreign practice and the development of new design approaches and tools, Electricite de France (EDF) is convinced that it is possible to improve new plant design, operation and maintenance without increasing too much investment costs. To remain competitive it is necessary to maintain the kWh production cost of the future unit at a level close to those of the latest unit under construction (N4 series), while raising the Safety level. To minimize the kWh cost EDF has decided to implement the CIDEM project (French acronym for Design Integrating Availability, Operating Experience and Maintenance), an analytic and systematic process for studying new projects, aiming at a design optimization including investment, maintenance, availability and radiation exposure objectives. This approach aims at a single goal: to minimize the kWh production cost incorporating investment operation and fuel cost, based on experience from French and foreign units. This process, already widely practiced in other industries or services (aerospace, defense, ...), uses concepts known by the acronyms RAM (Reliability, Availability, Maintainability) RCM (Reliability, Centered Maintenance) and ILS (Integrated Logistic Support). The first CIDEM application is centered on the future French nuclear unit construction program, known as the REP 2000 program but the approach could be applied to other Reactor type or fossil-fired units in particular for its methodological aspect. The purpose of this paper is to introduce the EDF ILS concept

  19. Integrated societal risk assessment framework for nuclear power and renewable energy sources

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Hun; Kang, Hyun Gook [Dept. of Nuclear and Quantum Engineering, KAIST, Daejeon (Korea, Republic of)

    2015-06-15

    Recently, the estimation of the social cost of energy sources has been emphasized as various novel energy options become feasible in addition to conventional ones. In particular, the social cost of introducing measures to protect power-distribution systems from power-source instability and the cost of accident-risk response for various power sources must be investigated. To account for these risk factors, an integrated societal risk assessment framework, based on power-uncertainty analysis and accident-consequence analysis, is proposed. In this study, we applied the proposed framework to nuclear power plants, solar photovoltaic systems, and wind-turbine generators. The required capacity of gas-turbine power plants to be used as backup power facilities to compensate for fluctuations in the power output from the main power source was estimated based on the performance indicators of each power source. The average individual health risk per terawatt-hours (TWh) of electricity produced by each power source was quantitatively estimated by assessing accident frequency and the consequences of specific accident scenarios based on the probabilistic risk assessment methodology. This study is expected to provide insight into integrated societal risk analysis, and can be used to estimate the social cost of various power sources.

  20. Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC)

    International Nuclear Information System (INIS)

    Schultz, Peter Andrew

    2011-01-01

    The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M and S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. Achieving the objective of modeling the performance of a disposal scenario requires describing processes involved in waste form degradation and radionuclide release at the subcontinuum scale, beginning with mechanistic descriptions of chemical reactions and chemical kinetics at the atomic scale, and upscaling into effective, validated constitutive models for input to high-fidelity continuum scale codes for coupled multiphysics simulations of release and transport. Verification and validation (V and V) is required throughout the system to establish evidence-based metrics for the level of confidence in M and S codes and capabilities, including at the subcontiunuum scale and the constitutive models they inform or generate. This Report outlines the nature of the V and V challenge at the subcontinuum scale, an approach to incorporate V and V concepts into subcontinuum scale modeling and simulation (M and S), and a plan to incrementally incorporate effective V and V into subcontinuum scale M and S destined for use in the NEAMS Waste IPSC work flow to meet requirements of quantitative confidence in the constitutive models informed by subcontinuum scale phenomena.

  1. Improved attractants for enhancing tsetse fly suppression

    International Nuclear Information System (INIS)

    2003-09-01

    At the initiation of this co-ordinated research project (CRP), the available visually attractant devices and odours for entomological monitoring and for suppression of tsetse fly populations were not equally effective against all economically important tsetse fly species. For species like G. austeni, G. brevipalpis, G. swynnertoni and some species of the PALPALIS-group of tsetse flies no sufficiently effective combinations of visual or odour attractants were available for efficient suppression and standardized monitoring as part of an operational integrated intervention campaign against the tsetse and trypanosomosis (T and T) problem. The Co-ordinated Research Project on Improved Attractants for Enhancing the Efficiency of Tsetse Fly Suppression Operations and Barrier Systems used in Tsetse Control/Eradication Campaigns involved (a) the identification, synthesis and provision of candidate kairomones, their analogues and of dispensers; (b) laboratory screening of synthesised candidate kairomones through electrophysiological studies and wind tunnel experiments; (c) field tests of candidate kairomones alone or as part of odour blends, in combination with available and or new trap designs; and (d) analysis of hydrocarbons that influence tsetse sexual behaviour. The CRP accomplished several main objectives, namely: - The screening of new structurally related compounds, including specific stereoisomers, of known tsetse attractants resulted in the identification of several new candidate odour attractants with promising potential. - An efficient two-step synthetic method was developed for the pilot plant scale production of 3-n-propyphenol, synergistic tsetse kairomone component. - Electrophysiological experiments complemented with wind tunnel studies provided an efficient basis for the laboratory screening of candidate attractants prior to the initiation of laborious field tests. - New traps were identified and modifications of existing traps were tested for some species

  2. Materials integrity analysis for application of POSCO developed STS to Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Hyun-Young, Ch.; Tae-Eun, J.; Young-Sik, K.

    2009-01-01

    Full text of publication follows: POSCO has developed duplex stainless steel (S32750) and hyper super duplex stainless steels for the purpose of using them in the secondary circulation cooling water system in Korean nuclear power plants. This system supplies seawater to cooling water heat exchanger tubes, related pipes and chlorine injection system. In normal operation, seawater is supplied to heat exchanger through the exit of circulation pump headers and the heat exchanged sea water is extracted to the discharge pipes in circulation cooling water system connected to the circulation water discharge lines. The flow velocity of circulation cooling water system in nuclear power plants is high and damages of components from corrosion are severe. Therefore, this environment makes requiring of using high strength and high corrosion resistant steels. Hyper duplex stainless steel (27Cr-7.0Ni-2.5Mo-3.2W-0.35N) has been newly developed in Korea and is being improved for applying to nuclear power plants. In this study, the physical and mechanical properties and corrosion resistance of currently producing stainless steels and newly developed materials are qualitatively evaluated in comparative to commercial stainless steels in other countries. The properties of weld are analyzed and the best compositions of welding rod are suggested. The optimum weld condition is derived for ensuring HAZ phase ratios and controlling weld cracks. For applying these materials to the seawater heat exchanger, CCT and CPT in weldments are measured using mock-up tube testers that are newly designed for this study. Coupons of candidate materials are introduced in the real system and corrosion resistance of them are analyzed. As results of all experiments, the current CCT and CPT criteria in Korean nuclear power plants are reviewed, and the more actual and strengthened criteria will be suggested. The real scale components made of newly developed hyper super duplex stainless steel will be applied to

  3. Integrated Geophysical Measurements for Bioremediation Monitoring: Combining Spectral Induced Polarization, Nuclear Magnetic Resonance and Magnetic Methods

    Energy Technology Data Exchange (ETDEWEB)

    Keating, Kristina [Rutgers Univ., Newark, NJ (United States). Dept. of Earth and Environmental Sciences; Slater, Lee [Rutgers Univ., Newark, NJ (United States). Dept. of Earth and Environmental Sciences; Ntarlagiannis, Dimitris [Rutgers Univ., Newark, NJ (United States). Dept. of Earth and Environmental Sciences; Williams, Kenneth H. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States). Earth Sciences Division

    2015-02-24

    This documents contains the final report for the project "Integrated Geophysical Measurements for Bioremediation Monitoring: Combining Spectral Induced Polarization, Nuclear Magnetic Resonance and Magnetic Methods" (DE-SC0007049) Executive Summary: Our research aimed to develop borehole measurement techniques capable of monitoring subsurface processes, such as changes in pore geometry and iron/sulfur geochemistry, associated with remediation of heavy metals and radionuclides. Previous work has demonstrated that geophysical method spectral induced polarization (SIP) can be used to assess subsurface contaminant remediation; however, SIP signals can be generated from multiple sources limiting their interpretation value. Integrating multiple geophysical methods, such as nuclear magnetic resonance (NMR) and magnetic susceptibility (MS), with SIP, could reduce the ambiguity of interpretation that might result from a single method. Our research efforts entails combining measurements from these methods, each sensitive to different mineral forms and/or mineral-fluid interfaces, providing better constraints on changes in subsurface biogeochemical processes and pore geometries significantly improving our understanding of processes impacting contaminant remediation. The Rifle Integrated Field Research Challenge (IFRC) site was used as a test location for our measurements. The Rifle IFRC site is located at a former uranium ore-processing facility in Rifle, Colorado. Leachate from spent mill tailings has resulted in residual uranium contamination of both groundwater and sediments within the local aquifer. Studies at the site include an ongoing acetate amendment strategy, native microbial populations are stimulated by introduction of carbon intended to alter redox conditions and immobilize uranium. To test the geophysical methods in the field, NMR and MS logging measurements were collected before, during, and after acetate amendment. Next, laboratory NMR, MS, and SIP measurements

  4. Integrated System Validation of Barakah Nuclear Power Plant in UAE for The Human Factor Engineering

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Munsoo [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    APR1400 simulator has been developed based on the state-of-the-art object-oriented simulation technology of TH(Thermo-Hydraulic) and Reactor Core model, which is applied for the first time in the our country and for the exportation, to well simulate characteristics of APR1400. Barakah unit 1,2 simulator are constructed and supplied with this type simulator model. Integrated system validation was performed using a simulator to verify the HFE(Human Factor Engineering) design of the MCR(Maim Control Room) for instrumentation and control system validation of the UAE nuclear power plant. APR1400 for the Barakah unit 1,2 has many specific features such as digital I and C, and digitalized main control room (MCR) design. From January 2016 to February, during six weeks, the tests carried out three times repeatedly and the various proposals for ergonomical satisfactation were derived. However, the HFE errors that cause significant change of validation target for APR1400 MCR design safety fidelity wasn't found. This has resulted in the conclusion to prove the stability of the basic design of APR1400 MCR. In the future, using the simulator derives the HFE requirements of the MCR systems and continually improve the simulator will be built in close to real high-fidelity power plant. These Integrated system validations are likely to be a great help in operating safety and preventing human errors by operators. Therefore successful completion of the Integrated System Validation for BNPP simulation will be effective to promotion the distinction of our simulator and APR1400 NPP.

  5. Integrated systems of monitoring and environmental data processing for nuclear facilities

    International Nuclear Information System (INIS)

    Diaconu, C.; Guta, V.; Oprea, I.; Oprea, M.; Stoica, M.; Pirvu, V.; Vasilache, E.; Pirvu, I.

    2001-01-01

    The processing of huge amount of data necessary to assess the real radiological situation both in normal operational conditions and during accidents requires an efficient system of monitoring and data processing. It must be able to secure information for the complex systems of radioactivity control aiming at evaluating the nuclear accident consequences and establishing a basis for correct decision making in the field of civil protection. The integrated environmental monitoring systems are based on a number of fixed and mobile installations, a meteorological parameter measurement station, a center for data processing and a communication network, working all under the control of a real-time operation system. They collect, and process the radioactivity level and meteorological data and transmit them through the communication network. The local monitoring stations are made of detector ensembles with pressurized ionization chambers and autonomous units providing continuously information on dose and integrated rates, average values as well as the current state of the station. The meteorological data acquisition station supplies information concerning wind direction and speed, the temperature and precipitation level. The information processing center is based on a PC integrated in a local network which collects data from the radiation monitoring equipment, meteorological station as well as other work stations which process various dosimetric parameters. It is connected to Internet, so ensuring fast transfer of information towards interested authorities. The communication network consists in a local or extended Ethernet network, radio or serial connections for radioactivity level monitoring units which can be stationary, portable or mobile. Requirements raised by the application of geographic information system (GIS) and the real time operation system (QNX) ensuring multiuser and multitask operations are discussed

  6. ABACC - Brazil-Argentina Agency for Accounting and Control of Nuclear Materials, a model of integration and transparence

    International Nuclear Information System (INIS)

    Oliveira, Antonio A.; Do Canto, Odilon Marcusso

    2013-01-01

    Argentina and Brazil began its activities in the nuclear area about the same time, in the 50 century past. The existence of an international nuclear nonproliferation treaty-TNP-seen by Brazil and Argentina as discriminatory and prejudicial to the interests of the countries without nuclear weapons, led to the need for a common system of control of nuclear material between the two countries to somehow provide assurances to the international community of the exclusively peaceful purpose of its nuclear programs. The creation of a common system, assured the establishment of uniform procedures to implement safeguards in Argentina and Brazil, so the same requirements and safeguards procedures took effect in both countries, and the operators of nuclear facilities began to follow the same rules of control of nuclear materials and subjected to the same type of verification and control. On July 18, 1991, the Bilateral Agreement for the Exclusively Peaceful Use of Nuclear Energy created a binational body, the Argentina-Brazil Agency for Accounting and Control of Nuclear Materials-ABACC-to implement the so-called Common System of Accounting and Control of Nuclear materials - SCCC. The deal provided, permanently, a clear commitment to use exclusively for peaceful purposes all material and nuclear facilities under the jurisdiction or control of the two countries. The Quadripartite Agreement, signed in December of that year, between the two countries, ABACC and IAEA completed the legal framework for the implementation of comprehensive safeguards system. The 'model ABACC' now represents a paradigmatic framework in the long process of economic, political, technological and cultural integration of the two countries. Argentina and Brazil were able to establish a guarantee system that is unique in the world today and that consolidated and matured over more than twenty years, has earned the respect of the international community

  7. Lessons from American-German nuclear power plant construction. Quality, safety and costs of an attempt to integrate American and German nuclear power plant technology

    International Nuclear Information System (INIS)

    Buchwald, K.

    1979-05-01

    The 1300 MW nuclear power plant at Muelheim-Kaerlich has been under construction since the beginning of 1975. It is being equipped with a pressurised water reactor which has been adapted to the German client's requirements and German licensing practice, based on a license held by Babcock and Wilcox USA (B and W). The problems which have arisen in making this adaptation are the result of different requirements in the USA and the Federal Republic of Germany which make it very difficult to integrate the two technologies. Full integration will almost certainly be impossible, but integration to the widest possible extent is important because it might mean both greater safety and reduced costs. In this article it is intended to show where the problems of integration lie and how they might perhaps be overcome. (author)

  8. Integrated Optimization of Long-Range Underwater Signal Detection, Feature Extraction, and Classification for Nuclear Treaty Monitoring

    NARCIS (Netherlands)

    Tuma, M.; Rorbech, V.; Prior, M.; Igel, C.

    2016-01-01

    We designed and jointly optimized an integrated signal processing chain for detection and classification of long-range passive-acoustic underwater signals recorded by the global geophysical monitoring network of the Comprehensive Nuclear-Test-Ban Treaty Organization. Starting at the level of raw

  9. A comparison of response spectrum and direct integration analysis methods as applied to a nuclear component support structure

    International Nuclear Information System (INIS)

    Bryan, B.J.; Flanders, H.E. Jr.

    1992-01-01

    Seismic qualification of Class I nuclear components is accomplished using a variety of analytical methods. This paper compares the results of time history dynamic analyses of a heat exchanger support structure using response spectrum and time history direct integration analysis methods. Dynamic analysis is performed on the detailed component models using the two methods. A nonlinear elastic model is used for both the response spectrum and direct integration methods. A nonlinear model which includes friction and nonlinear springs, is analyzed using time history input by direct integration. The loads from the three cases are compared

  10. Physical Attractiveness and Counseling Skills.

    Science.gov (United States)

    Vargas, Alice M.; Borkowski, John G.

    1982-01-01

    Searched for interaction between quality of counseling skills (presence or absence of empathy, genuineness, and positive regard) and physical attractiveness as determinants of counseling effectiveness. Attractiveness influenced perceived effectiveness of counselor's skill. Analyses of expectancy data revealed that only with good skills did…

  11. Physical Attractiveness and Interpersonal Influence

    Science.gov (United States)

    Dion, Karen K.; Stein, Steven

    1978-01-01

    Examines the hypothesis that attractive individuals should be more successful with opposite-sex peers but less successful with same-sex peers than unattractive individuals. Also investigates the influence strategies employed by persons differing in attractiveness since nothing is currently known about the actual behavior exhibited by attractive…

  12. Physical attractiveness stereotype and memory.

    Science.gov (United States)

    Rohner, Jean-Christophe; Rasmussen, Anders

    2011-08-01

    Three experiments examined explicit and implicit memory for information that is congruent with the physical attractiveness stereotype (i.e. attractive-positive and unattractive-negative) and information that is incongruent with the physical attractiveness stereotype (i.e. attractive-negative and unattractive-positive). Measures of explicit recognition sensitivity and implicit discriminability revealed a memorial advantage for congruent compared to incongruent information, as evident from hit and false alarm rates and reaction times, respectively. Measures of explicit memory showed a recognition bias toward congruent compared to incongruent information, where participants tended to call congruent information old, independently of whether the information had been shown previously or not. This recognition bias was unrelated to reports of subjective confidence in retrieval. The present findings shed light on the cognitive mechanisms that might mediate discriminatory behavior towards physically attractive and physically unattractive individuals. © 2011 The Authors. Scandinavian Journal of Psychology © 2011 The Scandinavian Psychological Associations.

  13. The 2014 Integrated Field Exercise of the Comprehensive Nuclear-Test-Ban Treaty revisited: The case for data fusion.

    Science.gov (United States)

    Burnett, Jonathan L; Miley, Harry S; Bowyer, Theodore W; Cameron, Ian M

    2018-09-01

    The International Monitoring System of the Preparatory Commission for the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO) uses a global network of radionuclide monitoring stations to detect evidence of a nuclear explosion. The two radionuclide technologies employed-particulate and noble gas (radioxenon) detection-have applications for data fusion to improve detection of a nuclear explosion. Using the hypothetical 0.5 kT nuclear explosive test scenario of the CTBTO 2014 Integrated Field Exercise, the intrinsic relationship between particulate and noble gas signatures has been examined. This study shows that, depending upon the time of the radioxenon release, the particulate progeny can produce the more detectable signature. Thus, as both particulate and noble gas signatures are inherently coupled, the authors recommend that the sample categorization schemes should be linked. Copyright © 2018 Elsevier Ltd. All rights reserved.

  14. The 2014 Integrated Field Exercise of the Comprehensive Nuclear-Test-Ban Treaty revisited: the case for data fusion

    Energy Technology Data Exchange (ETDEWEB)

    Burnett, Jonathan L.; Miley, Harry S.; Bowyer, Theodore W.; Cameron, Ian M.

    2018-04-18

    The International Monitoring System of the Preparatory Commission for the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO) uses a global network of radionuclide monitoring stations to detect evidence of a nuclear explosion. The two radionuclide technologies employed—particulate and noble gas (radioxenon) detection—have applications for data fusion to improve detection of a nuclear explosion. Using the hypothetical 0.5 kT nuclear explosive test scenario of the CTBTO 2014 Integrated Field Exercise, the intrinsic relationship between particulate and noble gas signatures has been examined. This study shows that, depending upon the time of the radioxenon release, the particulate progeny can produce the more detectable signature. Thus, as both particulate and noble gas signatures are inherently coupled, the authors recommend that the sample categorization schemes should be linked.

  15. BWR Spent Nuclear Fuel Integrity Research and Development Survey for UKABWR Spent Fuel Interim Storage

    Energy Technology Data Exchange (ETDEWEB)

    Bevard, Bruce Balkcom [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Mertyurek, Ugur [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Scaglione, John M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-10-01

    The objective of this report is to identify issues and support documentation and identify and detail existing research on spent fuel dry storage; provide information to support potential R&D for the UKABWR (United Kingdom Advanced Boiling Water Reactor) Spent Fuel Interim Storage (SFIS) Pre-Construction Safety Report; and support development of answers to questions developed by the regulator. Where there are gaps or insufficient data, Oak Ridge National Laboratory (ORNL) has summarized the research planned to provide the necessary data along with the schedule for the research, if known. Spent nuclear fuel (SNF) from nuclear power plants has historically been stored on site (wet) in spent fuel pools pending ultimate disposition. Nuclear power users (countries, utilities, vendors) are developing a suite of options and set of supporting analyses that will enable future informed choices about how best to manage these materials. As part of that effort, they are beginning to lay the groundwork for implementing longer-term interim storage of the SNF and the Greater Than Class C (CTCC) waste (dry). Deploying dry storage will require a number of technical issues to be addressed. For the past 4-5 years, ORNL has been supporting the U.S. Department of Energy (DOE) in identifying these key technical issues, managing the collection of data to be used in issue resolution, and identifying gaps in the needed data. During this effort, ORNL subject matter experts (SMEs) have become expert in understanding what information is publicly available and what gaps in data remain. To ensure the safety of the spent fuel under normal and frequent conditions of wet and subsequent dry storage, intact fuel must be shown to: 1.Maintain fuel cladding integrity; 2.Maintain its geometry for cooling, shielding, and subcriticality; 3.Maintain retrievability, and damaged fuel with pinhole or hairline cracks must be shown not to degrade further. Where PWR (pressurized water reactor) information is

  16. The development of an integrated nuclear fuel-cycle industry to meet the needs of the Italian nuclear power programme

    International Nuclear Information System (INIS)

    Angelini, A.M.; Badolato, G.; Clementel, E.

    1977-01-01

    The paper summarizes the Italian nuclear power station programme, recently approved by the Government, and illustrates the main reasons for the programme, which are in line with those presented at the Geneva Conference in 1971, and which lead to the consideration that nuclear energy is the main source for meeting practically all new electric power requirements in Italy. The implementation of this programme involves considerable nuclear fuel-cycle services, ranging from uranium supply to waste disposal. The industrial strategy to meet these needs is discussed. Technical and economic factors affecting such strategy, both for the fuel cycle as a whole and for its individual phases, are considered. Attention is focused on problems typical of the Italian situation and on various ways of solving them. A prominent feature of the Italian situation is the lack of sizeable domestic uranium resources, which makes it even more important to try, by local industrial efforts, to cover the phases of the cycle subsequent to uranium supply, so as to increase as much as possible the fraction of added value produced inside the country. The present status of the Italian nuclear fuel-cycle industry is reviewed in detail, and its capability of supporting the nuclear programme is analysed. Future development plans are discussed, taking into account the possibility of European co-operation. While the focus is on short- and medium-term programmes, the long-term nuclear programmes are discussed, such as those based on fast breeders, and stress is laid on the need to build up as quickly as possible a strong nuclear fuel-cycle industry. (author)

  17. Structural integrity of rod cluster control assembly of Chashma Nuclear Power Plant -1

    International Nuclear Information System (INIS)

    Siddiqui, A.; Zafar, F.; Murtaza, G.

    2008-01-01

    This study has been made in an attempt to verify the structural integrity of Rod Cluster Control Assembly (RCCA) of Chashma Nuclear Power Plant-1(CHASNUPP-1) using ANSYS computer code. The CHASNUPP-1 (PWR type, 300 MWe capacity, unit 1) was built by China at Chashma (District Mianwali), Pakistan. The plant is successfully operating since 2000. The rod cluster control assemblies (RCCA) are used to control fast reactivity changes in PWR type reactors during the normal operation and accident conditions. To fulfill this function the RCCA is stepped upwards or downwards by control rod drive mechanism (CRDM). The stepping action produces a large amount of acceleration. The load produced during stepping is normally considered as limiting one. In this work we have considered the experimental results of a test conducted in China. The test was performed to measure the acceleration produced in upward and downward stepping by CRDM on RCCA, at room temperatures, both in air and static water. The test results showed acceleration (g, m/s 2 ) values, 10.8 - 51.0 and 46.4 - 78.0, in air and static water environments, respectively. Making the analysis on conservative side we selected the highest value of acceleration, 78 g, for our study. To ensure the structural strength, a finite element model of CHASNUPP-1 RCCA has been developed simulating the loading conditions prevailing during reactor operation. This model has been analyzed using the Finite Element Code. The Maximum Stress intensity obtained through this analysis, 186 MPa, is less than the yield stress of RCCA material (∼SS 321), 205 MPa, thus fulfills its structural integrity criteria. (authors)

  18. Spent nuclear fuel integrity during dry storage - performance tests and demonstrations

    International Nuclear Information System (INIS)

    McKinnon, M.A.; Doherty, A.L.

    1997-06-01

    This report summarizes the results of fuel integrity surveillance determined from gas sampling during and after performance tests and demonstrations conducted from 1983 through 1996 by or in cooperation with the US DOE Office of Commercial Radioactive Waste Management (OCRWM). The cask performance tests were conducted at Idaho National Engineering Laboratory (INEL) between 1984 and 1991 and included visual observation and ultrasonic examination of the condition of the cladding, fuel rods, and fuel assembly hardware before dry storage and consolidation of fuel, and a qualitative determination of the effects of dry storage and fuel consolidation on fission gas release from the spent fuel rods. The performance tests consisted of 6 to 14 runs involving one or two loading, usually three backfill environments (helium, nitrogen, and vacuum backfills), and one or two storage system orientations. The nitrogen and helium backfills were sampled and analyzed to detect leaking spent fuel rods. At the end of each performance test, periodic gas sampling was conducted on each cask. A spent fuel behavior project (i.e., enhanced surveillance, monitoring, and gas sampling activities) was initiated by DOE in 1994 for intact fuel in a CASTOR V/21 cask and for consolidated fuel in a VSC-17 cask. The results of the gas sampling activities are included in this report. Information on spent fuel integrity is of interest in evaluating the impact of long-term dry storage on the behavior of spent fuel rods. Spent fuel used during cask performance tests at INEL offers significant opportunities for confirmation of the benign nature of long-term dry storage. Supporting cask demonstration included licensing and operation of an independent spent fuel storage installation (ISFSI) at the Virginia Power (VP) Surry reactor site. A CASTOR V/21, an MC-10, and a Nuclear Assurance NAC-I28 have been loaded and placed at the VP ISFSI as part of the demonstration program. 13 refs., 14 figs., 9 tabs

  19. Geophysics, Remote Sensing, and the Comprehensive Nuclear-Test-Ban Treaty (CTBT) Integrated Field Exercise 2014

    Science.gov (United States)

    Sussman, A. J.; Macleod, G.; Labak, P.; Malich, G.; Rowlands, A. P.; Craven, J.; Sweeney, J. J.; Chiappini, M.; Tuckwell, G.; Sankey, P.

    2015-12-01

    The Integrated Field Exercise of 2014 (IFE14) was an event held in the Hashemite Kingdom of Jordan (with concurrent activities in Austria) that tested the operational and technical capabilities of an on-site inspection (OSI) within the CTBT verification regime. During an OSI, up to 40 international inspectors will search an area for evidence of a nuclear explosion. Over 250 experts from ~50 countries were involved in IFE14 (the largest simulation of a real OSI to date) and worked from a number of different directions, such as the Exercise Management and Control Teams (which executed the scenario in which the exercise was played) and those participants performing as members of the Inspection Team (IT). One of the main objectives of IFE14 was to test and integrate Treaty allowed inspection techniques, including a number of geophysical and remote sensing methods. In order to develop a scenario in which the simulated exercise could be carried out, suites of physical features in the IFE14 inspection area were designed and engineered by the Scenario Task Force (STF) that the IT could detect by applying the geophysical and remote sensing inspection technologies, in addition to other techniques allowed by the CTBT. For example, in preparation for IFE14, the STF modeled a seismic triggering event that was provided to the IT to prompt them to detect and localize aftershocks in the vicinity of a possible explosion. Similarly, the STF planted shallow targets such as borehole casings and pipes for detection using other geophysical methods. In addition, airborne technologies, which included multi-spectral imaging, were deployed such that the IT could identify freshly exposed surfaces, imported materials, and other areas that had been subject to modification. This presentation will introduce the CTBT and OSI, explain the IFE14 in terms of the goals specific to geophysical and remote sensing methods, and show how both the preparation for and execution of IFE14 meet those goals.

  20. Effects of student physical attractiveness

    Directory of Open Access Journals (Sweden)

    Krnjajić Stevan B.

    2005-01-01

    Full Text Available Implicit personality theories suggest that people draw conclusions about other persons by using a relatively small number of visible features. The formation of "the first impression" is influenced by the factors, such as sex, age, appearances, race or nationality. Frequently, conclusions based on those factors lead to developing social stereotypes. Attractiveness is a good example of "the first impression" effect, because physical attractiveness entails the creation of impression about another person along a relatively great number of dimensions. Experimental paradigm, introduced in the sphere of interpersonal perception around the mid-20th century, led to a relatively great number of studies on stereotype based on physical attractiveness. One of the most often quoted conclusions of studies on physical attractiveness is summarized by the idiom "what is beautiful is good". For example, socially desirable personality traits (responsibility kindness, energy quality, modesty, more successful private and professional life, are all attributed to physically attractive persons. In addition physical attractiveness is coupled with positive expectations, peer acceptance, academic achievement etc. On the basis of studies on the "what is beautiful is good" stereotype, we have situated our analysis within the domain of roles regulating social interaction between teachers and students i.e. effects of physical attractiveness on teacher expectations, peer acceptance and academic achievement.

  1. A proposed structural, risk-informed approach to the periodicity of CANDU-6 nuclear containment integrated leak rate testing

    Energy Technology Data Exchange (ETDEWEB)

    Saliba, N. [McGill Univ., Dept. of Civil Engineering and Applied Mechanics, Montreal, Quebec (Canada); Komljenovic, D. [Hydro-Quebec, Gentilly-2 Nuclear Power Plant, Becancour, Quebec (Canada); Chouinard, L. [McGill Univ., Dept. of Civil Engineering and Applied Mechanics, Montreal, Quebec (Canada); Vaillancourt, R.; Chretien, G. [Hydro-Quebec, Gentilly-2 Nuclear Power Plant, Becancour, Quebec (Canada); Gocevski, V. [Hydro-Quebec Equipements, Montreal, Quebec (Canada)

    2010-07-01

    As ultimate lines of defense against leakage of large amounts of radioactive material to the environment in case of major reactor accidents, containments have been monitored through well designed periodic tests to ensure their proper performance. Regulatory organizations have imposed types and frequencies of containment tests based on highly-conservative deterministic approaches, and judgments of knowledgeable experts. Recent developments in the perception and methods of risk evaluation have been applied to rationalize the leakage-rate testing frequencies while maintaining risks within acceptable levels, preserving the integrity of containments, and respecting the defense-in-depth philosophy. The objective of this paper is to introduce a proposed risk-informed decision making framework on the periodicity of nuclear containment ILRTs for CANDU-6 nuclear power plants based on five main decision criteria, namely: 1) the containment structural integrity; 2) inputs from PSA Level-2; 3) the requirements of deterministic safety analyses and defense-in-depth concepts; 4- the obligations under regulatory and standard requirements; and 5) the return of experience from nuclear containments historic performance. The concepts of dormant reliability and structural fragility will guide the assessment of the containment structural integrity, within the general context of a global containment life cycle management program. This study is oriented towards the requirements of CANDU-6 reactors, in general, and Hydro-Quebec's Gentilly-2 nuclear power plant, in particular. The present article is the first part in a series of papers that will comprehensively detail the proposed research. (author)

  2. A proposed structural, risk-informed approach to the periodicity of CANDU-6 nuclear containment integrated leak rate testing

    International Nuclear Information System (INIS)

    Saliba, N.; Komljenovic, D.; Chouinard, L.; Vaillancourt, R.; Chretien, G.; Gocevski, V.

    2010-01-01

    As ultimate lines of defense against leakage of large amounts of radioactive material to the environment in case of major reactor accidents, containments have been monitored through well designed periodic tests to ensure their proper performance. Regulatory organizations have imposed types and frequencies of containment tests based on highly-conservative deterministic approaches, and judgments of knowledgeable experts. Recent developments in the perception and methods of risk evaluation have been applied to rationalize the leakage-rate testing frequencies while maintaining risks within acceptable levels, preserving the integrity of containments, and respecting the defense-in-depth philosophy. The objective of this paper is to introduce a proposed risk-informed decision making framework on the periodicity of nuclear containment ILRTs for CANDU-6 nuclear power plants based on five main decision criteria, namely: 1) the containment structural integrity; 2) inputs from PSA Level-2; 3) the requirements of deterministic safety analyses and defense-in-depth concepts; 4- the obligations under regulatory and standard requirements; and 5) the return of experience from nuclear containments historic performance. The concepts of dormant reliability and structural fragility will guide the assessment of the containment structural integrity, within the general context of a global containment life cycle management program. This study is oriented towards the requirements of CANDU-6 reactors, in general, and Hydro-Quebec's Gentilly-2 nuclear power plant, in particular. The present article is the first part in a series of papers that will comprehensively detail the proposed research. (author)

  3. Maintaining the design integrity of nuclear installations throughout their operating life. INSAG-19. A report by the International Nuclear Safety Advisory Group

    International Nuclear Information System (INIS)

    2003-01-01

    A nuclear power plant design is the product of the activities of many organizations, and changes to that design will occur continuously over the plant's lifetime. Reactor plants are designed to operate for a long period of time, typically 40 years, which may be extended for several decades. This period of time spans several working lifetimes of the staff of the plant, and its length represents a very specific challenge to safety and to the corporate asset management of the enterprise. It also implies that the vendor structure required to support the plant can be expected to change substantially during the plant's lifetime. this INSAG report discusses the problem of maintaining the integrity of design of a nuclear power plant over its entire lifetime in order to achieve a continuous high level of safety. A nuclear power plant design is the product of the activities of many organizations, and changes to that design will occur continuously over the plant's operating lifetime. Reactor plants are designed to operate for a long period of time, typically 40 years, which may be extended for several decades. This period of time spans several working lifetimes of the staff of the plant, and its length represents a very specific challenge to safety and to the corporate asset management of the enterprise. It also implies that the vendor structure required to support the plant can be expected to change substantially during the plant's lifetime. The purpose of this report is to identify the issues and some of the principles that should be addressed, discuss some of the solutions to the problem, and highlight the specific responsibilities of designers, operators and regulators. The issues and principles discussed here are also applicable to other nuclear installations (for example, research reactors and fuel cycle facilities). This INSAG report is directed at senior executives who are responsible for: the overall safety of nuclear installations; the operation, maintenance and

  4. Maintaining the design Integrity of nuclear installations throughout their operating life. INSAG-19. A report by the International Nuclear Safety Advisory Group (Russian Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    A nuclear power plant design is the product of the activities of many organizations, and changes to that design will occur continuously over the plant's lifetime. Reactor plants are designed to operate for a long period of time, typically 40 years, which may be extended for several decades. This period of time spans several working lifetimes of the staff of the plant, and its length represents a very specific challenge to safety and to the corporate asset management of the enterprise. It also implies that the vendor structure required to support the plant can be expected to change substantially during the plant's lifetime. this INSAG report discusses the problem of maintaining the integrity of design of a nuclear power plant over its entire lifetime in order to achieve a continuous high level of safety. A nuclear power plant design is the product of the activities of many organizations, and changes to that design will occur continuously over the plant's operating lifetime. Reactor plants are designed to operate for a long period of time, typically 40 years, which may be extended for several decades. This period of time spans several working lifetimes of the staff of the plant, and its length represents a very specific challenge to safety and to the corporate asset management of the enterprise. It also implies that the vendor structure required to support the plant can be expected to change substantially during the plant's lifetime. The purpose of this report is to identify the issues and some of the principles that should be addressed, discuss some of the solutions to the problem, and highlight the specific responsibilities of designers, operators and regulators. The issues and principles discussed here are also applicable to other nuclear installations (for example, research reactors and fuel cycle facilities). This INSAG report is directed at senior executives who are responsible for: the overall safety of nuclear installations; the operation

  5. Development of a three dimensional elastic plastic analysis system for the integrity evaluation of nuclear power plant components

    International Nuclear Information System (INIS)

    Huh, Nam Su; Im, Chang Ju; Kim, Young Jin; Pyo, Chang Ryul; Park, Chi Yong

    2000-01-01

    In order to evaluate the integrity of nuclear power plant components, the analysis based on fracture mechanics is crucial. For this purpose, finite element method is popularly used to obtain J-integral. However, it is time consuming to design the finite element model of a cracked structure. Also, the J-integral should by verified by alternative methods since it may differ depending on the calculation method. The objective of this paper is to develop a three-dimensional elastic-plastic J-integral analysis system which is named as EPAS program. The EPAS program consists of an automatic mesh generator for a through-wall crack and a surface crack, a solver based on ABAQUS program, and a J-integral calculation program which provides DI (Domain Integral) and EDI (Equivalent Domain Integral) based J-integral calculation. Using the EPAS program, an optimized finite element model for a cracked structure can be generated and corresponding J-integral can be obtained subsequently

  6. Sextant: an expert system for transient analysis of nuclear reactors and integral test facilities

    International Nuclear Information System (INIS)

    Barbet, N.; Dumas, M.; Mihelich, G.

    1987-01-01

    Expert systems provide a new way of dealing with the computer-aided management of nuclear plants by combining several knowledge bases and reasoning modes together with a set of numerical models for real-time analysis of transients. New development tools are required together with metaknowledge bases handling temporal hypothetical reasoning and planning. They have to be efficient and robust because during a transient, neither measurements nor models, nor scenarios are hold as absolute references. SEXTANT is a general purpose physical analyzer intended to provide a pattern and avoid duplication of general tools and knowledge bases for similar applications. It combines several knowledge bases concerning measurements, models and qualitative behavior of PWR with a mechanism of conjecture-refutation and a set of simplified models matching the current physical state. A prototype is under assessment by dealing with integral test facility transients. For its development, SEXTANT requires a powerful shell. SPIRAL is such a toolkit, oriented towards online analysis of complex processes and already used in several applications

  7. Comparison of results of integrated nuclear medical kidney examinations in different stages of Diabetes mellitus

    International Nuclear Information System (INIS)

    Krieger, E.

    1979-01-01

    In 67 diabetics and 33 hypertonics the author carried out the following tests: 1. Serial renal function scintiscanning with 131 J-oJH; 2. Simultaneous assessment of global sup(99m)Tc-dtpa and 131 J-oJH clearance using a partly screened-off whole-body count 3. Unilateral assessment of 131 J-oJH clearance; 4. Assessment of sup(99m)Tc-dtpa and 131 J-oJH excretion. From the integral gamma-camera time-activity curves established by ROI technique as a part of serial functional scintiscanning, the nephrogram parameters secretion value, secretion maximum and elimination half-time were ascertained. The values thus obtained were compared with the global and unilateral 131 J-oJH clearance. Moreover the excretion of the radiopharmaceuticals in the urine was compared with whole-body clearance determined simultaneously. At normal renal function, the biological half-life for 131 J-oJH and sup(99m)Tc-dtpa was calculated and the distribute volumes were assessed from the elimination constant and from renal clearance. The results of the nuclear-medical renal-function parameters in varying stages of diabetic renal disease indicate that the elimination half-time is the only RIN criterion to permit a differentiation of collectives. (orig./MG) [de

  8. Battelle integrity of nuclear piping program. Summary of results and implications for codes/standards

    International Nuclear Information System (INIS)

    Miura, Naoki

    2005-01-01

    The BINP(Battelle Integrity of Nuclear Piping) program was proposed by Battelle to elaborate pipe fracture evaluation methods and to improve LBB and in-service flaw evaluation criteria. The program has been conducted from October 1998 to September 2003. In Japan, CRIEPI participated in the program on behalf of electric utilities and fabricators to catch up the technical backgrounds for possible future revision of LBB and in-service flaw evaluation standards and to investigate the issues needed to be reflected to current domestic standards. A series of the results obtained from the program has been well utilized for the new LBB Regulatory Guide Program by USNRC and for proposal of revised in-service flaw evaluation criteria to the ASME Code Committee. The results were assessed whether they had implications for the existing or future domestic standards. As a result, the impact of many of these issues, which were concerned to be adversely affected to LBB approval or allowable flaw sizes in flaw evaluation criteria, was found to be relatively minor under actual plant conditions. At the same time, some issues that needed to be resolved to address advanced and rational standards in the future were specified. (author)

  9. RODOS and RESY: two integrated real time on-line decision support systems for nuclear emergencies

    International Nuclear Information System (INIS)

    Ehrhardt, J.; Fischer, F.; Paesler-Sauer, J.; Schuele, O.; Benz, G.; Rafat, M.

    1993-01-01

    Based on the experience gained with the development of the German real-time system RESY for near range and early phase decision support KfK has developed the hardware and software framework of RODOS, the EC real-time on-line decision support system for nuclear emergencies. The first prototype version of RODOS incorporates models for atmospheric dispersion, for external and internal dose and dose-rate assessments, for simulating sheltering, evacuation and milk interdiction, for estimating health effects and economic costs, and for evaluating action alternatives by means of a rule based system containing components of multi-attribute value techniques. The specially designed operating system has been developed on the basis of the client-server model as a transportable package to run on workstations with a standard based UNIX operating system, and an X-Window system. One of its key features is the support of integrated external software products developed by the contractors by providing standardized services, such as system control, data management and graphical presentation. A data base of geographical structures (e.g. landscape, buildings, traffic network) with an accuracy of 30 m stored as vector data and population distribution stored in a 1 kmx1 km grid allows the presentation and evaluation of results down to a high local resolution by a special graphics subsystem. (orig./DG)

  10. Integrated equipment for increasing and maintaining coolant pressure in primary circuit of PWR nuclear power plant

    International Nuclear Information System (INIS)

    Sykora, D.

    1986-01-01

    An open heat pump circuit is claimed connected to the primary circuit. The pump circuit consists of a steam pressurizer with a built-in steam distributor, a compressor, an expander, a reducing valve, an auxiliary pump, and of water and steam pipes. The operation is described and a block diagram is shown of integrated equipment for increasing and maintaining pressure in the nuclear power plant primary circuit. The appropriate entropy diagram is also shown. The advantage of the open pump circuit consists in reducing the electric power input and electric power consumption for the steam pressurizers, removing entropy loss in heat transfer with high temperature gradient, in the possibility of inserting, between the expander and the auxiliary pump, a primary circuit coolant treatment station, in simplified design and manufacture of the high-pressure steam pressurizer vessel, reducing the weight of the steam pressurizer by changing its shape from cylindrical to spherical, increasing the rate of pressure growth in the primary circuit. (E.S.)

  11. Integrated project-management information systems: the French nuclear industry experience

    Energy Technology Data Exchange (ETDEWEB)

    Jacquin, J.C.; Capuin, G.M.

    1988-01-01

    In the early eighties, and in the French case from 1985, the development of the data-processing industry has made the real integration of project-management information systems feasible, and the data-base administration function has been extended to all facets of the engineering process. The new systems had to take into account the existing ones which were still operating efficiently and the new problems encountered due to the changes in the environment. One of these new problems was equipment and materials management, as the period of plants built in series had vanished, and the industry was obliged to build plants individually. The challenge encountered by the French nuclear industry in terms of the project-management information systems was to adapt efficiently to the new situation, and the purpose of this paper is to describe the most-significant elements of this adaptation. The authors review: (2) the objectives established by the company's general management; (2) the organization put into place to reach these objectives; (3) the main choices made; and (4) the economics. 3 references, 1 figure, 1 table.

  12. Integrated project-management information systems: the French nuclear industry experience

    International Nuclear Information System (INIS)

    Jacquin, J.C.; Capuin, G.M.

    1988-01-01

    In the early eighties, and in the French case from 1985, the development of the data-processing industry has made the real integration of project-management information systems feasible, and the data-base administration function has been extended to all facets of the engineering process. The new systems had to take into account the existing ones which were still operating efficiently and the new problems encountered due to the changes in the environment. One of these new problems was equipment and materials management, as the period of plants built in series had vanished, and the industry was obliged to build plants individually. The challenge encountered by the French nuclear industry in terms of the project-management information systems was to adapt efficiently to the new situation, and the purpose of this paper is to describe the most-significant elements of this adaptation. The authors review: (2) the objectives established by the company's general management; (2) the organization put into place to reach these objectives; (3) the main choices made; and (4) the economics. 3 references, 1 figure, 1 table

  13. Study of developing nuclear fabrication facility's integrated emergency response manual

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Taeh Yeong; Cho, Nam Chan; Han, Seung Hoon; Moon, Jong Han; Lee, Jin Hang [KEPCO, Daejeon (Korea, Republic of); Min, Guem Young; Han, Ji Ah [Dongguk Univ., Daejeon (Korea, Republic of)

    2016-05-15

    Public begin to pay attention to emergency management. Thus, public's consensus on having high level of emergency management system up to advanced country's is reached. In this social atmosphere, manual is considered as key factor to prevent accident or secure business continuity. Therefore, we first define possible crisis at KEPCO Nuclear Fuel (hereinafter KNF) and also make a 'Reaction List' for each crisis situation at the view of information-design. To achieve it, we analyze several country's crisis response manual and then derive component, indicate duties and roles at the information-design point of view. From this, we suggested guideline to make 'Integrated emergency response manual(IERM)'. The manual we used before have following few problems; difficult to applicate at the site, difficult to deliver information. To complement these problems, we searched manual elements from the view of information-design. As a result, we develop administrative manual. Although, this manual could be thought as fragmentary manual because it confined specific several agency/organization and disaster type.

  14. An integrated approach for investigation of failed nuclear fuel used at NPP Cernavoda Unit 1

    International Nuclear Information System (INIS)

    Tuturici, I.L.; Parvan, M.; Popov, M.; Dobrin, R.; Staicu, C.

    1996-01-01

    At NPP Cernavoda-Unit 1 the fuel surveillance and the defect detection system in operation are based on monitoring the coolant activity concentration and on measuring the flux of delayed neutrons emitted by some short-lived fission products. In order to identify the failed fuel underwater non-destructive examination has to be performed. The major interest for the availability of underwater examination consists in the necessity of a speedy acquisition of the data on failed fuel in operation and of appropriate follow-up actions to be taken. Often the identification operation will be followed by more detailed examinations on selected fuel rods in the hot cells of the Post-irradiation Examination Laboratory of the Institute for Nuclear Research at Pitesti. Transfer of selected fuel rods will be done by the use of a type B(U) road transportation cask. Such an integrated approach will help to keep the level of activity concentration of the primary circuit well below the authorized limits. (author). 2 figs., 1 tab., 2 refs

  15. Nuclear trafficking of the HIV-1 pre-integration complex depends on the ADAM10 intracellular domain

    International Nuclear Information System (INIS)

    Endsley, Mark A.; Somasunderam, Anoma D.; Li, Guangyu; Oezguen, Numan; Thiviyanathan, Varatharasa; Murray, James L.; Rubin, Donald H.; Hodge, Thomas W.

    2014-01-01

    Previously, we showed that ADAM10 is necessary for HIV-1 replication in primary human macrophages and immortalized cell lines. Silencing ADAM10 expression interrupted the HIV-1 life cycle prior to nuclear translocation of viral cDNA. Furthermore, our data indicated that HIV-1 replication depends on the expression of ADAM15 and γ-secretase, which proteolytically processes ADAM10. Silencing ADAM15 or γ-secretase expression inhibits HIV-1 replication between reverse transcription and nuclear entry. Here, we show that ADAM10 expression also supports replication in CD4 + T lymphocytes. The intracellular domain (ICD) of ADAM10 associates with the HIV-1 pre-integration complex (PIC) in the cytoplasm and immunoprecipitates and co-localizes with HIV-1 integrase, a key component of PIC. Taken together, our data support a model whereby ADAM15/γ-secretase processing of ADAM10 releases the ICD, which then incorporates into HIV-1 PIC to facilitate nuclear trafficking. Thus, these studies suggest ADAM10 as a novel therapeutic target for inhibiting HIV-1 prior to nuclear entry. - Highlights: • Nuclear trafficking of the HIV-1 pre-integration complex depends on ADAM10. • ADAM10 associates with HIV-1 integrase in the pre-integration complex. • HIV-1 replication depends on the expression of ADAM15 and γ-secretase. • Silencing ADAM15 or γ-secretase expression inhibits nuclear import of viral cDNA. • ADAM10 is important for HIV-1 replication in human macrophages and CD4 + T lymphocytes

  16. Wind Integration into Energy Systems with a High Share of Nuclear Power—What Are the Compromises?

    Directory of Open Access Journals (Sweden)

    Behnam Zakeri

    2015-03-01

    Full Text Available Towards low-carbon energy systems, there are countries with ongoing plans for expanding their nuclear power capacity, and simultaneously advancing the role of variable renewable energy sources (RES, namely wind and solar energy. This crossroads of capital-intensive, baseload power production and uncontrollable, intermittent RES may entail new challenges in the optimal and economic operation of power systems. This study examines this case by hourly analysis of a national-level energy system with the EnergyPLAN modeling tool, coupled with wind integration simulations (including uncertainty implemented using MATLAB. We evaluate the maximum feasible wind integration under different scenarios for nuclear power plants, energy demand, and the flexibility of energy infrastructure for a real case study (Finland. We propose wind-nuclear compromise charts to envision the impact of any mix of these two technologies on four parameters: total costs, power exchange, carbon emissions, and renewable energy integration. The results suggest that nuclear power constrains the room for maximum uptake of wind energy by a descending parabolic relationship. If nuclear power production exceeds 50% of the total power demand, wind will be unlikely to penetrate in shares over 15% of the respective demand. Moreover, we investigate the role of four flexibility options: demand side management, electrical energy storage, smart electric heating, and large-scale heat pumps (backed with thermal energy storage. Heat pumps (which are in connection with combined heat and power (CHP and district heating systems offer the highest efficiency in balancing excess power from variable RES. However, power-to-heat options offer a limited capability for absorbing excess power, as oversupply arises mainly in the periods with relatively low demand for heat. This calls for longer-term energy storage and/or other flexibility options to achieve the planned targets in wind-nuclear scenarios.

  17. Nuclear trafficking of the HIV-1 pre-integration complex depends on the ADAM10 intracellular domain

    Energy Technology Data Exchange (ETDEWEB)

    Endsley, Mark A., E-mail: maendsle@utmb.edu [Department Internal Medicine, Division of Infectious Diseases, University of Texas Medical Branch, 301 University Blvd, Galveston, TX 77555 (United States); Somasunderam, Anoma D., E-mail: asomasun@utmb.edu [Department Internal Medicine, Division of Infectious Diseases, University of Texas Medical Branch, 301 University Blvd, Galveston, TX 77555 (United States); Li, Guangyu, E-mail: LIG001@mail.etsu.edu [Department of Internal Medicine, Quillen College of Medicine, East Tennessee State University, Johnson City, TN 37614 (United States); Oezguen, Numan, E-mail: numan.oezguen@bcm.edu [Department of Pathology and Immunology, Microbiome Center, Texas Children' s Hospital, Houston, TX 77030 (United States); Thiviyanathan, Varatharasa, E-mail: Varatharasa.Thiviyanathan@uth.tmc.edu [Institute of Molecular Medicine, University of Texas Health Science Center, Houston, TX 77030 (United States); Murray, James L., E-mail: jmurray100@yahoo.com [GeneTAG Technology, Inc., 3155 Northwoods Place, Norcross, GA 30071 (United States); Rubin, Donald H., E-mail: don.h.rubin@vanderbilt.edu [Research Medicine, VA Tennessee Valley Healthcare System, 1310 24th Ave. South, Nashville, TN 37212 (United States); Departments of Medicine, Pathology, Microbiology and Immunology, Vanderbilt University School of Medicine, 1161 21st Ave South, Nashville, TN 37232 (United States); Hodge, Thomas W., E-mail: twhodge3@gmail.com [Pre-clinical and Antiviral Research, Tamir Biotechnology, Inc., 12625 High Bluff Dr., Suite 113, San Diego, CA 92130 (United States); and others

    2014-04-15

    Previously, we showed that ADAM10 is necessary for HIV-1 replication in primary human macrophages and immortalized cell lines. Silencing ADAM10 expression interrupted the HIV-1 life cycle prior to nuclear translocation of viral cDNA. Furthermore, our data indicated that HIV-1 replication depends on the expression of ADAM15 and γ-secretase, which proteolytically processes ADAM10. Silencing ADAM15 or γ-secretase expression inhibits HIV-1 replication between reverse transcription and nuclear entry. Here, we show that ADAM10 expression also supports replication in CD4{sup +} T lymphocytes. The intracellular domain (ICD) of ADAM10 associates with the HIV-1 pre-integration complex (PIC) in the cytoplasm and immunoprecipitates and co-localizes with HIV-1 integrase, a key component of PIC. Taken together, our data support a model whereby ADAM15/γ-secretase processing of ADAM10 releases the ICD, which then incorporates into HIV-1 PIC to facilitate nuclear trafficking. Thus, these studies suggest ADAM10 as a novel therapeutic target for inhibiting HIV-1 prior to nuclear entry. - Highlights: • Nuclear trafficking of the HIV-1 pre-integration complex depends on ADAM10. • ADAM10 associates with HIV-1 integrase in the pre-integration complex. • HIV-1 replication depends on the expression of ADAM15 and γ-secretase. • Silencing ADAM15 or γ-secretase expression inhibits nuclear import of viral cDNA. • ADAM10 is important for HIV-1 replication in human macrophages and CD4{sup +} T lymphocytes.

  18. Nuclear reactors in de-regulated markets: Integration between providers and customers?

    International Nuclear Information System (INIS)

    Girard, Philippe

    2006-01-01

    The deregulation of electricity markets has in most cases coincided with the end of state monopolies, where financial risks were borne by customers/citizens. Today, despite an economic advantage, nuclear power development faces two main problems: public acceptance and reticence of investors (banks, utilities shareholders). The development of electricity markets provides different financial instruments in order to hedge financial risks, but it is currently difficult to fix forward contracts for more than three to four years, and this period is insufficient for the financing of a nuclear reactor. A solution could be the evolution of nuclear providers into nuclear operators selling electricity (MWh) rather than selling nuclear capacity (MW), nuclear fuel and services. In this case, their customers would be utilities and big customers aiming to hedge a part of their supplies with long-term contracts or stakes in nuclear reactors without some nuclear constraints. (author)

  19. Fluids with highly directional attractive forces. IV. Equilibrium polymerization

    International Nuclear Information System (INIS)

    Wertheim, M.S.

    1986-01-01

    The author investigates approximation methods for systems of molecules interacting by core repulsion and highly directional attraction due to several attraction sites. The force model chosen imitates a chemical bond by providing for bond saturation when binding occurs. The dense fluid is an equilibrium mixture of s-mers with mutual repulsion. The author uses a previously derived reformulation of statistical thermodynamics in which the particle species are monomeric units with a specified set of attraction sites bonded. Thermodynamic perturbation theory (TPT) and integral equations of two types are derived. The use of TPT is illustrated by explicit calculation for a molecular model with two attraction sites capable of forming chain and ring polymers. Successes and defects of TPT are discussed. The integral equations for pair correlations between particles of specified bonding include calculation of self-consistent densities of species. Methods of calculating thermodynamic properties from the solutions of integral equations are given

  20. Differences in Approach between Nuclear and Conventional Seismic Standards with regard to Hazard Definition - CSNI Integrity And Ageing Working Group

    International Nuclear Information System (INIS)

    Djaoudi, Ali; Labbe, Pierre; Murphy, Andrew; Kitada, Yoshio

    2008-01-01

    The Committee on the safety of Nuclear Installations (CSNI) of the OECD-NEA co-ordinates the NEA activities related to maintaining and advancing the scientific and technological knowledge base of the safety of nuclear installations. The Integrity and Ageing of Components and Structures Working Group of the CSNI is responsible for work related to the development and use of methods, data and information to assess the behaviour of materials and structures. It has three sub-groups, dealing with the integrity of metal components and structures, ageing of concrete structures, and the seismic behaviour of structures. The CSNI, at its meeting in June 2003, agreed to initiate an activity aimed to identify any difference between nuclear and non-nuclear conventional standards and their potential significance with regard to seismic hazards and design methods. There was a perception, mainly in some of the European countries that nuclear seismic hazard and design standards may be lagging behind developments in similar standards for conventional facilities. Adequate answer to such perception, need the examination of the following aspects and their significance on the seismic assessment of structures and components: - The safety philosophy behind the seismic nuclear and conventional standards. - The differences in approach regarding the seismic hazard definition. - The difference in approach regarding the design and the methods of analysis. These topics are examined in this report. Appendices A to H of this report contain a brief description of the conventional and the nuclear approaches in the NEA member countries: Belgium, Canada, Czech Republic, Germany, Japan, South Korea, Spain,and USA. The following general conclusions can be drawn: - The approach adopted by the nuclear seismic standards is more conservative and more reliable (in particular for meeting the continued operation criteria) than t