WorldWideScience

Sample records for technology facilities risk

  1. Fact Sheet for Friction Materials Manufacturing Facilities Residual Risk and Technology Review

    Science.gov (United States)

    proposed amendments to the National Emission Standards for Hazardous Air Pollutants (NESHAP) for Friction Materials Manufacturing Facilities to address the results of the residual risk and technology review

  2. Armament Technology Facility (ATF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Armament Technology Facility is a 52,000 square foot, secure and environmentally-safe, integrated small arms and cannon caliber design and evaluation facility....

  3. Technological risks

    International Nuclear Information System (INIS)

    Klinke, A.; Renn, O.

    1998-01-01

    The empirical part about the technological risks deals with different technologies: nuclear energy, early warning systems of nuclear weapons and NBC-weapons, and electromagnetic fields. The potential of damage, the contemporary management strategies and the relevant characteristics will be described for each technology: risks of nuclear energy; risks of early warning systems of nuclear weapons and NBC-weapons; risks of electromagnetic fields. (authors)

  4. Technological risks

    Energy Technology Data Exchange (ETDEWEB)

    Klinke, A.; Renn, O. [Center of Technology Assessment in Baden-Wuerttemberg, Stuttgart (Germany)

    1998-07-01

    The empirical part about the technological risks deals with different technologies: nuclear energy, early warning systems of nuclear weapons and NBC-weapons, and electromagnetic fields. The potential of damage, the contemporary management strategies and the relevant characteristics will be described for each technology: risks of nuclear energy; risks of early warning systems of nuclear weapons and NBC-weapons; risks of electromagnetic fields. (authors)

  5. Technological risk

    Energy Technology Data Exchange (ETDEWEB)

    Dierkes, M; Coppock, R; Edwards, S

    1980-01-01

    The book begins with brief statements from representatives of political organizations. Part II presents an overview of the discussion about the control and management of technological progress. Parts III and IV discuss important elements in citizens' perception of technological risks and the development of consensus on how to deal with them. In Part V practical problems in the application of risk assessment and management, and in Part VI additional points are summarized.

  6. Technological risk

    International Nuclear Information System (INIS)

    Dierkes, M.; Coppock, R.; Edwards, S.

    1980-01-01

    The book begins with brief statements from representatives of political organizations. Part II presents an overview of the discussion about the control and management of technological progress. Parts III and IV discuss important elements in citizens' perception of technological risks and the development of consensus on how to deal with them. In Part V practical problems in the application of risk assessment and management, and in Part VI additional points are summarized. (DG)

  7. Facility decontamination technology workshop

    International Nuclear Information System (INIS)

    1980-10-01

    Purpose of the meeting was to provide a record of experience at nuclear facilities, other than TMI-2, of events and incidents which have required decontamination and dose reduction activities, and to furnish GPU and others involved in the TMI-2 cleanup with the results of that decontamination and dose reduction technology. Separate abstracts were prepared for 24 of the 25 papers; the remaining paper had been previously abstracted

  8. Facility decontamination technology workshop

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-10-01

    Purpose of the meeting was to provide a record of experience at nuclear facilities, other than TMI-2, of events and incidents which have required decontamination and dose reduction activities, and to furnish GPU and others involved in the TMI-2 cleanup with the results of that decontamination and dose reduction technology. Separate abstracts were prepared for 24 of the 25 papers; the remaining paper had been previously abstracted. (DLC)

  9. Carbon Fiber Technology Facility (CFTF)

    Data.gov (United States)

    Federal Laboratory Consortium — Functionally within the MDF, ORNL operates DOE’s unique Carbon Fiber Technology Facility (CFTF)—a 42,000 ft2 innovative technology facility and works with leading...

  10. Technology Development Facility (TDF)

    International Nuclear Information System (INIS)

    Doggett, J.N.

    1982-01-01

    We have been studying small, driven, magnetic-mirror-based fusion reactors for the Technology Development Facility (TDF), that will test fusion reactor materials, components, and subsystems. Magnetic mirror systems are particularly interesting for this application because of their inherent steady-state operation, potentially high neutron wall loading, and relatively small size. Our design is a tandem mirror device first described by Fowler and Logan, based on the physics of the TMX experiments at Lawrence Livermore National Laboratory (LLNL). The device produces 20 MW of fusion power with a first-wall, uncollided 14-MeV neutron flux of 1.4 MW/m 2 on an area of approximately 8 m 2 , while consuming approximately 250 MW of electrical power. The work was done by a combined industrial-laboratory-university group

  11. Standoff Detection Technology Evaluation Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Standoff Detection Technology Evaluation facility is the only one of its kind in the country and allows researchers to release a known amount of material while...

  12. Underground Facilities, Technological Challenges

    CERN Document Server

    Spooner, N

    2010-01-01

    This report gives a summary overview of the status of international under- ground facilities, in particular as relevant to long-baseline neutrino physics and neutrino astrophysics. The emphasis is on the technical feasibility aspects of creating the large underground infrastructures that will be needed in the fu- ture to house the necessary detectors of 100 kton to 1000 kton scale. There is great potential in Europe to build such a facility, both from the technical point of view and because Europe has a large concentration of the necessary engi- neering and geophysics expertise. The new LAGUNA collaboration has made rapid progress in determining the feasibility for a European site for such a large detector. It is becoming clear in fact that several locations are technically fea- sible in Europe. Combining this with the possibility of a new neutrino beam from CERN suggests a great opportunity for Europe to become the leading centre of neutrino studies, combining both neutrino astrophysics and neutrino beam stu...

  13. Uncertainties in risk assessment at USDOE facilities

    Energy Technology Data Exchange (ETDEWEB)

    Hamilton, L.D.; Holtzman, S.; Meinhold, A.F.; Morris, S.C.; Rowe, M.D.

    1994-01-01

    The United States Department of Energy (USDOE) has embarked on an ambitious program to remediate environmental contamination at its facilities. Decisions concerning cleanup goals, choices among cleanup technologies, and funding prioritization should be largely risk-based. Risk assessments will be used more extensively by the USDOE in the future. USDOE needs to develop and refine risk assessment methods and fund research to reduce major sources of uncertainty in risk assessments at USDOE facilities. The terms{open_quote} risk assessment{close_quote} and{open_quote} risk management{close_quote} are frequently confused. The National Research Council (1983) and the United States Environmental Protection Agency (USEPA, 1991a) described risk assessment as a scientific process that contributes to risk management. Risk assessment is the process of collecting, analyzing and integrating data and information to identify hazards, assess exposures and dose responses, and characterize risks. Risk characterization must include a clear presentation of {open_quotes}... the most significant data and uncertainties...{close_quotes} in an assessment. Significant data and uncertainties are {open_quotes}...those that define and explain the main risk conclusions{close_quotes}. Risk management integrates risk assessment information with other considerations, such as risk perceptions, socioeconomic and political factors, and statutes, to make and justify decisions. Risk assessments, as scientific processes, should be made independently of the other aspects of risk management (USEPA, 1991a), but current methods for assessing health risks are based on conservative regulatory principles, causing unnecessary public concern and misallocation of funds for remediation.

  14. Uncertainties in risk assessment at USDOE facilities

    International Nuclear Information System (INIS)

    Hamilton, L.D.; Holtzman, S.; Meinhold, A.F.; Morris, S.C.; Rowe, M.D.

    1994-01-01

    The United States Department of Energy (USDOE) has embarked on an ambitious program to remediate environmental contamination at its facilities. Decisions concerning cleanup goals, choices among cleanup technologies, and funding prioritization should be largely risk-based. Risk assessments will be used more extensively by the USDOE in the future. USDOE needs to develop and refine risk assessment methods and fund research to reduce major sources of uncertainty in risk assessments at USDOE facilities. The terms open-quote risk assessment close-quote and open-quote risk management close-quote are frequently confused. The National Research Council (1983) and the United States Environmental Protection Agency (USEPA, 1991a) described risk assessment as a scientific process that contributes to risk management. Risk assessment is the process of collecting, analyzing and integrating data and information to identify hazards, assess exposures and dose responses, and characterize risks. Risk characterization must include a clear presentation of open-quotes... the most significant data and uncertainties...close quotes in an assessment. Significant data and uncertainties are open-quotes...those that define and explain the main risk conclusionsclose quotes. Risk management integrates risk assessment information with other considerations, such as risk perceptions, socioeconomic and political factors, and statutes, to make and justify decisions. Risk assessments, as scientific processes, should be made independently of the other aspects of risk management (USEPA, 1991a), but current methods for assessing health risks are based on conservative regulatory principles, causing unnecessary public concern and misallocation of funds for remediation

  15. Tandem mirror technology demonstration facility

    Energy Technology Data Exchange (ETDEWEB)

    1983-10-01

    This report describes a facility for generating engineering data on the nuclear technologies needed to build an engineering test reactor (ETR). The facility, based on a tandem mirror operating in the Kelley mode, could be used to produce a high neutron flux (1.4 MW/M/sup 2/) on an 8-m/sup 2/ test area for testing fusion blankets. Runs of more than 100 h, with an average availability of 30%, would produce a fluence of 5 mW/yr/m/sup 2/ and give the necessary experience for successful operation of an ETR.

  16. Tandem mirror technology demonstration facility

    International Nuclear Information System (INIS)

    1983-10-01

    This report describes a facility for generating engineering data on the nuclear technologies needed to build an engineering test reactor (ETR). The facility, based on a tandem mirror operating in the Kelley mode, could be used to produce a high neutron flux (1.4 MW/M 2 ) on an 8-m 2 test area for testing fusion blankets. Runs of more than 100 h, with an average availability of 30%, would produce a fluence of 5 mW/yr/m 2 and give the necessary experience for successful operation of an ETR

  17. DECONTAMINATION TECHNOLOGIES FOR FACILITY REUSE

    International Nuclear Information System (INIS)

    Bossart, Steven J.; Blair, Danielle M.

    2003-01-01

    As nuclear research and production facilities across the U.S. Department of Energy (DOE) nuclear weapons complex are slated for deactivation and decommissioning (D and D), there is a need to decontaminate some facilities for reuse for another mission or continued use for the same mission. Improved technologies available in the commercial sector and tested by the DOE can help solve the DOE's decontamination problems. Decontamination technologies include mechanical methods, such as shaving, scabbling, and blasting; application of chemicals; biological methods; and electrochemical techniques. Materials to be decontaminated are primarily concrete or metal. Concrete materials include walls, floors, ceilings, bio-shields, and fuel pools. Metallic materials include structural steel, valves, pipes, gloveboxes, reactors, and other equipment. Porous materials such as concrete can be contaminated throughout their structure, although contamination in concrete normally resides in the top quarter-inch below the surface. Metals are normally only contaminated on the surface. Contamination includes a variety of alpha, beta, and gamma-emitting radionuclides and can sometimes include heavy metals and organic contamination regulated by the Resource Conservation and Recovery Act (RCRA). This paper describes several advanced mechanical, chemical, and other methods to decontaminate structures, equipment, and materials

  18. Investigative report, science committee of Aggregate corporation Radiological technologist society of the Oita prefecture. Questionnaires research on security control of department of radiological technology of medical facilities in the Oita prefecture. The second report. Research on high risk incident measures

    International Nuclear Information System (INIS)

    Eto, Yoshihiro; Mano, Isao; Takagi, Ikuya; Murakami, Yasunori; Sueyoshi, Seiji; Yoshimoto, Asahi

    2007-01-01

    Oita association of radiological technologists carried out the questionnaires about the measures against high lisk incidental in department of radiological technology at the medical facilities in Oita. We distributed the questionnaire to 102 facilities, which are worked by the technologists (member), and got response from 91 facilities (89%). Research contents are Patient verification method'' ''Input and verification of patient attribute'' ''Infection in hospital'' ''Stumbles and falls of patient'' Contrast enhancement CT'' ''Something related to pacemaker'' ''MRI inspection and the magnetic substance'' ''Remedy mistake'' and ''Risk management''. The Result, Low level recognition contents of medical accident measures are ''Contrast enhancement CT'' ''Stumbles and falls of patient'' Risk management of department of radiological technology''. (author)

  19. Empowering Facilities Teams through Technology

    Science.gov (United States)

    Cormier, Scott

    2013-01-01

    Facilities departments at colleges and universities are facing the same challenge: how not to do just the most projects, but also the right projects with the limited funds they are given. In order to make the best decisions, they need more control over the capital planning process, which requires accurate, current facility condition data. Each…

  20. Information and Communication Technology (ICT) Facilities and ...

    African Journals Online (AJOL)

    The library is at the centre of academic activities in every university. It is being transformed from the traditional operations to a service organization with the use of information and communication technology facilities. In this study, the researchers x-rayed ICT facilities and the skills level of the staff in the three universities in ...

  1. Tokamak Engineering Technology Facility scoping study

    Energy Technology Data Exchange (ETDEWEB)

    Stacey, W.M. Jr.; Abdou, M.A.; Bolta, C.C.

    1976-03-01

    A scoping study for a Tokamak Engineering Technology Facility (TETF) is presented. The TETF is a tokamak with R = 3 m and I/sub p/ = 1.4 MA based on the counterstreaming-ion torus mode of operation. The primary purpose of TETF is to demonstrate fusion technologies for the Experimental Power Reactor (EPR), but it will also serve as an engineering and radiation test facility. TETF has several technological systems (e.g., superconducting toroidal-field coil, tritium fuel cycle, impurity control, first wall) that are prototypical of EPR.

  2. Tokamak Engineering Technology Facility scoping study

    International Nuclear Information System (INIS)

    Stacey, W.M. Jr.; Abdou, M.A.; Bolta, C.C.

    1976-03-01

    A scoping study for a Tokamak Engineering Technology Facility (TETF) is presented. The TETF is a tokamak with R = 3 m and I/sub p/ = 1.4 MA based on the counterstreaming-ion torus mode of operation. The primary purpose of TETF is to demonstrate fusion technologies for the Experimental Power Reactor (EPR), but it will also serve as an engineering and radiation test facility. TETF has several technological systems (e.g., superconducting toroidal-field coil, tritium fuel cycle, impurity control, first wall) that are prototypical of EPR

  3. On-orbit technology experiment facility definition

    Science.gov (United States)

    Russell, Richard A.; Buchan, Robert W.; Gates, Richard M.

    1988-01-01

    A study was conducted to identify on-orbit integrated facility needs to support in-space technology experiments on the Space Station and associated free flyers. In particular, the first task was to examine the proposed technology development missions (TDMX's) from the model mission set and other proposed experimental facilities, both individually and by theme, to determine how and if the experiments might be combined, what equipment might be shared, what equipment might be used as generic equipment for continued experimentation, and what experiments will conflict with the conduct of other experiments or Space Station operations. Then using these results, to determine on-orbit facility needs to optimize the implementation of technology payloads. Finally, to develop one or more scenarios, design concepts, and outfitting requirements for implementation of onboard technology experiments.

  4. International Facility for Food Irradiation Technology

    International Nuclear Information System (INIS)

    Farkas, J.

    1982-01-01

    The International Facility for Food Irradiation Technology (IFFIT) was set up in November 1978 for a period of five years at the Pilot Plant for Food Irradiation, Wageningen, The Netherlands under an Agreement between the FAO, IAEA and the Ministry of Agriculture and Fisheries of the Government of the Netherlands. Under this Agreement, the irradiation facilities, office space and services of the Pilot Plant for Food Irradiation are put at IFFIT's disposal. Also the closely located Research Foundation, ITAL, provides certain facilities and laboratory services within the terms of the Agreement. The FAO and IAEA contribute US-Dollar 25,000. Annually for the duration of IFFIT. (orig.) [de

  5. The risks of technology

    International Nuclear Information System (INIS)

    Hauptmanns, U.; Werner, W.; Herttrich, M.

    1987-01-01

    The book presents a complete survey of the methods and procedures applied for risk assessment, referring in particular to the field of nuclear engineering, but dealing also with risk assessment in the sector of the chemical industry and of the power industry, comparing the risks of various technologies for energy production. The material presented shows that a risk assessment study requires information and knowledge from a great variety of subject fields, evaluating and merging the information collected into a complete survey being the main task of risk assessment. It also becomes clear that despite the strong commitment to research in this field, there still remain unresolved problems and phenomena, so that risk assessment bears a certain degree of uncertainty. The results and the mutual connections are represented in words only, so that the reader can do without mathematical knowledge. Many studies and their results are presented, and their explanation in the overall framework allows insight into the connections and an evaluation of usefulness. The status report on risk assessment prepared in August 1984 by the GRS (Society for Reactor Safety) on behalf of the Federal Ministry of the Interior, has been taken as a basis for this book which consists of many individual contributions. (orig./HP) With 45 figs [de

  6. Decommissioning of reactor facilities (2). Required technology

    International Nuclear Information System (INIS)

    Yanagihara, Satoshi

    2014-01-01

    Decommissioning of reactor facilities was planned to perform progressive dismantling, decontamination and radioactive waste disposal with combination of required technology in a safe and economic way. This article outlined required technology for decommissioning as follows: (1) evaluation of kinds and amounts of residual radioactivity of reactor facilities with calculation and measurement, (2) decontamination technology of metal components and concrete structures so as to reduce worker's exposure and production of radioactive wastes during dismantling, (3) dismantling technology of metal components and concrete structures such as plasma arc cutting, band saw cutting and controlled demolition with mostly remote control operation, (3) radioactive waste disposal for volume reduction and reuse, and (4) project management of decommissioning for safe and rational work to secure reduction of worker's exposure and prevent the spreading of contamination. (T. Tanaka)

  7. Estimating Fire Risks at Industrial Nuclear Facilities

    International Nuclear Information System (INIS)

    Coutts, D.A.

    1999-01-01

    The Savannah River Site (SRS) has a wide variety of nuclear production facilities that include chemical processing facilities, machine shops, production reactors, and laboratories. Current safety documentation must be maintained for the nuclear facilities at SRS. Fire Risk Analyses (FRAs) are used to support the safety documentation basis. These FRAs present the frequency that specified radiological and chemical consequences will be exceeded. The consequence values are based on mechanistic models assuming specific fire protection features fail to function as designed

  8. Methodology and technology of decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    1986-01-01

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

  9. Decontamination Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Oh, Won Zin; Jung, Chong Hun; Choi, Wang Kyu; Won, Hui Jun; Kim, Gye Nam

    2004-02-01

    Technology development of surface decontamination in the uranium conversion facility before decommissioning, technology development of component decontamination in the uranium conversion facility after decommissioning, uranium sludge treatment technology development, radioactive waste soil decontamination technology development at the aim of the temporary storage soil of KAERI, Optimum fixation methodology derivation on the soil and uranium waste, and safety assessment methodology development of self disposal of the soil and uranium waste after decontamination have been performed in this study. The unique decontamination technology applicable to the component of the nuclear facility at room temperature was developed. Low concentration chemical decontamination technology which is very powerful so as to decrease the radioactivity of specimen surface under the self disposal level was developed. The component decontamination technology applicable to the nuclear facility after decommissioning by neutral salt electro-polishing was also developed. The volume of the sludge waste could be decreased over 80% by the sludge waste separation method by water. The electrosorption method on selective removal of U(VI) to 1 ppm of unrestricted release level using the uranium-containing lagoon sludge waste was tested and identified. Soil decontamination process and equipment which can reduce the soil volume over 90% were developed. A pilot size of soil decontamination equipment which will be used to development of real scale soil decontamination equipment was designed, fabricated and demonstrated. Optimized fixation methodology on soil and uranium sludge was derived from tests and evaluation of the results. Safety scenario and safety evaluation model were development on soil and uranium sludge aiming at self disposal after decontamination

  10. Communication in reducing facility siting risk

    International Nuclear Information System (INIS)

    Bisconti, A.S.

    1992-01-01

    Today, social considerations are as important as technical ones in siting new nuclear facilities. Siting any industrial facility has become extremely difficult in this era of not in my backyard (NIMBY). Even if NIMBY does not arise locally, well-organized national opposition groups can be counted on to step in to fan the flames, especially when the industrial facility has to do with anything nuclear. It is now generally recognized that the greatest risk of failure for new nuclear facilities is not technical but social. Applying lessons gained from past experience and social science research can help reduce that risk. From these lessons, six principles for public interaction and communication stand out: (1) create goodwill now; (2) involve the community early; (3) establish the need; (4) communicate controls, not risk; (5) avoid jargon; (6) understand your public

  11. Scientific and Technological Facilities in CIEMAT

    International Nuclear Information System (INIS)

    Vaquero Ortiz, E. M.; Cascante Díaz, E.; González Pineda, L. M.

    2015-01-01

    The precise knowledge of the available Resources in an Organization, regardless the work it carries out, is an essential strategic enabler to achieve its goals. Material Resources are part of the resources in an organization, The “Material Resources” expression includes a wide span of elements, because a Material Resource, as a generic concept, is each and every specific physical mean, utilized to get any of the Organization objectives. In CIEMAT, as Public Research Agency, its Material Resources consist of its scientific and technological facilities. These resources are the basis of this Agency numerous amount of technical capabilities, allowing it to carry out its research, development and innovation activity to transfer its results to the society later. This report is a summary on CIEMAT scientific and technological facilities, whose spread can help to show its scientific and technological capabilities, to enable the execution of a wide variety of projects and to open new external cooperation channels. Outstanding among these facilities are two “Unique Scientific and Technological Infrastructures” (ICTS) and the Ionizing Radiations Metrology Laboratory (LMRI) which is the Spanish National Standards Laboratory for ionising radiations.

  12. Radiation risk and its estimation for nuclear facilities

    International Nuclear Information System (INIS)

    Krueger, F.W.

    1979-01-01

    The level of knowledge achieved in estimating risks due to the operation of nuclear facilities is discussed. In this connection it is analyzed to what extent risk estimates may be used for establishing requirements for facilities and measures of radiation protection and accident prevention. At present, estimates of risks are subject to great uncertainties. However, the results attainable already permit to discern the causes of possible accidents and to develop effective measures for preventing such accidents. For the time being (and maybe in principle) risk estimation is possible only with more or less arbitrary premises. Within the foreseeable future, cost-benefit comparisons cannot compensate for discretionary decisions in establishing requirements for measures of radiation protection and accident prevention. In preparing such decisions based on experience, expert opinions, political and socio-economic reflections and views, comparison of the risk of novel technologies with existing ones or accepted risks may be a useful means. (author)

  13. Use of probabilistic risk assessment in fuel cycle facilities

    International Nuclear Information System (INIS)

    Gonzalez, Felix; Gonzalez, Michelle; Wagner, Brian

    2013-01-01

    As expressed in its Policy Statement on the Use of Probabilistic Risk Assessment (PRA) Methods in Nuclear Regulatory Activities, the U.S Nuclear Regulatory Commission has been working for decades to increase the use of PRA technology in its regulatory activities. Since the policy statement was issued in 1995, PRA has become a core component of the nuclear power plant (NPP) licensing and oversight processes. In the last several years, interest has increased in PRA technologies and their possible application to other areas including, but not limited to, spent fuel handling, fuel cycle facilities, reprocessing facilities, and advanced reactors. This paper describes the application of PRA technology currently used in NPPs and its application in other areas such as fuel cycle facilities and advanced reactors. It describes major challenges that are being faced in the application of PRA into new technical areas and possible ways to resolve them. (authors)

  14. Emerging Technological Risk Underpinning the Risk of Technology Innovation

    CERN Document Server

    Anderson, Stuart

    2012-01-01

    Classes of socio-technical hazards allow a characterization of the risk in technology innovation and clarify the mechanisms underpinning emergent technological risk. Emerging Technological Risk provides an interdisciplinary account of risk in socio-technical systems including hazards which highlight: ·         How technological risk crosses organizational boundaries, ·         How technological trajectories and evolution develop from resolving tensions emerging between social aspects of organisations and technologies and ·         How social behaviour shapes, and is shaped by, technology. Addressing an audience from a range of academic and professional backgrounds, Emerging Technological Risk is a key source for those who wish to benefit from a detail and methodical exposure to multiple perspectives on technological risk. By providing a synthesis of recent work on risk that captures the complex mechanisms that characterize the emergence of risk in technology innovation, Emerging Tec...

  15. Scientific and Technological Facilities in CIEMAT

    International Nuclear Information System (INIS)

    Vaquero Ortiz, E. M.

    2012-01-01

    The precise knowledge of the available Resources in an Organization, regardless the work it carries out, is an essential strategic enable to achieve its goals. Material Resources are part of the resources in an organization, The Material Resources expression includes a wide span of elements, because a Material Resource, as a generic concept, is each and every specific physical mean, utilised to get any of the Organization objectives. In case of CIEMAT, as Public Research Agency, its Material Resources consists of its scientific and technological facilities. These resources are the basis of this Agency numerous amount of technical capabilities, allowing it to carry out its research, development and innovation activity to transfer its results to the society later. This report is a summary on CIEMAT scientific and technological facilities, whose spread can help to show its scientific and technological capabilities, to enable the execution of a wide variety of projects and to open new external cooperation channels. In that list its possible to find the two Unique Scientific and Technological Infrastructures (ICTS) in Spain which are hold by CIEMAT and the Ionizing Radiations Metrology Laboratory (LMRI) which is the Spanish National Standards Laboratory for ionising radiations. (Author)

  16. High-risk facilities. Emergency management in nuclear, chemical and hazardous waste facilities

    International Nuclear Information System (INIS)

    Kloepfer, Michael

    2012-01-01

    The book on emergency management in high-risk facilities covers the following topics: Change in the nuclear policy, risk management of high-risk facilities as a constitutional problem - emergency management in nuclear facilities, operational mechanisms of risk control in nuclear facilities, regulatory surveillance responsibilities for nuclear facilities, operational mechanism of the risk control in chemical plants, regulatory surveillance responsibilities for chemical facilities, operational mechanisms of the risk control in hazardous waste facilities, regulatory surveillance responsibilities for hazardous waste facilities, civil law consequences in case of accidents in high-risk facilities, criminal prosecution in case of accidents in high-risk facilities, safety margins as site risk for emission protection facilities, national emergency management - strategic emergency management structures, warning and self-protection of the public in case of CBRN hazards including aspects of the psych-social emergency management.

  17. Methodology for analyzing risk at nuclear facilities

    International Nuclear Information System (INIS)

    Yoo, Hosik; Lee, Nayoung; Ham, Taekyu; Seo, Janghoon

    2015-01-01

    Highlights: • A new methodology for evaluating the risk at nuclear facilities was developed. • Five measures reflecting all factors that should be concerned to assess risk were developed. • The attributes on NMAC and nuclear security culture are included as attributes for analyzing. • The newly developed methodology can be used to evaluate risk of both existing facility and future nuclear system. - Abstract: A methodology for evaluating risks at nuclear facilities is developed in this work. A series of measures is drawn from the analysis of factors that determine risks. Five measures are created to evaluate risks at nuclear facilities. These include the legal and institutional framework, material control, physical protection system effectiveness, human resources, and consequences. Evaluation attributes are developed for each measure and specific values are given in order to calculate the risk value quantitatively. Questionnaires are drawn up on whether or not a state has properly established a legal and regulatory framework (based on international standards). These questionnaires can be a useful measure for comparing the status of the physical protection regime between two countries. Analyzing an insider threat is not an easy task and no methodology has been developed for this purpose. In this study, attributes that could quantitatively evaluate an insider threat, in the case of an unauthorized removal of nuclear materials, are developed by adopting the Nuclear Material Accounting & Control (NMAC) system. The effectiveness of a physical protection system, P(E), could be analyzed by calculating the probability of interruption, P(I), and the probability of neutralization, P(N). In this study, the Tool for Evaluating Security System (TESS) code developed by KINAC is used to calculate P(I) and P(N). Consequence is an important measure used to analyze risks at nuclear facilities. This measure comprises radiological, economic, and social damage. Social and

  18. Image processing technology for nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Jong Min; Lee, Yong Beom; Kim, Woong Ki; Park, Soon Young

    1993-05-01

    Digital image processing technique is being actively studied since microprocessors and semiconductor memory devices have been developed in 1960's. Now image processing board for personal computer as well as image processing system for workstation is developed and widely applied to medical science, military, remote inspection, and nuclear industry. Image processing technology which provides computer system with vision ability not only recognizes nonobvious information but processes large information and therefore this technique is applied to various fields like remote measurement, object recognition and decision in adverse environment, and analysis of X-ray penetration image in nuclear facilities. In this report, various applications of image processing to nuclear facilities are examined, and image processing techniques are also analysed with the view of proposing the ideas for future applications. (Author)

  19. Risk assessment of LPG automotive refuelling facilities

    Energy Technology Data Exchange (ETDEWEB)

    Melchers, R.E. [University of Newcastle, Newcastle (Australia). Dept. of Civil, Surveying and Enviromental Engineering; Feutrill, W.R. [Wesfarmers Kleenheat Gas Pty. Ltd., Perth (Australia)

    2001-12-01

    Quantified risk analysis (QRA) was used for the revision of regulatory separation distances associated with medium size liquefied petroleum gas (LPG) refuelling facilities used in automotive service (gas) stations. Typically these facilities consist of a 7.5 kl pressure vessel, pump, pipework, dispensing equipment and safety equipment. Multi-tank installations are relatively uncommon. This paper describes the hazard scenarios considered, the risk analysis procedure and the selection and application of data for initiating events and for rates of failure of mechanical components and of the pressure vessel. Human errors and intervention possibilities were also considered. Because of the inapplicability of established consequence models and the relatively small scale of the facilities, a number of tests were performed to estimate flame length, flame impingement effects, ignition probabilities and the effectiveness of screening devices. (author)

  20. Health at risk in immigration detention facilities

    Directory of Open Access Journals (Sweden)

    Ioanna Kotsioni

    2013-09-01

    Full Text Available Since 2004 Médecins Sans Frontières (MSF has provided medical and psychosocial support for asylum seekers and migrants held in different immigration detention facilities across Europe (in Greece, Malta, Italy and Belgium where the life, health and human dignity of vulnerable people are being put at risk.

  1. Man, technology and risk

    Energy Technology Data Exchange (ETDEWEB)

    Renn, O

    1981-06-01

    Using the instruments of empirical social sciences, a cross-section study was conducted comprising experiments on qualitative risk characteristics, in-depth interviews on mechanisms of risk perception and representative surveys of the public on technical risk sources, in particular with regard to nuclear energy. The results of these studies show that person-related expectations in respect of risk consequences, the possibility of personal influencing control, the severeness of risk consequences and one's own risk propensity play a significant role in the evaluation of risks. (Translated from German, original report Juel-Spez--67).

  2. Agricultural Technology, Risk, and Gender

    DEFF Research Database (Denmark)

    Arndt, Channing; Tarp, Finn

    2000-01-01

    Interactions between agricultural technology improvements, risk-reducing behavior, and gender roles in agricultural production in Mozambique are examined. The analysis employs a computable general equilibrium (CGE) model that explicitly incorporates key features of the economy. These include......: detailed accounting of marketing margins, home consumption, risk, and gender roles in agricultural production. Our results show that agricultural technology improvements benefit both male and female occupants of rural households. Due to economic interactions, agricultural technology improvements...

  3. Managing highly flexible facilities: an essential complementary asset at risk

    NARCIS (Netherlands)

    Tierney, Robert; Tierney, R.; Groen, Arend J.; Harms, Rainer; Luizink, M.; Hetherington, D.; Steward, H.; Walsh, Steven Thomas; Linton, Jonathan; Linton, J.D.

    2012-01-01

    Purpose: Twenty first century problems are increasingly being addressed by multi technology solutions developed by regional entrepreneurial and intreprepreneurial innovators. However, they require an expensive new type of fabrication facility. Multiple technology production facilities (MTPF) have

  4. Risk assessment of tailings facility dam failure

    OpenAIRE

    Hadzi-Nikolova, Marija; Mirakovski, Dejan; Stefanova, Violeta

    2011-01-01

    This paper presents the consequences of tailings facility dam failure and therefore the needs for its risk assessment. Tailings are fine-grained wastes of the mining industry, output as slurries, due to mixing with water during mineral processing. Tailings dams vary a lot as it is affected by: tailings characteristics and mill output, site characteristics as: topography, hydrology, geology, groundwater, seismicity and available material and disposal methods. The talings which accumulat...

  5. Managing information technology security risk

    Science.gov (United States)

    Gilliam, David

    2003-01-01

    Information Technology (IT) Security Risk Management is a critical task for the organization to protect against the loss of confidentiality, integrity and availability of IT resources. As systems bgecome more complex and diverse and and attacks from intrusions and malicious content increase, it is becoming increasingly difficult to manage IT security risk. This paper describes a two-pronged approach in addressing IT security risk and risk management in the organization: 1) an institutional enterprise appraoch, and 2) a project life cycle approach.

  6. Screening Level Risk Assessment for the New Waste Calcining Facility

    Energy Technology Data Exchange (ETDEWEB)

    M. L. Abbott; K. N. Keck; R. E. Schindler; R. L. VanHorn; N. L. Hampton; M. B. Heiser

    1999-05-01

    This screening level risk assessment evaluates potential adverse human health and ecological impacts resulting from continued operations of the calciner at the New Waste Calcining Facility (NWCF) at the Idaho Nuclear Technology and Engineering Center (INTEC), Idaho National Engineering and Environmental Laboratory (INEEL). The assessment was conducted in accordance with the Environmental Protection Agency (EPA) report, Guidance for Performing Screening Level Risk Analyses at Combustion Facilities Burning Hazardous Waste. This screening guidance is intended to give a conservative estimate of the potential risks to determine whether a more refined assessment is warranted. The NWCF uses a fluidized-bed combustor to solidify (calcine) liquid radioactive mixed waste from the INTEC Tank Farm facility. Calciner off volatilized metal species, trace organic compounds, and low-levels of radionuclides. Conservative stack emission rates were calculated based on maximum waste solution feed samples, conservative assumptions for off gas partitioning of metals and organics, stack gas sampling for mercury, and conservative measurements of contaminant removal (decontamination factors) in the off gas treatment system. Stack emissions were modeled using the ISC3 air dispersion model to predict maximum particulate and vapor air concentrations and ground deposition rates. Results demonstrate that NWCF emissions calculated from best-available process knowledge would result in maximum onsite and offsite health and ecological impacts that are less then EPA-established criteria for operation of a combustion facility.

  7. Structuring for technology risk

    International Nuclear Information System (INIS)

    Klapper, M.

    1993-01-01

    The Colver Power Project in Cambria County, PA, looked good in nearly all aspects, but lenders had concerns about startup problems encountered by earlier waste coal circulating fluidized bed projects. Nevertheless, a closer look at the operating history of the earlier plants showed possible risks could be handled

  8. Design, Evaluation and Test Technology Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The mission of this facility, which is composed of numerous specialized facilities, is to provide capabilities to simulate a wide range of environments for component...

  9. Effect of Information Communication Technology Facilities on ...

    African Journals Online (AJOL)

    This study examined the effect of ICT facilities on students' performance by comparing ... The comparison was conducted using subtests of English language and ... ICT facilities in all secondary schools to enhance teaching and learning.

  10. Risk management activities at the DOE Class A reactor facilities

    International Nuclear Information System (INIS)

    Sharp, D.A.; Hill, D.J.; Linn, M.A.; Atkinson, S.A.; Hu, J.P.

    1993-01-01

    The probabilistic risk assessment (PRA) and risk management group of the Association for Excellence in Reactor Operation (AERO) develops risk management initiatives and standards to improve operation and increase safety of the DOE Class A reactor facilities. Principal risk management applications that have been implemented at each facility are reviewed. The status of a program to develop guidelines for risk management programs at reactor facilities is presented

  11. Environmental risk assessment for start-up of a new consolidated maintenance facility

    Energy Technology Data Exchange (ETDEWEB)

    Heubach, J.G.; Wise, J.A.

    1992-10-01

    This paper summarizes a case study of a risk assessment for a consolidated maintenance facility (CMF). An interdisciplinary team was formed to identify and evaluate showstopper'' risks which could delay or prevent ontime, safe, and economical operation of a CMF and to recommend ways to mitigate the risks. The risk assessment was constrained by time, information, incomplete plans and facilities, and a concomitant major transition in manufacturing process, organization, and technology. Working within these constraints, the team integrated convergent findings into estimates of high, medium, and low risks based on the subjective likelihood of occurrence and predicted consequences of potential hazard events. The team also made risk-reduction recommendations for facility detail design and production start-up. The findings and recommendations reported in this study focus on risks related to environmental design and workstation ergonomics. Findings from the risk assessment effort should aid other constrained risk assessments and applied research on similar facilities.

  12. Remote handling technology for nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Sakai, Akira; Maekawa, Hiromichi; Ohmura, Yutaka

    1997-01-01

    Design and R and D on nuclear fuel cycle facilities has intended development of remote handling and maintenance technology since 1977. IHI has completed the design and construction of several facilities with remote handling systems for Power Reactor and Nuclear Fuel Development Corporation (PNC), Japan Atomic Energy Research Institute (JAERI), and Japan Nuclear Fuel Ltd. (JNFL). Based on the above experiences, IHI is now undertaking integration of specific technology and remote handling technology for application to new fields such as fusion reactor facilities, decommissioning of nuclear reactors, accelerator testing facilities, and robot simulator-aided remote operation systems in the future. (author)

  13. Decontamination Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Choi, W. K.; Jung, C. H.; Oh, W. Z.

    2007-06-01

    The originative CO 2 pellet blasting equipment was developed by improving additional components such as feed screw, idle roller and air-lock feeder to clear up the problems of freezing and discontinuity of blasting and by adopting pneumatically operated vacuum suction head and vacuum cup to prevent recontamination by collecting contaminant particulates simultaneously with the decontamination. The optimum decontamination process was established according to the kind of materials such as metal, concrete and plastic and the type of contaminants such as particulate, fixed chemical compound and oil. An excellent decontamination performances were verified by means of the lab-scale hot test with radioactive specimen and the technology demonstration in IMEF hot cell. The PFC dry decontamination equipment applicable to the surface contaminated with high radioactive particulate was developed. This equipment consists of the unit processes such as spray, collection, filtration and dry distillation designed originatively applicable to inside of dry hot cell. Through the demonstration of PFC spray decontamination process in IMEF hot cell, we secured on-site applicability and the decontamination efficiency more than 90 %. We investigated the characteristics of dismantled metal waste melting and the radionuclide(Co, Cs, U) distribution into ingot and slag by melting decontamination experiments using electric arc melter. We obtained the decontamination factors greater than 100 for Cs and of 10∼100 for uranium. The pilot scale(200 kg/batch) demonstration for melting decontamination was carried out successfully using high temperature melting facility at KAERI. The volume reduction factor of 1/7 and the economical feasibility of the melting decontamination were verified.

  14. ORSEC technological risks, Blayais NPP

    International Nuclear Information System (INIS)

    2016-01-01

    The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Blayais NPP (Gironde, France)

  15. Technological risks and social conflicts

    International Nuclear Information System (INIS)

    Conrad, J.; Krebsbach-Gnath, C.

    1980-12-01

    Research on acceptance, perception and assessment of risks clearly shows that perception of risk by the public is based more on subjective assessments than on scientifically objective risk values. Risk perception by the public is influenced by a number of factors. Risk is still a central point in the conflict and always plays a major role in the opposition toward dangerous technologies. Risk forms the thematic focus for the controversy. The development of the actual conflict, the positions, interests, adaptation problems and processes of the various societal institutions, the conditions, prospects, and forms of antinuclear protest and the subjects and structures, symmetries and changes of argument in the public discussion on nuclear energy are analyzed and represented in detail in this report. (orig./HSCH) [de

  16. Innovative technologies for recycling and reusing radioactively contaminated materials from DOE facilities

    International Nuclear Information System (INIS)

    Bossart, S.J.; Hyde, J.

    1993-01-01

    Through award of ten contracts under the solicitation, DOE is continuing efforts to develop innovative technologies for decontamination and recycling or reusing of process equipment, scrap metal, and concrete. These ten technologies are describe briefly in this report. There is great economic incentive for recycling or reusing materials generated during D ampersand D of DOE's facilities. If successfully developed, these superior technologies will enable DOE to clean its facilities by 2019. These technologies will also generate a reusable or recyclable product, while achieving D ampersand D in less time at lower cost with reduced health and safety risks to the workers, the public and the environment

  17. National Ignition Facility risk management plan, rev. 1

    International Nuclear Information System (INIS)

    Brereton, S J; Lane, M A

    1998-01-01

    The initial release of the National Ignition Facility (AUF) Risk Management Plan (LLNL, 1997a) was prepared in accordance with the DOE Life Cycle Asset Management Good Practice Guide (DOE, 1996a) and supported Critical Decision 3 (CD3), Approval to Initiate Construction (DOE, 1997a). The objectives of the plan were to: (1) Identify the risks to the completion of the Project in terms of meeting technical and regulatory requirements, cost, and schedule. (2) Assess the risks in terms of likelihood of occurrence and their impact potential relative to technical performance, ES and H (environmental, safety and health), costs, and schedule. (3) Address suitable risk mitigation measures for each identified risk. This revision of the Risk Management Plan considers project risks and vulnerabilities after CD3 (DOE, 1997a) was approved by the Secretary of Energy. During the one-year period since the initial release, the vulnerabilities of greatest concern have been the litigation of the Programmatic Environmental Impact Statement (PEIS) (DOE, 1996b) by a group of environmental organizations led by the Natural Resources Defense Council; the finding and successful clean-up of polychlorinated biphenyl (PCB)-filled electrical capacitors at the NIF site excavation; the FY98 congressional budget authorization and request for the FY99 budget authorization; funding for Inertial Confinement Fusion (ICF)/NIF programmatic activities (including French and other sources of funding); and finally, progress in the core science and technology, and optics program that form the basis for the NIF design

  18. Technology Evaluation for Environmental Risk Mitigation Compendium

    Science.gov (United States)

    Meinhold, A.; Greene, B.; Dussich, J.; Sorkin, A.; Olsen, W.

    2017-01-01

    The Technology Evaluation for Environmental Risk Mitigation (TEERM) Principal Center and its predecessor organization the Acquisition Pollution Prevention Program (AP2) supported the National Aeronautics and Space Administration (NASA) in identifying technology solutions to risks and costs to NASA programs driven by environmental regulations and requirements. TEERM researched the commercial and government marketplace to locate viable and available technologies that met NASAs needs. TEERM focused on addressing environmentally-driven risks of direct concern to NASA programs and facilities, including hazardous materials in NASA operations and materials that became obsolescent because of environmental regulations. TEERM projects aimed to reduce cost; ensure the health and safety of people, assets, and the environment; promote efficiency; and minimize duplication. Major TEERM and AP2 projects focused on waste minimization and hazardous waste treatment, recycling, corrosion prevention and control, solvent and ozone depleting substances substitution, and aqueous based cleaners. In 2017, NASA made the decision to terminate the TEERM Principal Center. This Compendium Report documents TEERM and AP2 project successes. The Compendium Report traces the evolution of TEERM based on evolving risks and requirements for NASA and its relationship to the Space Shuttle Program, the United States Department of Defense, the European Space Agency, and other public and private stakeholders. This Compendium Report also documents project details from Project Summaries and Joint Test Plans and describes project stakeholders and collaborative effort results.

  19. The role of economic incentives for managing technological risks

    International Nuclear Information System (INIS)

    Kunreuther, H.

    1995-01-01

    A key issue facing society in dealing with the management of technological facilities is balancing the costs of reducing risks with the relevant benefits. These tradeoffs are difficult for both experts and laypersons to make when there is limited objective data on the nature of the health and safety risks. Economic incentives, such as insurance and compensation, can play an important role in reducing and preventing losses associated with technological facilities if they are coupled with appropriate regulations and/or standards. They also can communicate information to the public on the price associated with different levels of risk. The talk will focus on how these policy tools can be utilized for improving the risk management process in conjunction with risk assessment. The siting of facilities for storing and disposing of potentially hazardous wastes will be used to illustrate these concepts and indicate how the public can be made a more integral part of the process

  20. Mitigating risks related to facilities management.

    Science.gov (United States)

    O'Neill, Daniel P; Scarborough, Sydney

    2013-07-01

    By looking at metrics focusing on the functionality, age, capital investment, transparency, and sustainability (FACTS) of their organizations' facilities, facilities management teams can build potential business cases to justify upgrading the facilities. A FACTS analysis can ensure that capital spent on facilities will produce a higher or more certain ROI than alternatives. A consistent process for managing spending helps to avoid unexpected spikes that cost the enterprise more in the long run.

  1. Protection of Facilities and Risk Assessment Application

    OpenAIRE

    Nađ, Ivan; Mihaljević, Branko; Mihalinčić, Martina

    2014-01-01

    The state of security on a specific area imposes the necessity for constant analysis of the existing system of protection of key state facilities, especially facilities of special significance for the defence. The facilities of special significance for the defence are an important part of the daily life, and enable smooth functioning of the economy and all other state activities. The protection of facilities of special significance for the defence is considered to be a system of obligatory me...

  2. Utilization Of Information And Communication Technology Facilities ...

    African Journals Online (AJOL)

    The purpose of this study was to investigate the types of ICT facilities used for the provision of library and information services in Nigerian University libraries. It was also set to determine if there is any significant difference between Southern and Northern Nigeria University libraries of the first, second and third generations in ...

  3. Health risks of energy technologies

    International Nuclear Information System (INIS)

    Travis, C.C.; Etnier, E.L.

    1983-01-01

    This volume examines occupational, public health, and environmental risks of the coal fuel cycle, the nuclear fuel cycle, and unconventional energy technologies. The 6 chapters explore in detail the relationship between energy economics and risk analysis, assess the problems of applying traditional cost-benefit analysis to long-term environmental problems (such as global carbon dioxide levels), and consider questions about the public's perception and acceptance of risk. Also included is an examination of the global risks associated with current and proposed levels of energy production and comsumption from all major sources. A separate abstract was prepared for each of the 6 chapters; all are included in Energy Abstracts for Policy Analysis (EAPA) and four in Energy Research Abstracts

  4. Application of information and communication technology facilities in ...

    African Journals Online (AJOL)

    ... technology facilities in technical services operations at Bayero University library, Nigeria. ... Victoria Sokari, Umar Garba Gama, Zanaib Abba Haliru, Kemi J. Olayemi, ... This paper examines the application of Information and Communication ...

  5. Composites Manufacturing Education and Technology Facility Expedites Manufacturing Innovation

    Energy Technology Data Exchange (ETDEWEB)

    2017-01-01

    The Composites Manufacturing Education and Technology facility (CoMET) at the National Wind Technology Center at the National Renewable Energy Laboratory (NREL) paves the way for innovative wind turbine components and accelerated manufacturing. Available for use by industry partners and university researchers, the 10,000-square-foot facility expands NREL's composite manufacturing research capabilities by enabling researchers to design, prototype, and test composite wind turbine blades and other components -- and then manufacture them onsite. Designed to work in conjunction with NREL's design, analysis, and structural testing capabilities, the CoMET facility expedites manufacturing innovation.

  6. Technological risks and social conflicts

    International Nuclear Information System (INIS)

    Conrad, J.; Krebsbach-Gnath, C.

    1980-12-01

    This volume of materials is part of the report on 'Technological risks and social conflicts. Political risk strategies in the field of nuclear power'. The interested reader who wants to deepen his knowledge on the results and reasoning of the main report, will here find detailed explanations and brief drafts of subprojects; fundamental aspects of problems are presented in detail, and theoretical-conceptional, methodological and scientific-political points of view are explained. Furthermore it contains general reflections on the application-oriented research by order, a review of the status of risk research, historical considerations on the nuclear energy conflict, and finally explanations are attempted for the nuclear energy conflict. (orig./HSCH) [de

  7. Occupational Safety Review of High Technology Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee Cadwallader

    2005-01-31

    This report contains reviews of operating experiences, selected accident events, and industrial safety performance indicators that document the performance of the major US DOE magnetic fusion experiments and particle accelerators. These data are useful to form a basis for the occupational safety level at matured research facilities with known sets of safety rules and regulations. Some of the issues discussed are radiation safety, electromagnetic energy exposure events, and some of the more widespread issues of working at height, equipment fires, confined space work, electrical work, and other industrial hazards. Nuclear power plant industrial safety data are also included for comparison.

  8. Development of Diagnostic Technology for Substation Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kweon, D.J.; Yoon, J.Y. [Korea Electric Power Research Institute, Taejeon (Korea, Republic of)

    1998-09-01

    This report contains the conceptual design of predictive diagnostic system for KEPCO 765kV substation apparatus which will be operated in 2001. Various kinds of techniques in the world for power transformer and GIS monitoring were examined, then the integrated diagnosis system configuration which will be most effective in our future substation was suggested. In addition, the development of the optimum life management for substation facilities. development of a system to measure the ESDD of substation insulator surfaces at a distance and application study of the degradation sensor(PCS) were described also. (author) 55 refs., 27 figs., 68 tabs.

  9. Risk management study for the retired Hanford Site facilities

    International Nuclear Information System (INIS)

    Coles, G.A.; Shultz, M.V.; Taylor, W.E.

    1993-04-01

    Risk from retired surplus facilities has always been assumed to be low at the Hanford Site as the facilities are inactive and have few potentials for causing an offsite hazardous material release. However,the fatal accident that occurred in the spring of 1992 in which an employee fell through a deteriorated roof at the 105-F Reactor Building has raised the possibility that retired facilities represent a greater risk than was originally assumed. Therefore, Westinghouse Hanford Company and the US Department of Energy management have determined that facility risk management strategies and programmatic plans should be reevaluated to assure risks are identified and appropriate corrective action plans are developed. To evaluate risk management strategies, accurate risk information about the current and projected condition of the facilities must be developed. This work procedure has been created to address the development of accurate and timely risk information. By using the evaluation results in this procedure, it will be possible to create a prioritized baseline for managing facility risk until all retired surplus facilities are demolished

  10. Risk evaluation system for facility safeguards and security planning

    International Nuclear Information System (INIS)

    Udell, C.J.; Carlson, R.L.

    1987-01-01

    The Risk Evaluation System (RES) is an integrated approach to determining safeguards and security effectiveness and risk. RES combines the planning and technical analysis into a format that promotes an orderly development of protection strategies, planing assumptions, facility targets, vulnerability and risk determination, enhancement planning, and implementation. In addition, the RES computer database program enhances the capability of the analyst to perform a risk evaluation of the facility. The computer database is menu driven using data input screens and contains an algorithm for determining the probability of adversary defeat and risk. Also, base case and adjusted risk data records can be maintained and accessed easily

  11. Risk evaluation system for facility safeguards and security planning

    International Nuclear Information System (INIS)

    Udell, C.J.; Carlson, R.L.

    1987-01-01

    The Risk Evaluation System (RES) is an integrated approach to determining safeguards and security effectiveness and risk. RES combines the planning and technical analysis into a format that promotes an orderly development of protection strategies, planning assumptions, facility targets, vulnerability and risk determination, enhancement planning, and implementation. In addition, the RES computer database program enhances the capability of the analyst to perform a risk evaluation of the facility. The computer database is menu driven using data input screens and contains an algorithm for determining the probability of adversary defeat and risk. Also, base case and adjusted risk data records can be maintained and accessed easily

  12. Risk assessment of 30 MeV cyclotron facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Gyo Seong; Lee, Jin Woo [Advanced Radiation Technology Institute, Korea Atomic Energy Research Institute, Jeongeup (Korea, Republic of); Kim, Chong Yeal [Dept. of Radiation Science and Technology, Chonbuk National University, Jeonju (Korea, Republic of)

    2017-03-15

    A cyclotron is a kind of particle accelerator that produces a beam of charged particles for the production of medical, industrial, and research radioisotopes. More than 30 cyclotrons are operated in Korea to produce 18F, an FDG synthesis at hospitals. A 30-MeV cyclotron was installed at ARTI (Advanced Radiation Technology Institute, KAERI) mainly for research regarding isotope production. In this study, we analyze and estimate the items of risk such as the problems in the main components of the cyclotron, the loss of radioactive materials, the leakage of coolant, and the malfunction of utilities, fres and earthquakes. To estimate the occurrence frequency in an accident risk assessment, five levels, i.e., Almost certain, Likely, Possible, Unlikely, and Rare, are applied. The accident consequence level is classified under four grades based on the annual permissible dose for radiation workers and the public in the nuclear safety law. The analysis of the accident effect is focused on the radioactive contamination caused by radioisotope leakage and radioactive material leakage of a ventilation filter due to a free. To analyze the risks, Occupation Safety and Health Acts is applied. In addition, action plans against an accident were prepared after a deep discussion among relevant researchers. In this acts, we will search for hazard and introduce the risk assessment for the research 30-MeV cyclotron facilities of ARTI.

  13. Risk assessment of 30 MeV cyclotron facilities

    International Nuclear Information System (INIS)

    Jeong, Gyo Seong; Lee, Jin Woo; Kim, Chong Yeal

    2017-01-01

    A cyclotron is a kind of particle accelerator that produces a beam of charged particles for the production of medical, industrial, and research radioisotopes. More than 30 cyclotrons are operated in Korea to produce 18F, an FDG synthesis at hospitals. A 30-MeV cyclotron was installed at ARTI (Advanced Radiation Technology Institute, KAERI) mainly for research regarding isotope production. In this study, we analyze and estimate the items of risk such as the problems in the main components of the cyclotron, the loss of radioactive materials, the leakage of coolant, and the malfunction of utilities, fres and earthquakes. To estimate the occurrence frequency in an accident risk assessment, five levels, i.e., Almost certain, Likely, Possible, Unlikely, and Rare, are applied. The accident consequence level is classified under four grades based on the annual permissible dose for radiation workers and the public in the nuclear safety law. The analysis of the accident effect is focused on the radioactive contamination caused by radioisotope leakage and radioactive material leakage of a ventilation filter due to a free. To analyze the risks, Occupation Safety and Health Acts is applied. In addition, action plans against an accident were prepared after a deep discussion among relevant researchers. In this acts, we will search for hazard and introduce the risk assessment for the research 30-MeV cyclotron facilities of ARTI

  14. Technological Advances, Human Performance, and the Operation of Nuclear Facilities

    Science.gov (United States)

    Corrado, Jonathan K.

    Many unfortunate and unintended adverse industrial incidents occur across the United States each year, and the nuclear industry is no exception. Depending on their severity, these incidents can be problematic for people, the facilities, and surrounding environments. Human error is a contributing factor in many such incidents. This dissertation first explored the hypothesis that technological changes that affect how operators interact within the systems of the nuclear facilities exacerbate the cost of incidents caused by human error. I conducted a review of nuclear incidents in the United States from 1955 through 2010 that reached Level 3 (serious incident) or higher on the International Nuclear Events Scale (INES). The cost of each incident at facilities that had recently undergone technological changes affecting plant operators' jobs was compared to the cost of events at facilities that had not undergone changes. A t-test determined a statistically significant difference between the two groups, confirming the hypothesis. Next, I conducted a follow-on study to determine the impact of the incorporation of new technologies into nuclear facilities. The data indicated that spending more money on upgrades increased the facility's capacity as well as the number of incidents reported, but the incident severity was minor. Finally, I discuss the impact of human error on plant operations and the impact of evolving technology on the 21st-century operator, proposing a methodology to overcome these challenges by applying the systems engineering process.

  15. Decommissioning Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Kang, Y. A.; Kim, G. H.

    2007-06-01

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely

  16. Decommissioning Technology Development for Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K. W.; Kang, Y. A.; Kim, G. H. (and others)

    2007-06-15

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely.

  17. Advances in technology transfer at Federal Facilities

    International Nuclear Information System (INIS)

    Silva, R.R. Jr.

    1994-11-01

    The Hanford Site, located in the southeast portion of the state of Washington, is a 1450-hectare (560 square miles) reservation that was selected by the US Government in 1942 for production of the world's first nuclear weapons materials. For more than 40 years, defense production operations at Hanford generated hazardous and radioactive materials and wastes that for the most part remain there today. Environmental restoration of the Hanford Site is the primary mission of the Westinghouse Hanford Company (WHC) and it is also the thrust of the Tri-Party agreement among the US Environmental Protection Agency, the Washington State Department of Ecology and the US Department of Energy. Restoration will require treatment of about 1400 individual locations that are contaminated by chemically hazardous wastes, radioactive wastes, non-hazardous wastes and mixed hazardous and radioactive wastes. These locations include burial sites, storage facilities, obsolete buildings, settling ponds, waste cribs and large and small areas of near-surface and deep soil contamination. Burial trenches contain an estimated 109,000 cubic meters of low-level solid wastes contaminated with hazardous chemicals and radioactive materials. Approximately 450 sites were contaminated by discharge of liquids to the ground and there are about 250 additional areas where waste materials were spilled. At one time, ditches carried water from processing plants to settling/cooling ponds and 131 cribs were used over the years to dispose of slightly radioactive liquid wastes

  18. Risk management study for the Hanford Site facilities: Risk reduction cost comparison for the retired Hanford Site facilities

    International Nuclear Information System (INIS)

    Coles, G.A.; Egge, R.G.; Senger, E.; Shultz, M.W.; Taylor, W.E.

    1994-02-01

    This document provides a cost-comparison evaluation for implementing certain risk-reduction measures and their effect on the overall risk of the 100 and 200 Area retired, surplus facilities. The evaluation is based on conditions that existed at the time the risk evaluation team performed facility investigations, and does not acknowledge risk-reduction measures that occurred soon after risk identification. This evaluation is one part of an overall risk management study for these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1450-km 2 Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30 km southeast of the 200 Area. This cost-comparison evaluation (1) determines relative costs for reducing risk to acceptable levels; (2) compares the cost of reducing risk using different risk-reduction options; and (3) compares the cost of reducing risks at different facilities. The result is an identification of the cost effective risk-reduction measures. Supporting information required to develop costs of the various risk-reduction options also is included

  19. Risk management study for the Hanford Site facilities: Risk reduction cost comparison for the retired Hanford Site facilities. Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    Coles, G.A.; Egge, R.G.; Senger, E.; Shultz, M.W.; Taylor, W.E.

    1994-02-01

    This document provides a cost-comparison evaluation for implementing certain risk-reduction measures and their effect on the overall risk of the 100 and 200 Area retired, surplus facilities. The evaluation is based on conditions that existed at the time the risk evaluation team performed facility investigations, and does not acknowledge risk-reduction measures that occurred soon after risk identification. This evaluation is one part of an overall risk management study for these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1450-km{sup 2} Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30 km southeast of the 200 Area. This cost-comparison evaluation (1) determines relative costs for reducing risk to acceptable levels; (2) compares the cost of reducing risk using different risk-reduction options; and (3) compares the cost of reducing risks at different facilities. The result is an identification of the cost effective risk-reduction measures. Supporting information required to develop costs of the various risk-reduction options also is included.

  20. Use of risk information to safety regulation. Reprocessing facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    A procedure of probabilistic risk assessment (PRA) for a reprocessing facility has been under the development aiming to utilize risk information for safety regulations in this project. Activities in the fiscal year 2012 are summarized in the paper. A major activity is a fundamental study on a concept of serious accidents, requirements of serious accident management, and a policy of utilizing risk information for fabrication and reprocessing facilities. Other than the activity a study on release and transport of aerial radioactive materials at a serious accident in a reprocessing facility has been conducted. The outline and results are provided in the chapter 1 and 2 respectively. (author)

  1. Westinghouse Hanford Company risk management strategy for retired surplus facilities

    International Nuclear Information System (INIS)

    Taylor, W.E.; Coles, G.A.; Shultz, M.V.; Egge, R.G.

    1993-09-01

    This paper describes an approach that facilitates management of personnel safety and environmental release risk from retired, surplus Westinghouse Hanford Company-managed facilities during the predemolition time frame. These facilities are located in the 100 and 200 Areas of the 1,450-km 2 (570-mi 2 ) Hanford Site in Richland, Washington. The production reactors are located in the 100 Area and the chemical separation facilities are located in the 200 Area. This paper also includes a description of the risk evaluation process, shows applicable results, and includes a description of comparison costs for different risk reduction options

  2. Nuclear facilities: repair and replacement technologies

    International Nuclear Information System (INIS)

    2005-01-01

    The oldest operating reactors are more than 35 years old and are now facing major maintenance operations. The first replacement of a pressurizer took place in autumn 2005 at the St-Lucie plant (Usa) while steam generators have been currently replaced since 1983. Nuclear industry has to adapt to this new market by proposing innovative technological solutions in the reactor maintenance field. This document gathers the 9 papers presented at the conference. The main improvements concern repair works on internal components of PWR-type reactors, the replacement of major components of the primary coolant circuit and surface treatments to limit the propagation of damages. The first paper shows that adequate design and feedback experience are good assets to manage the ageing of a nuclear unit. Another paper shows that a new repair method of a relief valve can avoid its replacement. (A.C.)

  3. Cryogenic technology review of cold neutron source facility for localization

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hun Cheol; Park, D. S.; Moon, H. M.; Soon, Y. P. [Daesung Cryogenic Research Institute, Ansan (Korea); Kim, J. H. [United Pacific Technology, Inc., Ansan (Korea)

    1998-02-01

    This Research is performed to localize the cold neutron source(CNS) facility in HANARO and the report consists of two parts. In PART I, the local and foreign technology for CNS facility is investigated and examined. In PART II, safety and licensing are investigated. CNS facility consists of cryogenic and warm part. Cryogenic part includes a helium refrigerator, vacuum insulated pipes, condenser, cryogenic fluid tube and moderator cell. Warm part includes moderator gas control, vacuum equipment, process monitoring system. Warm part is at high level as a result of the development of semiconductor industries and can be localized. However, even though cryogenic technology is expected to play a important role in developing the 21st century's cutting technology, it lacks of specialists and the research facility since the domestic market is small and the research institutes and government do not recognize the importance. Therefore, it takes a long research time in order to localize the facility. The safety standard of reactor for hydrogen gas in domestic nuclear power regulations is compared with that of the foreign countries, and the licensing method for installation of CNS facility is examined. The system failure and its influence are also analyzed. 23 refs., 59 figs., 26 tabs. (Author)

  4. Technical requirement of experiments and facilities for fusion nuclear technology

    International Nuclear Information System (INIS)

    Abdou, M.; Tillak, M.; Gierszwski, P.; Grover, J.; Puigh, R.; Sze, D.K.; Berwald, D.

    1986-06-01

    The technical issues and requirements of experiments and facilities for fusion nuclear technology (FNT) have been investigated. The nuclear subsystems addressed are: a) blanket, b) radiation shield, c) tritium processing system, and d) plasma interactive components. Emphasis has been placed on the important and complex development problems of the blanket. A technical planning process for FNT has been developed and applied, including four major elements: 1) characterization of issues, 2) quantification of testing requirements, 3) evaluation of facilities, and 4) development of a test plan to identify the role, timing, characteristics and costs of major experiments and facilities

  5. Research and test facilities required in nuclear science and technology

    International Nuclear Information System (INIS)

    2009-01-01

    Experimental facilities are essential research tools both for the development of nuclear science and technology and for testing systems and materials which are currently being used or will be used in the future. As a result of economic pressures and the closure of older facilities, there are concerns that the ability to undertake the research necessary to maintain and to develop nuclear science and technology may be in jeopardy. An NEA expert group with representation from ten member countries, the International Atomic Energy Agency and the European Commission has reviewed the status of those research and test facilities of interest to the NEA Nuclear Science Committee. They include facilities relating to nuclear data measurement, reactor development, neutron scattering, neutron radiography, accelerator-driven systems, transmutation, nuclear fuel, materials, safety, radiochemistry, partitioning and nuclear process heat for hydrogen production. This report contains the expert group's detailed assessment of the current status of these nuclear research facilities and makes recommendations on how future developments in the field can be secured through the provision of high-quality, modern facilities. It also describes the online database which has been established by the expert group which includes more than 700 facilities. (authors)

  6. Space Technology Demonstrations Using Low Cost, Short-Schedule Airborne and Range Facilities at the Dryden Flight Research Center

    Science.gov (United States)

    Carter, John; Kelly, John; Jones, Dan; Lee, James

    2013-01-01

    There is a national effort to expedite advanced space technologies on new space systems for both government and commercial applications. In order to lower risk, these technologies should be demonstrated in a relevant environment before being installed in new space systems. This presentation introduces several low cost, short schedule space technology demonstrations using airborne and range facilities available at the Dryden Flight Research Center.

  7. IFMIF (International Fusion Materials Irradiation Facility) key element technology phase interim report

    Energy Technology Data Exchange (ETDEWEB)

    Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-03-01

    Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator-based deuteron (D{sup +})-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m{sup 2}, 20 dpa/year for Fe) in a volume of 500 cm{sup 3} for testing candidate fusion materials. In 2000, a 3 year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test facilities and design integration. (author)

  8. IFMIF (International Fusion Materials Irradiation Facility) key element technology phase interim report

    International Nuclear Information System (INIS)

    Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki

    2002-03-01

    Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator-based deuteron (D + )-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m 2 , 20 dpa/year for Fe) in a volume of 500 cm 3 for testing candidate fusion materials. In 2000, a 3 year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test facilities and design integration. (author)

  9. Risk creation in a technological world

    International Nuclear Information System (INIS)

    Kuhlmann, A.

    1989-01-01

    The question ultimately facing mankind is how to establish an appropriate risk acceptance in a technological world. The systematics of the risk concept is explained in 4 theses. They imply that a heavy use of technology is linked to high risk potentials which place heavy demands on technology in coping with them, and that technology ought as far as possible to be adapted to man and the environment ought to remain under man's influence. (DG) [de

  10. Robotics for radioactive waste management in AEA technology facilities

    International Nuclear Information System (INIS)

    Legg, S.A.; Watson, C.J.H.; Staples, A.

    1992-01-01

    This paper describes the use of robotic technology in two AEA Technology facilities. In the first application, the task is standardized and repetitive, and is undertaken using a conventional industrial robot, operating in teach-and-repeat mode. In the second application, the task is non-repetitive, and requires the use of a variety of different tools. it is therefore undertaken by a nuclear engineered telerobot, with a tool change station

  11. Development of decommissioning, decontamination and reuse technology for nuclear facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Moon, J. K.; Choi, B. S.

    2012-03-01

    In this project, the foundation of decommissioning technology through the development of core technologies applied to maintenance and decommissioning of nuclear facility was established. First of all, we developed the key technology such as safety assessment technology for decommissioning work needed at the preparatory stage of decommissioning of the highly contaminated facilities and simultaneous measurement technology of the high-level alpha/beta contamination applicable to the operation and decommissioning of the nuclear facilities. Second, we developed a remotely controlled laser ablation decontamination system which is useful for a removal of fixed contaminants and developed a chemical gel decontamination technology for a removal of non-fixed contaminants during the maintenance and decommissioning works of high radiation hot cells which have been used for a recycling or treatment of spent fuels. Third, we developed a volume reduction and self-disposal technology for dismantled concrete wastes. Also, the technology for volume reduction and stabilization of the peculiar wastes(HEPA filter and organic mixed wastes), which have been known to be very difficult to treat and manage, generated from the high radioactive facilities in operation, improvement and repair and under decommissioning was developed. Finally, this research project was developed a system for the reduction of radiotoxicity of several uranium mixtures generated in the front- and back-end nuclear fuel cycles with characteristics of highly enhanced proliferation-resistance and more environmental friendliness, which can make the uranium to be recovered or separated from the mixtures with a high purity level enough for the uranium to be reused and to be classified as C-class level for burial near the surface, and then which result in the much reduction in volume of the uranium mixture wastes

  12. Technology standards for structure, etc. concerning nuclear power generating facilities

    International Nuclear Information System (INIS)

    1977-01-01

    Based on the Ordinance for the Technology Standards concerning Nuclear Power Generating Facilities, the technology standards are established for the vessels of class 1 to 4 (including reactor pressure vessels, reactor containment vessels, etc.), the pipes of class 1 to 3, safety valves, pressure test and monitoring test specimens. Those specified are materials, nondestructive tests, structures, shapes, shells, flanges, etc. for the vessels and the pipes, and so on. (Mori, K.)

  13. Engineering risk assessment for hydro facilities

    International Nuclear Information System (INIS)

    Laurence, K.G.

    1991-01-01

    Faced with escalating property insurance premiums, the Alaska Energy Authority decided to evaluate what losses may realistically be expected due to catastrophic events at their hydroelectric generation and transmission facilities. Ideally insurance rates are established using historic loss statistics. Where these statistics are non-existent, other means must be employed to estimate expected losses so that appropriate steps may be taken to protect investments in facilities. The natural perils of earthquake, flood, tidal wave (tsunami), wind, snow and internal failure potentially can cause catastrophic damage, but due to their infrequency in the higher magnitudes, meaningful statistics are as yet insufficient to be of value in estimating losses from these events. In order to overcome this deficiency a quasi-engineering approach can be adopted as distinct from the actuarial approach preferred and most often used by the insurance industry. This paper describes the quasi-engineering approach used for this assessment with a specific example worked through for earthquake peril

  14. Physical security technologies for weapons complex reconfiguration facilities

    International Nuclear Information System (INIS)

    Jaeger, C.D.

    1994-01-01

    Sandia National Laboratories was a member of the Weapons Complex Reconfiguration (WCR) Safeguards and Security (S ampersand S) team providing assistance to the Department of Energy's (DOE) Office of Weapons Complex Reconfiguration. The physical security systems in the new and upgraded facilities being considered for the WCR had to meet DOE orders and other requirements set forth in the WCR Programmatic Design Criteria (PDC), incorporate the latest physical security technologies using proven state-of-the-art systems and meet fundamental security principles. The outcome was to avoid costly retrofits and provide effective and comprehensive protection against current and projected threats with minimal impact on operations, costs and schedule. Physical security requirements for WCR facilities include: (1) reducing S ampersand S life-cycle costs, (2) where feasible automating S ampersand S functions to minimize operational costs, access to critical assets and exposure of people to hazardous environments, (3) increasing the amount of delay to outsider adversary attack, (4) compartmentalizing the facility to minimize the number of personnel requiring access to critical areas and (5) having reliable and maintainable systems. To be most effective against threats physical security must be integrated with facility operations, safety and other S ampersand S activities, such as material control and accountability, nuclear measurements and computer and information security. This paper will discuss the S ampersand S issues, requirements, technology opportunities and needs. Physical security technologies and systems considered in the design effort of the Weapons Complex Reconfiguration facilities will be reviewed

  15. Development of Experimental Facilities for Advanced Spent Fuel Management Technology

    Energy Technology Data Exchange (ETDEWEB)

    You, G. S.; Jung, W. M.; Ku, J. H. [and others

    2004-07-01

    The advanced spent fuel management process(ACP), proposed to reduce the overall volume of the PWR spent fuel and improve safety and economy of the long-term storage of spent fuel, is under research and development. This technology convert spent fuels into pure metal-base uranium with removing the highly heat generating materials(Cs, Sr) efficiently and reducing of the decay heat, volume, and radioactivity from spent fuel by 1/4. In the next phase(2004{approx}2006), the demonstration of this technology will be carried out for verification of the ACP in a laboratory scale. For this demonstration, the hot cell facilities of {alpha}-{gamma} type and auxiliary facilities are required essentially for safe handling of high radioactive materials. As the hot cell facilities for demonstration of the ACP, a existing hot cell of {beta}-{gamma} type will be refurbished to minimize construction expenditures of hot cell facility. In this study, the design requirements are established, and the process detail work flow was analysed for the optimum arrangement to ensure effective process operation in hot cell. And also, the basic and detail design of hot cell facility and process, and safety analysis was performed to secure conservative safety of hot cell facility and process.

  16. Radiation risk management at DOE accelerator facilities

    International Nuclear Information System (INIS)

    Dyck, O.B. van.

    1997-01-01

    The DOE accelerator contractors have been discussing among themselves and with the Department how to improve radiation safety risk management. This activity-how to assure prevention of unplanned high exposures-is separate from normal exposure management, which historically has been quite successful. The ad-hoc Committee on the Accelerator Safety Order and Guidance [CASOG], formed by the Accelerator Section of the HPS, has proposed a risk- based approach, which will be discussed. Concepts involved are risk quantification and comparison (including with non-radiation risk), passive and active (reacting) protection systems, and probabilistic analysis. Different models of risk management will be presented, and the changing regulatory environment will also be discussed

  17. Comparative analysis of risk characteristics of nuclear waste repositories and other disposal facilities

    International Nuclear Information System (INIS)

    Lindell, M.K.; Earle, T.C.; Nealey, S.M.

    1981-06-01

    Three fundamental questions concerning public perception of the measurement of radioactive wastes were addressed in this report. The first question centered on the perceived importance of nuclear waste management as a public issue: how important is nuclear waste management relative to other technological and scientific issues; do different segments of the public disagree on its importance; the second question concerned public attitudes toward a nuclear waste disposal facility: how great a risk to health and safety is a nuclear waste disposal facility relative to other industrial facilities; is there disagreement on its riskiness among various public groups; the third question pertained to the aspects of risks that affect overall risk perception: what are the qualitative aspects of a nuclear waste disposal facility that contribute to overall perceptions of risk; do different segments of the population associate different risk characteristics with hazardous facilities. The questions follow from one another: is the issue important; given the importance of the issue, is the facility designed to deal with it considered risky; given the riskiness of the facility, why is it considered risky. Also addressed in this report, and a main focus of its findings, were the patterns of differences among respondent groups on each of these questions

  18. Facility for protection of technological, especially power assemblies

    International Nuclear Information System (INIS)

    Cichon, S.; Hahn, J.; Malatek, K.; Randak, O.; Vitovec, P.; Zidek, M.

    1987-01-01

    The facility consists of sensors producing analog signals, used as input information for the evaluation of process conditions or equipment failures. The sensors are fitted to partial functional parts of technological assemblies, such as nuclear reactors. The individual sensors are connected via unification converters to the respective protection units. The facility is resistant to breakdowns of the analog sensors and other components including the computer; it features the possibility of in-service failure detection and the capability of immediate regeneration following a failure. This capability prevents, with high probability, the production of non-accident failures of the technological assembly. The block diagram is described of the facility and its operation in the event of an emergency. (J.B.). 1 fig

  19. Information Technology in Facilities Management - A Literature Review

    DEFF Research Database (Denmark)

    Ebbesen, Poul

    2015-01-01

    Purpose : The aim of this paper is to present the state of the art of research in Information Technology (IT) in Facilities Management (FM). Background : Initial studies indicate that investments into IT in FM often do not add the expected value, neither to the FM department itself nor...

  20. Adding Value to Facilities Management with Information Technology

    DEFF Research Database (Denmark)

    Ebbesen, Poul

    2016-01-01

    This PhD project investigates implementation and use of Information Systems (IS) and Information Technologies (IT) in the Facilities management (FM) business domain. This investigation is relevant because implementation and use of IS/IT in FM has potentials for improvements which can provide...

  1. Noxious facility impact projection: Incorporating the effects of risk aversion

    International Nuclear Information System (INIS)

    Nieves, L.A.

    1993-01-01

    Developing new sites for noxious facilities has become a complex process with many potential pitfalls. In addition to the need to negotiate conditions acceptable to the host community, siting success may depend on the facility proposer's ability to identify a candidate site that not only meets technical requirements, but that is located in a community or region whose population is not highly averse to the risks associated with the type of facility being proposed. Success may also depend on the proposer accurately assessing potential impacts of the facility and offering an equitable compensation package to the people affected by it. Facility impact assessments, as typically performed, include only the effects of changes in population, employment and economic activity associated with facility construction and operation. Because of their scope, such assessments usually show a short-run, net economic benefit for the host region, making the intensely negative public reaction to some types and locations of facilities seem unreasonable. The impact component excluded from these assessments is the long-run economic effect of public perceptions of facility risk and nuisance characteristics. Recent developments in psychological and economic measurement techniques have opened the possibility of correcting this flaw by incorporating public perceptions in projections of economic impacts from noxious facilities

  2. Risk management study for the retired Hanford Site facilities: Qualitative risk evaluation for the retired Hanford Site facilities

    International Nuclear Information System (INIS)

    Coles, G.A.; Shultz, M.V.; Taylor, W.E.

    1993-09-01

    This document provides a risk evaluation of the 100 and 200 Area retired, surplus facilities on the Hanford Site. Also included are the related data that were compiled by the risk evaluation team during investigations performed on the facilities. Results are the product of a major effort performed in fiscal year 1993 to produce qualitative information that characterizes certain risks associated with these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1,450-km 2 (570-mi 2 ) Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30-km (20 mi) southeast of the 200 Area. During walkdown investigations of these facilities, data on real and potential hazards that threatened human health or safety or created potential environmental release issues were identified by the risk evaluation team. Using these findings, the team categorized the identified hazards by facility and evaluated the risk associated with each hazard. The factors contributing to each risk, and the consequence and likelihood of harm associated with each hazard also are included in this evaluation

  3. Risk management study for the retired Hanford Site facilities: Qualitative risk evaluation for the retired Hanford Site facilities. Volume 3

    Energy Technology Data Exchange (ETDEWEB)

    Coles, G.A.; Shultz, M.V.; Taylor, W.E.

    1993-09-01

    This document provides a risk evaluation of the 100 and 200 Area retired, surplus facilities on the Hanford Site. Also included are the related data that were compiled by the risk evaluation team during investigations performed on the facilities. Results are the product of a major effort performed in fiscal year 1993 to produce qualitative information that characterizes certain risks associated with these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1,450-km{sup 2} (570-mi{sup 2}) Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30-km (20 mi) southeast of the 200 Area. During walkdown investigations of these facilities, data on real and potential hazards that threatened human health or safety or created potential environmental release issues were identified by the risk evaluation team. Using these findings, the team categorized the identified hazards by facility and evaluated the risk associated with each hazard. The factors contributing to each risk, and the consequence and likelihood of harm associated with each hazard also are included in this evaluation.

  4. Need for realistic risk assessments at DOE facilities

    International Nuclear Information System (INIS)

    Hamilton, L.D.

    1993-01-01

    Widespread environmental contamination has been documented at U.S. Department of Energy (DOE) facilities. Human health risk assessments are increasingly being used to support decisions concerning remediation at these sites. Current methods for assessing risk at DOE facilities are generally excessively conservative or simplistic. Generic models, conservative parameter default values, and assumptions are often used, and unrealistic exposure and land-use scenarios are embedded in the analyses. These approaches are appropriate only as first-level screening analyses and identify contaminants or pathways that are not important in terms of risk to human health

  5. Conceptual capital-cost estimate and facility design of the Mirror-Fusion Technology Demonstration Facility

    International Nuclear Information System (INIS)

    1982-09-01

    This report contains contributions by Bechtel Group, Inc. to Lawrence Livermore National Laboratory (LLNL) for the final report on the conceptual design of the Mirror Fusion Technology Demonstration Facility (TDF). Included in this report are the following contributions: (1) conceptual capital cost estimate, (2) structural design, and (3) plot plan and plant arrangement drawings. The conceptual capital cost estimate is prepared in a format suitable for inclusion as a section in the TDF final report. The structural design and drawings are prepared as partial inputs to the TDF final report section on facilities design, which is being prepared by the FEDC

  6. Development of decommissioning technology for nuclear fuel facility

    International Nuclear Information System (INIS)

    Tanimoto, Ken-ichi

    1998-01-01

    There are many kinds of objects for decommissioning and their properties are greatly different in respects of morphology, constituent materials, contamination history, etc. Therefore, the techniques for decontamination and dismantlement are required to have a great applicability. In addition, most of contamination nuclides have long half-life and so, it is desirable to rapidly take measures to stop or close a contaminated facility. In consideration of these characteristics developments of elementary techniques for decontamination have been attempted. This report summarized the present states of decommissioning technology for nuclear fuel facility. The function and performance of each elementary technique were examined through test operation and simulation was made for the important techniques of them aiming at generalization and optimization. For remote handling technology, two operation tools; 'metal splitting saw cutting tool' and 'plasma cutting tool' were produced and utilizations of these tools in combination with a robot for conveyance are under investigation now. (M.N.)

  7. 10 CFR 611.202 - Advanced Technology Vehicle Manufacturing Facility Award Program.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 4 2010-01-01 2010-01-01 false Advanced Technology Vehicle Manufacturing Facility Award... TECHNOLOGY VEHICLES MANUFACTURER ASSISTANCE PROGRAM Facility/Funding Awards § 611.202 Advanced Technology Vehicle Manufacturing Facility Award Program. DOE may issue, under the Advanced Technology Vehicle...

  8. Moving out. Technology transfer from hospitals to outpatient facilities.

    Science.gov (United States)

    Freedman, G

    1991-02-01

    The Temple Radiology Group opened on July 1, 1977 in the Temple Medical Center. The initial 10-room, full-service department has grown with new technology into approximately 25 rooms. The original four-room Temple surgery center has grown to 10 rooms. Additional support facilities that have evolved include: 1) a computer company; 2) physical therapy for orthopedic, neurological and cardiac patients; 3) a brain trauma center; 4) a collection agency; and most recently, 5) a 100-bed medical hotel.

  9. Verification of best available technology for the 300 Area Treated Effluent Disposal Facility (310 Facility)

    International Nuclear Information System (INIS)

    Wagner, R.N.

    1994-01-01

    This compilation of Project L-045H reference materials documents that the 300 Area Treated Effluent Disposal Facility (TEDF, also designated the 310 Facility) was designed, built, and will be operated in accordance with the best available technology (BAT) identified in the Engineering Summary Report. The facility is intended for treatment of 300 Area process sewer wastewater. The following unit operations for 300 Area process sewer water treatment are specified as: influent receipt; iron co-precipitation and sludge handling for removal of heavy metals and initial suspended solids; ion exchanged for removal of mercury and other heavy metals; ultraviolet (UV)/peroxide treatment for destruction of organic compounds, cyanide, coliforms, sulfide, and nitrite; and effluent discharge to the Columbia River with pH monitoring/control capability

  10. Perceived risk impacts from siting hazardous waste facilities

    International Nuclear Information System (INIS)

    Hemphill, R.C.; Edwards, B.K.; Bassett, G.W. Jr.

    1992-01-01

    This paper describes methods for evaluating perception-based economic impacts resulting from siting hazardous waste facilities. Socioeconomic impact analysis has devoted increasing attention to the potential implications of changed public perceptions of risk due to an activity or situation. This contrasts with traditional socioecconomic impact analysis, which has been limited to measuring direct and indirect consequences of activities, e.g., the employment effects of placing a military base in a specified location. Approaches to estimating economic impacts due to changes in public perceptions are ex ante or ex post. The former predict impacts prior to the construction and operation of a facility, while the later is based on impacts that become evident only when the facility is up and running. The theoretical foundations and practical requirements for demonstrating impacts, resulting from the siting of a hazardous facility are described. The theoretical rationale supporting the study of perceived risk research is presented along with discussion of problems that arise in demonstrating the existence and measuring the quantitative importance of economic impacts due to changes in perceived risk. The high-level nuclear waste facility being considered in Nevada is presented as an example in which there is potential for impacts, but where the link between perceived risk and economic conditions has not yet been developed

  11. Perceived risk impacts from siting hazardous waste facilities

    International Nuclear Information System (INIS)

    Hemphill, R.C.; Edwards, B.K.; Bassett, G.W. Jr.

    1992-01-01

    This paper describes methods for evaluating perception-based economic impacts resulting from siting hazardous waste facilities. Socioeconomic impact analysis has devoted increasing attention to the potential implications of changed public perceptions of risk due to an activity or situation. This contrasts with traditional socioeconomic impact analysis, which has been limited to measuring direct and indirect consequences of activities, e.g., the employment effects of placing a military base in a specified location. Approaches to estimating economic impacts due to changes in public perceptions are ex ante or ex post. The former predict impacts prior to the construction and operation of a facility, while the later is based on impacts that become evident only when the facility is up and running. The theoretical foundations and practical requirements for demonstrating impacts resulting from the siting of a hazardous facility are described. The theoretical rationale supporting the study of perceived risk research is presented along with discussion of problems that arise in demonstrating the existence and measuring the quantitative importance of economic impacts due to changes in perceived risk. The high-level nuclear waste facility being considered in Nevada is presented as an example in which there is potential for impacts, but where the link between perceived risk and economic conditions has not yet been developed

  12. Use of information technology for medication management in residential care facilities: correlates of facility characteristics.

    Science.gov (United States)

    Bhuyan, Soumitra S; Chandak, Aastha; Powell, M Paige; Kim, Jungyoon; Shiyanbola, Olayinka; Zhu, He; Shiyanbola, Oyewale

    2015-06-01

    The effectiveness of information technology in resolving medication problems has been well documented. Long-term care settings such as residential care facilities (RCFs) may see the benefits of using such technologies in addressing the problem of medication errors among their resident population, who are usually older and have numerous chronic conditions. The aim of this study was two-fold: to examine the extent of use of Electronic Medication Management (EMM) in RCFs and to analyze the organizational factors associated with the use of EMM functionalities in RCFs. Data on RCFs were obtained from the 2010 National Survey of Residential Care Facilities. The association between facility, director and staff, and resident characteristics of RCFs and adoption of four EMM functionalities was assessed through multivariate logistic regression. The four EMM functionalities included were maintaining lists of medications, ordering for prescriptions, maintaining active medication allergy lists, and warning of drug interactions or contraindications. About 12% of the RCFs adopted all four EMM functionalities. Additionally, maintaining lists of medications had the highest adoption rate (34.5%), followed by maintaining active medication allergy lists (31.6%), ordering for prescriptions (19.7%), and warning of drug interactions or contraindications (17.9%). Facility size and ownership status were significantly associated with adoption of all four EMM functionalities. Medicaid certification status, facility director's age, education and license status, and the use of personal care aides in the RCF were significantly associated with the adoption of some of the EMM functionalities. EMM is expected to improve the quality of care and patient safety in long-term care facilities including RCFs. The extent of adoption of the four EMM functionalities is relatively low in RCFs. Some RCFs may strategize to use these functionalities to cater to the increasing demands from the market and also to

  13. Relative risk measure suitable for comparison of design alternatives of interim spent nuclear fuel storage facility

    International Nuclear Information System (INIS)

    Ferjencik, M.

    1997-01-01

    Accessible reports on risk assessment of interim spent nuclear fuel storage facilities presume that only releases of radioactive substances represent undesired consequences. However, only certain part of the undesired consequences is represented by them. Many other events are connected with safety and are able to cause losses to the operating company. The following two presumptions are pronounced based on this. 1. Any event causing a disturbance of a safety function of the storage facility is an incident event. 2. Any disturbance of a safety function is an undesired consequence. If the facility safety functions are identified and if the severity of their disturbances is quantified, then it is possible to combine consequence severity quantifications and event frequencies into a risk measure. Construction and application of such a risk measure is described in this paper. The measure is shown to be a tool suitable for comparison of interim storage technology design alternatives. (author)

  14. Problems in the communication of technological risks

    International Nuclear Information System (INIS)

    Wiedemann, P.M.; Hennen, L.

    1989-01-01

    The authors discuss the problems in the communication of technological risks. They show that - contrary to a current popular belief - acceptance problems are not attributable to information deficits: such problems are caused rather by the fact that risks are perceived differently by the various groups in science, industry, politics and the larger public. Nevertheless, improved information about technology may help to find acceptable compromises and, thus, to prevent social conflicts to erupt over technology and to geopardize the basic political consensus. (orig.) [de

  15. Proceedings of the Seminar 'Irradiation Technologies and the IRASM Facility'

    International Nuclear Information System (INIS)

    Ponta, Corneliu Catalin; Moise, Ioan Valentin

    1999-01-01

    The seminar devoted to 'Irradiation Technologies and the IRASM Facility' aimed at debating the principal problems related to one of the most important project ever developed in Romania, at the Horia Hulubei National Institute of Physics and Nuclear Engineering, in collaboration with IAEA. IRASM (an acronym for Multiple Purpose Irradiation Facility) is using initially a 60 Co of 100 kCi irradiation source (to be replaced after an promotional stage by a 2 MCi Co source). It is designed to irradiate a materials volume of about 35,000 m 3 /year. Health, agriculture, food industry and materials industry are the most targeted customers. It will be used for sterilization of medical materials and pharmaceuticals products, peat and seed (and other agricultural products) decontamination and sterilization, experimental irradiation of food products, irradiation of composite plastics and other industrial products, etc. The seminar was a first meeting of Romanian specialists in radiation processing with potential users of these technologies as well as with decision making persons working with national governmental and regulation authorities. Twelve communications were presented as a basis for discussion. These were: 1. IRASM - a technical assistance IAEA project and the prospects for technological irradiation in Romania (Serban Dobrescu); 2. IRASM facility - goal, present stage, perspectives (Corneliu C. Ponta); 3. Nuclear safeguards and radioprotection at IRASM (Ioan Valentin Moise); 4. Nuclear safeguard policy for IRASM (Mariana Irimia, Gabriela Vladescu, Ion Cristian); 5. Technological dosimetry at IRASM (Rodica Macrin, Rodica Moraru, Nicolae Valcov); 6. Quality assurance in building and exploiting IRASM (Ioana Domsa); 7. Current status of irradiation technologies in IFIN-HH (Mitica Dragusin); 8. Chemical-pharmaceutical, cosmetic and medical product sterilization (Paul Adrian, Eleonora Gheorghiu); 9. The concept of sterilization and the sterilization testing (Ileana Petcu

  16. A survey of ecological risk assessment at DOE facilities

    International Nuclear Information System (INIS)

    Barnthouse, L.W.; Bascietto, J.; Joseph, T.; Bilyard, G.

    1992-01-01

    The US Department of Energy (DOE) Risk-Based Standards Working Group is studying standard-setting and remedial action based on realistic estimates of human health and ecological risks. Federal and state regulations require DOE to assess ecological risks due to present and past operation of DOE facilities and ecological damage caused by remedial actions. Unfortunately, little technical guidance has been provided by regulatory agencies about how these assessments should be performed or what constitutes an adequate assessment. Active ecological research, environmental characterization, and ecological risk assessment programs are already underway at many locations. Some of these programs were established more than 30 years ago. Because of the strength of its existing programs and the depth of expertise available within the DOE complex, the agency is in a position to lead in developing ecological risk assessment procedures that are fully consistent with the general principles defined by EPA and that will ensure environmentally sound and cost-effective restoration of its sites. As a prelude to guidance development, the working group conducted a survey of ecological risk assessment activities at a subset of major DOE facilities. The survey was intended to (1) identify approaches now being used in ecological risk assessments performed by DOE staff and contractors at each site, (2) record successes and failures of these approaches, (3) identify new technical developments with potential for general application to many DOE facilities, and (4) identify major data needs, data resources, and methodological deficiencies

  17. Overview of established and emerging treatment technologies for polycyclic aromatic hydrocarbons at wood preserving facilities

    International Nuclear Information System (INIS)

    Shearon, M.D.

    1992-01-01

    The contamination of soil and groundwater by polycyclic aromatic hydrocarbons (PAHs) is common to wood preserving facilities and manufactured gas plants. Since the inception of RCRA and CERCLA, much attention has been focused upon the remediation of both active and defunct wood preserving facilities. The experiences gleaned from the use of proven technologies, and more importantly, the lessons being learned in the trials of emerging technologies on creosote-derived PAH clean-ups at wood preserving sites, should have direct bearing on the clean-up of similar contaminants at MGP sites. In this paper, a review of several remedial actions using waste removal/disposal, on-site incineration, and bioremediation will be presented. Additionally, emerging technologies for the treatment of PAH-contaminated soil and water will be reviewed. Lastly, recent information on risk assessment results for creosote sites and treated PAH waste will be discussed

  18. Scientific and Technological Facilities in CIEMAT; Las Instalaciones del CIEMAT

    Energy Technology Data Exchange (ETDEWEB)

    Vaquero Ortiz, E M

    2012-09-13

    The precise knowledge of the available Resources in an Organization, regardless the work it carries out, is an essential strategic enable to achieve its goals. Material Resources are part of the resources in an organization, The Material Resources expression includes a wide span of elements, because a Material Resource, as a generic concept, is each and every specific physical mean, utilised to get any of the Organization objectives. In case of CIEMAT, as Public Research Agency, its Material Resources consists of its scientific and technological facilities. These resources are the basis of this Agency numerous amount of technical capabilities, allowing it to carry out its research, development and innovation activity to transfer its results to the society later. This report is a summary on CIEMAT scientific and technological facilities, whose spread can help to show its scientific and technological capabilities, to enable the execution of a wide variety of projects and to open new external cooperation channels. In that list its possible to find the two Unique Scientific and Technological Infrastructures (ICTS) in Spain which are hold by CIEMAT and the Ionizing Radiations Metrology Laboratory (LMRI) which is the Spanish National Standards Laboratory for ionising radiations. (Author)

  19. Development of the Decommissioning Technology for Nuclear Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Kim, G. N.; Kim, S. G.

    2010-04-01

    The evaluation technology of decommissioning process must be developed and will be used for the ALARA planning tool of decommissioning process and demonstrated for tools of decommissioning equipment. Also, this technology can be used for tools workplaces with high work difficulty such as large-scale chemical plant, under water and space. The monitoring system for high alpha radioactive contamination measurement will be use in the high radioactivity decommissioning sites such as hot-cell or glove box. Also, it will be use in the general nuclear facilities as the radiation monitoring unit. The preparation technology of the radiation sensor for high radioactive contamination measurement will be transferred to the company for the industrialization. The remote monitoring system can prevent the workers exposure using the optical fiber to separate the sensor and electronics

  20. Development of the Decontamination and Decommissioning Technology for Nuclear Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Moon, J. K.; Won, C. H.

    2010-04-01

    The research results could be used for a design of a remote ablation decontamination system and ultimately applicable for an decontamination of high radiation facilities such as the DUPIC and PIEF. The evaluation technology of decommissioning process must be developed and will be used for the ALARA planning tool of decommissioning process and demonstrated for tools of decommissioning equipment. Also, this technology can be used for tools workplaces with high work difficulty such as large-scale chemical plant, under water and space. It is expected that the technology for a volume reduction and self-disposal of dismantled concrete wastes can be contributed to the establishment of a management plan for radioactive dismantled concrete wastes through the minimization of final waste volume

  1. Risk communication on the siting of radioactive waste management facility

    International Nuclear Information System (INIS)

    Okoshi, Minoru; Torii, Hiroyuki; Fujii, Yasuhiko

    2007-01-01

    Siting of radioactive waste management facilities frequently raise arguments among stakeholders such as a municipal government and the residents. Risk communication is one of the useful methods of promoting mutual understanding on related risks among stakeholders. In Finland and Sweden, siting selection procedures of repositories for spent nuclear fuels have been carried out successfully with risk communication. The success reasons are analyzed based on the interviews with those who belong to the regulatory authorities and nuclear industries in both countries. Also, in this paper, risk communication among the Japan Radioisotope Association (JRIA), a local government and the general public, which was carried out during the establishment process of additional radioactive waste treatment facilities in Takizawa Village, Iwate Prefecture, is analyzed based on articles in newspapers and interviews with persons concerned. The analysis results showed that good risk communication was not carried out because of the lack of confidence on the JRIA, decision making rules, enough communication chances and economic benefits. In order to make good use of these experiences for the future establishment of radioactive waste management facilities, the lessons learned from these cases are summarized and proposals for good risk communication (establishment of exploratory committee and technical support system for decision making, and measurements to increase familiarity of radioactive waste) are discussed. (author)

  2. Trial of risk assessment of a hypothetical nuclear facility

    International Nuclear Information System (INIS)

    Terao, Norichika; Suzuki, Mitsutoshi

    2013-01-01

    An equation for risk assessment in physical protection is shown by a probability of an adversary attack during a period time, P A , a probability of system effectiveness, P E , and consequence value, C. In addition, P E is shown as the multiplication of a probability of interruption of the facility, P I , by a probability of neutralization by response force, P N . In this study, it is assumed that an adversary assaults a hypothetical nuclear facility. The new quantification method about P A and P I in risk evaluation formula is devised, and risk assessment is attempted. In case of P A , the possibility of assaults against a nuclear facility is discussed by using terrorism data written in the open source database of terrorism, Global Terrorism Database (GTD), summarized by University of Maryland. In addition, it is discussed about P I by using the way of thinking of a risk assessment tool, EASI, developed by the Sandia National Laboratories (SNL). In the hypothetical nuclear facility, the performance of response force, sensors, and communication is expressed quantitatively by probability distribution based on some assumptions. (author)

  3. Seismic risk analysis for General Electric Plutonium Facility, Pleasanton, California

    International Nuclear Information System (INIS)

    1978-01-01

    This report presents the results of a seismic risk analysis that focuses on all possible sources of seismic activity, with the exception of the postulated Verona Fault. The best estimate curve indicates that the Vallecitos facility will experience 30% g with a return period of roughly 130 years and 60% g with a return period of roughly 700 years

  4. Application technology for optical fiber in nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Jong Min; Kim, Chul Jung; Lee, Yong Bum; Kim, Woong Ki; Yoon, Tae Seob; Sohn, Surg Won; Kim, Chang Hoi; Hwang, Suk Yong; Baik, Sung Hum; Kwon, Seong Ouk

    1987-12-01

    Lately, the optical fiber increasingly used in such adverse environments as nuclear power plant, radiation facilities because of their endurant properties against heat, radiation, corrosion, etc. Moreover, the transmission of signal through optical fiber does not induce interference from the electromagnetic wave. Basic theory about the optical fiber technology was studied and the developed techniques for nuclear facilities were reviewed. Since the radiations change the characteristics of the optical fiber, the effects of γ-ray irradiation on single mode and multimode optical fiber were examined. The image transmission system through optical fiber bundle was designed, constructed, and tested. Its software system was also updated. It can be used for remote internal inspection in adverse environment. (Author)

  5. Solar energy and conservation technologies for Caribbean Tourist Facilities (CTF)

    Science.gov (United States)

    The primary objectives of the Caribbean Tourist Facilities (CTF) project were to develop and publish materials and conduct workshops on solar energy and conservation technologies that would directly address the needs and interests of tourist facilities in the Caribbean basin. Past contacts with the Caribbean and US tourist industries indicated that decision-makers remained unconvinced that renewable technologies could have a significant impact on development and operation costs or that renewable energy products and services suited their needs. In order to assure that the materials and programs developed were responsive to the Caribbean tourist industry and U.S. conservation and renewable energy industries, marketing research with potential end users and the organizations and associations that serve those users was included as an underlying task in the project. The tasks outlined in the CTF Statement of Work included conference planning, gathering of field data, development of educational materials, and conduct of workshop(s). In addition to providing a chronicle of the fulfillment of those tasks, this final report includes suggestions for distributing the documents developed during the project, venues for future workshops, and other technology transfer and market influence strategies.

  6. Technology development risk assessment and mixed interests

    International Nuclear Information System (INIS)

    Borrelli, G.; Sartori, S.

    1992-05-01

    The main purpose of this work is to demonstrate by means of a critical analysis of the state-of-the-art in technological and environmental risk analysis and decision making, that risk and environmental management decisions involve heterogeneous groups of social actors, each representing conflicting interests. It is argued that risk analyses should therefore be based on social interaction and communication paradigma, as well as, on a new rational way of thinking concerning the optimum choice of suitable technological development strategies leading towards a publicly acceptable balance between national energy-economic strategic necessities and social and individual perception of risk

  7. Risk management study for the retired Hanford Site facilities: Risk management executive summary

    International Nuclear Information System (INIS)

    Coles, G.A.; Shultz, M.V.; Taylor, W.E.

    1994-02-01

    This document provides a cost-comparison evaluation for implementing certain risk-reduction measures and their effect on the overall risk of the 100 and 200 Area retired, surplus facilities. The evaluation is based on conditions that existed at the time the risk evaluation team performed facility investigations, and does not acknowledge risk-reduction measures that occurred soon after risk identification. This evaluation is one part of an overall risk management study for these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1450-km 2 Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30 km southeast of the 200 Area. This document is the first in a four volume series that comprise the risk management study for the retired, surplus facilities. Volume 2 is the risk evaluation work procedure; volume 3 provides the results for the risk evaluation; and volume 4 is the risk-reduction cost comparison

  8. Risk communication on the construction of radioactive waste treatment facility

    International Nuclear Information System (INIS)

    Okoshi, Minoru

    2005-01-01

    In this paper, risk communications among the Japan Radioisotope Association (JRIA), a local government and the general public which were carried out during the development process of a radioactive waste treatment facility in Takizawa Village, Iwate Prefecture are analyzed based on the articles of newspapers and the interviews with the concerned people. The analysis results show good risk communications were not carried out because of the absence of the confidence to the JRIA, decision making rules and the merits. In order to make good use of this experience for the future development of radioactive waste management facilities, the lessons learned from this case are summarized and the check lists for good risk communication are proposed. (author)

  9. Assessment of risk of potential exposures on facilities industries

    International Nuclear Information System (INIS)

    Leocadio, Joao Carlos

    2007-03-01

    This work develops a model to evaluate potential exposures on open facilities of industrial radiography in Brazil. This model will decisively contribute to optimize operational, radiological protection and safety procedures, to prevent radiation accidents and to reduce human errors in industrial radiography. The probabilistic safety assessment (PSA) methodology was very useful to assess potential exposures. The open facilities of industrial radiography were identified as the scenario to be analyzed in what concerns the evaluation of potential exposures, due to their high accidents indices. The results of the assessment of potential exposures confirm that the industrial radiography in Brazil is a high-risk practice as classified by the IAEA. The risk of potential exposure was estimated to be 40,5 x 10 -2 per year in Brazil, having as main consequences injuries to the workers' hands and arms. In the world scene, the consequences are worst, leading to fatalities of people, thus emphasizing the high risk of industrial radiography. (author)

  10. Radiological risks of transports to central waste management facilities

    International Nuclear Information System (INIS)

    Lange, F.

    1997-01-01

    Transports of radioactive waste from nuclear facilities have been a matter of frequent public concern in the recent past. News reports, protests and questions concerning the radiological risk tended to concentrate on transports to and from central waste management facilities, e.g. transports of spent fuel elements to reprocessing plants abroad (France, England), transports to intermediate storage sites (Ahaus, Gorleben), transports to operative (Morsleben) and projected (Konrad) final storage sites, and transports of vitrified high-activity waste from reprocessing plants to the intermediate storage site (Gorleben). (orig.) [de

  11. Proceeding of the 7. Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

    International Nuclear Information System (INIS)

    Hastowo, Hudi; Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Jujuratisbela, Uju; Aziz, Ferhat; Su'ud, Zaki; Suprawhardana, M. Salman

    2002-02-01

    The seventh proceedings of seminar safety and technology of nuclear power plant and nuclear facilities, held by National Nuclear Energy Agency. The Aims of seminar is to exchange and disseminate information about safety and nuclear Power Plant Technology and Nuclear Facilities consist of technology; high temperature reactor and application for national development sustain able and high technology. This seminar level all aspects technology, Power Reactor research reactor, high temperature reactor and nuclear facilities. The article is separated by index

  12. Managing risks during the construction of a power generation facility

    International Nuclear Information System (INIS)

    Loulakis, M.C.

    1992-01-01

    The construction of a power generation facility is a substantial undertaking that involves considerable risks to all parties involved. While contractors are accustomed to dealing with risks, construction owners are typically more naive about not only the risks they are assuming in the construction of a project, but also about the role they play on the project itself. Owners and developers of power facilities must understand at the outset that their role during the construction of a project is as integral to the success of the project as that of the designer and contractor. In addition, owners should also understand that there are virtually no risks on a construction project that cannot be shifted among the contracting parties as part of the business deal. Consequently, an owner may contractually be assuming the risks of (1) unusually severe weather, (2) unexpected subsurface conditions, (3) strikes at the turbine supplier's plant or (4) changes in law - as well as the increases in price and delays to project completion associated with such risks. In light of this, a prudent owner will evaluate more than just whether there is sufficient financing to complete the construction of a contemplated project. Prudent owners will conduct a risk management review of the project structure and the contracting terms, with the primary focus being (1) the identification and analysis of the most significant risks faced, (2) a determination of how such risks can be either mitigated or eliminated, and (3) the assessment of the financial exposure to the owner should the potential risk become a reality. This paper will present the framework that owners and developers of power generation projects can use in undertaking such a risk management review

  13. Maintenance and disassembly considerations for the Technology Demonstration Facility

    International Nuclear Information System (INIS)

    Spampinato, P.T.

    1983-01-01

    The Technology Demonstration Facility (TDF) is a tandem-mirror design concept carried out under the direction of Lawrence Livermore National Laboratory. It was conceived as a near-term device with a mission of developing engineering technology in a D-T fusion environment. Overall maintenance and component disassembly were among the responsibilities of the Fusion Engineering Design Center (FEDC). A configuration evolved that was based on the operational requirements of the components, as well as the requirements for their replacements. Component lifetime estimates were used to estimate the frequency and the number of replacements. In addition, it was determined that the need for remote handling equipment followed within 1.5 years after initial start-up, emphasizing the direct relationship between developing maintenance scenarios/equipment and the device configuration. Many of the scheduled maintenance operations were investigated to first order, and preliminary handling equipment concepts were developed

  14. Respect for autonomy and technological risks

    NARCIS (Netherlands)

    Asveld, L.

    2008-01-01

    Technological developments can undermine the autonomy of the individual. Autonomy is one's ability to make and act upon decisions according to one's own moral framework. Respect for autonomy dictates that risks should not be imposed on the individual without her consent. Technological developments

  15. Engaging At-Risk Students with Technology.

    Science.gov (United States)

    Duttweiler, Patricia Cloud

    1992-01-01

    Educational technology can be used to engage students in interesting activities through which teachers can present skills, concepts, and problems to be solved. At-risk students benefit from the investigation of relevant real world problems and the immediate feedback and privacy that technology affords. (EA)

  16. Emerging Technology Domains Risk Survey

    Science.gov (United States)

    2015-04-01

    Success 22 11.6 Exploitation Examples 22 11.7 Triage Table 22 12 Vehicle Autonomy ( Driverless Cars) 23 12.1 Introduction 23 12.2 Recommendation 24... Driverless Cars) 12.1 Introduction Autonomous vehicles have the ability to move without direct commands from an operator. They can navigate to a...lifestyle, and likely adoption mean that driverless cars will become an incredibly important technology. In addition, the potential for human harm and

  17. IFMIF-KEP. International fusion materials irradiation facility key element technology phase report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-03-01

    The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m{sup 2}, 20 dpa/y in Fe, in a volume of 500 cm{sup 3} and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration. (author)

  18. IFMIF-KEP. International fusion materials irradiation facility key element technology phase report

    International Nuclear Information System (INIS)

    2003-03-01

    The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m 2 , 20 dpa/y in Fe, in a volume of 500 cm 3 and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration. (author)

  19. 2017 Emerging Technology Domains Risk Survey

    Science.gov (United States)

    2017-10-01

    REV-03.18.2016.0 2017 Emerging Technology Domains Risk Survey Daniel Klinedinst Joel Land Kyle O’Meara October 2017 TECHNICAL REPORT CMU/SEI...Distribution Statement A: Approved for Public Release. Distribution is Unlimited. List of Tables Table 1: New and Emerging Technologies 2 Table 2: Security...Impact of New and Emerging Technologies 4 Table 3: Severity Classifications and Impact Scores 5 CMU/SEI-2017-TR-008 | SOFTWARE ENGINEERING

  20. Risk management program for the 283-W water treatment facility

    International Nuclear Information System (INIS)

    Green, W.E.

    1999-01-01

    This Risk Management (RM) Program covers the 283-W Water Treatment Facility (283W Facility), located in the 200 West Area of the Hanford Site. A RM Program is necessary for this facility because it stores chlorine, a listed substance, in excess of or has the potential to exceed the threshold quantities defined in Title 40 of the Code of Federal Regulations (CFR) Part 68 (EPA, 1998). The RM Program contains data that will be used to prepare a RM Plan, which is required by 40 CFR 68. The RM Plan is a summary of the RM Program information, contained within this document, and will be submitted to the U.S. Environmental Protection Agency (EPA) ultimately for distribution to the public. The RM Plan will be prepared and submitted separately from this document

  1. Spent Nuclear Fuel Alternative Technology Risk Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Perella, V.F.

    1999-11-29

    A Research Reactor Spent Nuclear Fuel Task Team (RRTT) was chartered by the Department of Energy (DOE) Office of Spent Fuel Management with the responsibility to recommend a course of action leading to a final technology selection for the interim management and ultimate disposition of the foreign and domestic aluminum-based research reactor spent nuclear fuel (SNF) under DOE''s jurisdiction. The RRTT evaluated eleven potential SNF management technologies and recommended that two technologies, direct co-disposal and an isotopic dilution alternative, either press and dilute or melt and dilute, be developed in parallel. Based upon that recommendation, the Westinghouse Savannah River Company (WSRC) organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and provide a WSRC recommendation to DOE for a preferred SNF alternative management technology. A technology risk assessment was conducted as a first step in this recommendation process to determine if either, or both, of the technologies posed significant risks that would make them unsuitable for further development. This report provides the results of that technology risk assessment.

  2. Spent Nuclear Fuel Alternative Technology Risk Assessment

    International Nuclear Information System (INIS)

    Perella, V.F.

    1999-01-01

    A Research Reactor Spent Nuclear Fuel Task Team (RRTT) was chartered by the Department of Energy (DOE) Office of Spent Fuel Management with the responsibility to recommend a course of action leading to a final technology selection for the interim management and ultimate disposition of the foreign and domestic aluminum-based research reactor spent nuclear fuel (SNF) under DOE''s jurisdiction. The RRTT evaluated eleven potential SNF management technologies and recommended that two technologies, direct co-disposal and an isotopic dilution alternative, either press and dilute or melt and dilute, be developed in parallel. Based upon that recommendation, the Westinghouse Savannah River Company (WSRC) organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and provide a WSRC recommendation to DOE for a preferred SNF alternative management technology. A technology risk assessment was conducted as a first step in this recommendation process to determine if either, or both, of the technologies posed significant risks that would make them unsuitable for further development. This report provides the results of that technology risk assessment

  3. Development of Decontamination and Decommissioning Technologies for Nuclear Facilities

    International Nuclear Information System (INIS)

    Moon, Jei Kwon; Lee, Kune Woo; Won, Hui Jun

    2010-04-01

    A laser ablation decontamination technology which is reportedly effective for a removal of fixed contaminants has been developed for three years as the first stage of the development. Lab scale experimental equipment was fabricated and the process variables have been assessed for determination of appropriate decontamination conditions at the laser wave lengths of 1,064 nm and 532 nm, respectively. The decontamination tests using radioactive specimens showed that the decontamination efficiency was about 100 which is quite a high value. An electrokinetic-flushing, an agglomeration leaching and a supercritical CO 2 soil decontamination technology were development for a decontamination of radioactive soil wastes from the decommissioned sites of the TRIGA research reactor and the uranium conversion facilities. An electrokinetic-flushing process was found to be effective for soil wastes aged for a long time and an agglomeration leaching process was effective for soil wastes of surface contamination. On the other hand, a supercritical CO 2 soil decontamination technology was found to be applicable for U or TRU bearing soil wastes. The remediation monitoring key technologies such as a representative sample taking and a measurement concept for the vertical distribution of radionuclides were developed for an assessment of the site remediation. Also an One-Dimensional Water Flow and Contaminant Transport in Unsaturated Zone (FTUNS) code was developed to interpretate the radionuclide migration in the unsaturated zone

  4. Enacting Risk in Independent Technological Innovation

    DEFF Research Database (Denmark)

    Berglund, Henrik; Hellström, Tomas

    2002-01-01

    The present study aims at investigating the role of risk in the activity of independent technological venturing. Altogether, 12 deep-interviews were conducted with technological entrepreneurs, who had taken part in the inventive, developmental and the commercialisation phases of a technology......-based innovation process. The interviews revealed a number of enactment approaches through which these innovators encountered and affected (dealt with or transformed) risk within the innovation process. Factors thus developed from the empirical material included human capital, pace and priority, the world moves...... for the benefit of innovation management....

  5. Risk - interface between law and technology

    International Nuclear Information System (INIS)

    1982-01-01

    Due to the rapid developments of technology, the subject of this congress has received central significance. It basically deals with the question of how advantages created by technology can be utilized by simultaneously avoiding any possible disadvantages that may arise from them. In the first part of this meeting, engineers present their considerations concerning risk assessment and risk comparisons, while the second part deals with the significance of scientific standardization. The third part elaborates on the evaluation of technical risks from the legal point of view. (orig./HP) [de

  6. Risk management plan for the National Ignition Facility

    International Nuclear Information System (INIS)

    Brereton, S.; Lane, M.; Smith, C.; Yatabe, J.

    1998-01-01

    The National Ignition Facility (NIF) is a U.S. Department of Energy inertial confinement laser fusion facility, currently under construction at the Lawrence Livermore National Laboratory (LLNL). NIF is a critical tool for the Department of Energy (DOE) science- based Stockpile Stewardship and Management Program. In addition, it represents a major step towards realizing inertial confinement fusion as a source of energy. The NIF will focus 192 laser beams onto spherical targets containing a mixture of deuterium and tritium, causing them to implode. This will create the high temperatures and pressures necessary for these targets to undergo fusion. The plan is for NIF to achieve ignition (i.e., self-heating of the fuel) and energy gain (i.e., more fusion energy produced than laser energy deposited) in the laboratory for the first time. A Risk Management Plan was prepared for the NIF design and construction Project. The plan was prepared in accordance with the DOE Life Cycle Asset Management Good Practice Guide. The objectives of the plan were to: (1) identify the risks to the completion of the Project in terms of meeting technical and regulatory requirements, cost, and schedule, (2) assess the risks in terms of likelihood of occurrence and their impact potential relative to technical performance, ES ampersand H (environment, safety and health), costs, and schedule, and (3) address each risk in terms of suitable risk management measures. Major risk elements were identified for the NIF Project. A risk assessment methodology was developed, which was utilized to rank the Project risks with respect to one another. Those elements presenting greater risk were readily identified by this process. This paper describes that methodology and the results

  7. Quality assurance system for sitting high risk facilities

    International Nuclear Information System (INIS)

    Rodriguez, Aymee; Peralta, Jose L.; Fernandez, Manuel

    1999-01-01

    The paper shows how we have conceived and designed the quality assurance system for the site selection process of an area for sitting the facility of high risk in correspondence with the approved methodology. The results obtained in the implementation of the system have permitted the satisfactory performance of each one the expected stage, defining the most favorable sectors in order to continue the studies of the repository site for the disposal of low and intermedium. (author)

  8. Technology-Induced Risks in History

    Science.gov (United States)

    Rabkin, Ya.

    Our perception of risk contains three main aspects: (1) probability of the risk occurring; (2) the extent of possible damage; (3) the degree of voluntary or involuntary exposure to risk. History of risk assessment has been traced in several areas, such as transportation, and has largely focused on insurance. Construction projects constitute one of the oldest areas of technology where accidents continue to occur, while health has always been a fragile commodity. Urbanization has multiplied the risks of illness and death, while natural catastrophes, though still frightening, have ceded their central place to technology-based disasters in the Western perceptions of risk. The human has become the main source of danger to the very survival of the planet. The Enlightenment utopia of scientific progress resulting in social and moral progress of humanity has collided with the awareness of new technology induced risks. Life on Earth began without humans, and it may end without them. Our civilization is the first that faces an end to be brought about by our own technological ingenuity.

  9. Use of risk information to safety regulation. Fabrication facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    A procedure of ISA (Integrated Safety Analysis) for uranium fuel fabrication/enrichment facilities has been under the development aiming to utilize risk information for safety regulations in this project. Activities in the fiscal year 2012 are summarized in the paper. There are two major activities in the year. First one is a study on ISA procedure for external events such as earthquakes. Second one is that for chemical consequences such as UF6 and HF. Other than the activities a fundamental study on a policy of utilizing risk information was conducted. The outline and results are provided in the chapter 1 and 2 respectively. (author)

  10. Health risks in perspective: Judging health risks of energy technologies

    Energy Technology Data Exchange (ETDEWEB)

    Rowe, M.D.

    1992-09-18

    Almost daily, Americans receive reports from the mass news media about some new and frightening risk to health and welfare. Most such reports emphasize the newsworthiness of the risks -- the possibility of a crisis, disagreements among experts, how things happened, who is responsible for fixing them, how much will it cost, conflict among parties involved, etc. As a rule, the magnitudes of the risks, or the difficulty of estimating those magnitudes, have limited newsworthiness, and so they are not mentioned. Because of this emphasis in the news media, most people outside the risk assessment community must judge the relative significance of the various risks to which we all are exposed with only that information deemed newsworthy by reporters. This information is biased and shows risks in isolation. There is no basis for understanding and comparing the relative importance of risks among themselves, or for comparing one risk, perhaps a new or newly-discovered one, in the field of all risks. The purpose of this report is to provide perspective on the various risks to which we are routinely exposed. It serves as a basis for understanding the meaning of quantitative risk estimates and for comparing new or newly-discovered risks with other, better-understood risks. Specific emphasis is placed on health risks of energy technologies.

  11. D and D Toolbox Project - Technology Demonstration of Fixatives Applied to Hot Cell Facilities via Remote Sprayer Platforms

    International Nuclear Information System (INIS)

    Lagos, L.; Shoffner, P.; Espinosa, E.; Pena, G.; Kirk, P.; Conley, T.

    2009-01-01

    The objective of the US Department of Energy Office of Environmental Management's (DOE-EM's) D and D Toolbox Project is to use an integrated systems approach to develop a suite of decontamination and decommissioning (D and D) technologies, a D and D toolbox, that can be readily used across the DOE complex to improve safety, reduce technical risks, and limit uncertainty within D and D operations. Florida International University's Applied Research Center (FIU-ARC) is supporting this initiative by identifying technologies suitable to meet specific facility D and D requirements, assessing the readiness of those technologies for field deployment, and conducting technology demonstrations of selected technologies at FIU-ARC facilities in Miami, Florida. To meet the technology gap challenge for a technology to remotely apply strippable/fixative coatings, FIU-ARC identified and demonstrated of a remote fixative sprayer platform. During this process, FIU-ARC worked closely with the Oak Ridge National Laboratory in the selection of typical fixatives and in the design of a hot cell mockup facility for demonstrations at FIUARC. For this demonstration and for future demonstrations, FIU-ARC built a hot cell mockup facility at the FIU-ARC Technology Demonstration/Evaluation site in Miami, Florida. FIU-ARC selected the International Climbing Machines' (ICM's) Robotic Climber to perform this technology demonstration. The selected technology was demonstrated at the hot cell mockup facility at FIU-ARC during the week of November 10, 2008. Fixative products typically used inside hot cells were investigated and selected for this remote application. The fixatives tested included Sherwin Williams' Promar 200 and DTM paints and Bartlett's Polymeric Barrier System (PBS). The technology evaluation documented the ability of the remote system to spray fixative products on horizontal and vertical concrete surfaces. The technology performance, cost, and health and safety issues were evaluated

  12. Proceedings of the international workshop on hadron facility technology

    Energy Technology Data Exchange (ETDEWEB)

    Thiessen, H.A. (comp.)

    1987-12-01

    The conference included papers on facility plans, beam dynamics, accelerator hardware, and experimental facilities. Individual abstracts were prepared for 43 papers in the conference proceedings. (LEW)

  13. Shielding technology for high energy radiation production facility

    International Nuclear Information System (INIS)

    Lee, Byung Chul; Kim, Heon Il

    2004-06-01

    In order to develop shielding technology for high energy radiation production facility, references and data for high energy neutron shielding are searched and collected, and calculations to obtain the characteristics of neutron shield materials are performed. For the evaluation of characteristics of neutron shield material, it is chosen not only general shield materials such as concrete, polyethylene, etc., but also KAERI developed neutron shields of High Density PolyEthylene (HDPE) mixed with boron compound (B 2 O 3 , H 2 BO 3 , Borax). Neutron attenuation coefficients for these materials are obtained for later use in shielding design. The effect of source shape and source angular distribution on the shielding characteristics for several shield materials is examined. This effect can contribute to create shielding concept in case of no detail source information. It is also evaluated the effect of the arrangement of shield materials using current shield materials. With these results, conceptual shielding design for PET cyclotron is performed. The shielding composite using HDPE and concrete is selected to meet the target dose rate outside the composite, and the dose evaluation is performed by configuring the facility room conceptually. From the result, the proper shield configuration for this PET cyclotron is proposed

  14. 6 CFR 27.200 - Information regarding security risk for a chemical facility.

    Science.gov (United States)

    2010-01-01

    ... chemical facility. 27.200 Section 27.200 Domestic Security DEPARTMENT OF HOMELAND SECURITY, OFFICE OF THE SECRETARY CHEMICAL FACILITY ANTI-TERRORISM STANDARDS Chemical Facility Security Program § 27.200 Information regarding security risk for a chemical facility. (a) Information to determine security risk. In order to...

  15. Safety analysis and risk assessment of the National Ignition Facility

    International Nuclear Information System (INIS)

    Brereton, S.; McLouth, L.; Odell, B.

    1996-01-01

    The National Ignition Facility (NIF) is a proposed U.S. Department of Energy inertial confinement laser fusion facility. The candidate sites for locating the NIF are: Los Alamos National Laboratory, Sandia National Laboratory, the Nevada Test Site, and Lawrence Livermore National Laboratory (LLNL), the preferred site. The NIF will operate by focusing 192 laser beams onto a tiny deuterium-tritium target located at the center of a spherical target chamber. The NIF mission is to achieve inertial confinement fusion (ICF) ignition, access physical conditions in matter of interest to nuclear weapons physics, provide an above ground simulation capability for nuclear weapons effects testing, and contribute to the development of inertial fusion for electrical power production. The NIF has been classified as a radiological, low hazard facility on the basis of a preliminary hazards analysis and according to the DOE methodology for facility classification. This requires that a safety analysis be prepared under DOE Order 5481.1B, Safety Analysis and Review System. A draft Preliminary Safety Analysis Report (PSAR) has been written, and this will be finalized later in 1996. This paper summarizes the safety issues associated with the operation of the NIF and the methodology used to study them. It provides a summary of the methodology, an overview of the hazards, estimates maximum routine and accidental exposures for the preferred site of LLNL, and concludes that the risks from NIF operations are low

  16. Evaluating health risks in communities near nuclear facilities

    International Nuclear Information System (INIS)

    Ruttenber, A.J.

    1992-01-01

    Over the past 10 years, epidemiologic studies have been the most popular approach to examining health risks to populations near nuclear facilities. A review of these studies has identified a number of methodologic problems, particularly with regard to establishing causal relations between radiation exposure and disease. Recently, in the United States, dose reconstruction and risk assessment projects have been conducted as alternatives to epidemiologic studies. This paper reviews the problems associated with epidemiologic studies and discusses how dose reconstruction and risk assessment can serve as alternatives to epidemiologic studies. Examples are also provided to demonstrate how these techniques can be used to explore the feasibility of epidemiologic studies, and how dose reconstruction data can improve the quality of epidemiologic studies

  17. Benefits and risks of smart home technologies

    OpenAIRE

    Wilson, Charlie; Hargreaves, Tom; Hauxwell-Baldwin, Richard

    2017-01-01

    Smart homes are a priority area of strategic energy planning and national policy. The market adoption of smart home technologies (SHTs) relies on prospective users perceiving clear benefits with acceptable levels of risk. This paper characterises the perceived benefits and risks of SHTs from multiple perspectives. A representative national survey of UK homeowners (n=1025) finds prospective users have positive perceptions of the multiple functionality of SHTs including energy management. Cedin...

  18. Introduction to Technology Export License of Nuclear Facility

    International Nuclear Information System (INIS)

    Seo, Hana; Lee, Chansuh; Shin, Donghoon

    2014-01-01

    In this regime, the Nuclear Safety and Security Commission (NSSC) has authority on final decision making. And the Korea Institute of Nuclear nonproliferation and Control (KINAC) has missions to review the classification and export licensing technically. In principle, classification and export licensing are applied and reviewed individually. However, the number of application for classification and licensing has increased geometrically in the last three years. This is largely a due to the contract that the Republic of Korea (ROK) has finalized to build the UAE Barakah Nuclear Power Plant (BNPP) and Jordan Research and Training Reactor (JRTR). This circumstance brought an administrative burden for the government and related institutes as well as stakeholders. This article introduces the law related to the 'Technology Export License of Nuclear Facility' which was developed and legislated to improve the efficiency and effectiveness of commodities classification and export licensing. This system could significantly reduce the licensing burden for transferring the technologies. However, the classification and license on this system are still requested when transferring the goods. Therefore, KINAC will continue to figure out the needs for the stakeholders and keep searching for solutions to problems inherent in the industry

  19. Introduction to Technology Export License of Nuclear Facility

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Hana; Lee, Chansuh; Shin, Donghoon [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2014-05-15

    In this regime, the Nuclear Safety and Security Commission (NSSC) has authority on final decision making. And the Korea Institute of Nuclear nonproliferation and Control (KINAC) has missions to review the classification and export licensing technically. In principle, classification and export licensing are applied and reviewed individually. However, the number of application for classification and licensing has increased geometrically in the last three years. This is largely a due to the contract that the Republic of Korea (ROK) has finalized to build the UAE Barakah Nuclear Power Plant (BNPP) and Jordan Research and Training Reactor (JRTR). This circumstance brought an administrative burden for the government and related institutes as well as stakeholders. This article introduces the law related to the 'Technology Export License of Nuclear Facility' which was developed and legislated to improve the efficiency and effectiveness of commodities classification and export licensing. This system could significantly reduce the licensing burden for transferring the technologies. However, the classification and license on this system are still requested when transferring the goods. Therefore, KINAC will continue to figure out the needs for the stakeholders and keep searching for solutions to problems inherent in the industry.

  20. Tritium research and technology facilities at the JRC-Ispra

    International Nuclear Information System (INIS)

    Dworschak, H.; Mannone, F.; Perujo, A.; Pierini, G.; Reiter, F.; Vassallo, G.; Viola, A.; Camposilvan, J.; Douglas, K.; Grassi, G.; Lolli Ceroni, P.; Simonetta, A.; Spelta, B.

    1990-01-01

    A set of experiments which are of prominent interest for the development of nuclear fusion technology in Europe are planned by the JRC-Ispra for the near future, in the frame of experimental activities to be performed in ETHEL, the European Tritium Handling Experimental Laboratory under construction at the Ispra site. These experiments already included for the most part as JRC-Task Action Sheets in the 1989-1991 European Technology Programme Actions will initiate in ETHEL on a fully active laboratory scale starting mid-1991. They will concern the following research areas: Recycling of tritium from first wall materials; Tritium recovery from water cooled Pb-17Li blankets; Detritiation of ventilation atmospheres; Plasma exhaust processing; Tritiazed waste management. In view of fully active tritium experiments in ETHEL and to obtain information of the basic processes involved, since 1985 preparatory experimental studies are being performed at the JRC-Ispra laboratories using hydrogen and deuterium. Furthermore, always with regard to ETHEL experiments, particular attention is given to possible technical and managerial problems which potentially may arise in this context. To identify at an early stage such problems a questionnaire has been developed and distributed to researchers in conjunction with an ETHEL information packet. The questionnaire demands information regarding the scope, design and operation of the intended experiment as well as planning and required support to be supplied by ETHEL. A brief description of experimental preparatory studies and future tritium handling experiments in ETHEL as well of the ETHEL facility is here presented. (orig.)

  1. Seismic risk analysis for the Westinghouse Electric facility, Cheswick, Pennsylvania

    International Nuclear Information System (INIS)

    1977-01-01

    This report presents the results of a detailed seismic risk analysis of the Westinghouse Electric plutonium fuel development facility at Cheswick, Pennsylvania. This report focuses on earthquakes. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases. Because of the aseismicity of the region around the site, an analysis different from the conventional closest approach in a tectonic province was adapted. Earthquakes as far from the site as 1,000 km were included, as were the possibility of earthquakes at the site. In addition, various uncertainties in the input were explicitly considered in the analysis. For example, allowance was made for both the uncertainty in predicting maximum possible earthquakes in the region and the effect of the dispersion of data about the best fit attenuation relation. The attenuation relationship is derived from two of the most recent, advanced studies relating earthquake intensity reports and acceleration. Results of the risk analysis, which include a Bayesian estimate of the uncertainties, are presented as return period accelerations. The best estimate curve indicates that the Westinghouse facility will experience 0.05 g every 220 years and 0.10 g every 1400 years. The accelerations are very insensitive to the details of the source region geometries or the historical earthquake statistics in each region and each of the source regions contributes almost equally to the cumulative risk at the site

  2. Benefits and risks of smart home technologies

    International Nuclear Information System (INIS)

    Wilson, Charlie; Hargreaves, Tom; Hauxwell-Baldwin, Richard

    2017-01-01

    Smart homes are a priority area of strategic energy planning and national policy. The market adoption of smart home technologies (SHTs) relies on prospective users perceiving clear benefits with acceptable levels of risk. This paper characterises the perceived benefits and risks of SHTs from multiple perspectives. A representative national survey of UK homeowners (n=1025) finds prospective users have positive perceptions of the multiple functionality of SHTs including energy management. Ceding autonomy and independence in the home for increased technological control are the main perceived risks. An additional survey of actual SHT users (n=42) participating in a smart home field trial identifies the key role of early adopters in lowering perceived SHT risks for the mass market. Content analysis of SHT marketing material (n=62) finds the SHT industry are insufficiently emphasising measures to build consumer confidence on data security and privacy. Policymakers can play an important role in mitigating perceived risks, and supporting the energy-management potential of a smart-home future. Policy measures to support SHT market development include design and operating standards, guidelines on data and privacy, quality control, and in situ research programmes. Policy experiences with domestic energy efficiency technologies and with national smart meter roll-outs offer useful precedents. - Highlights: • Representative national survey of prospective smart home users. • Comparative analysis of three datasets to analyse perceived benefits and risks of smart home technologies. • Distinctive characteristics identified of early adopters who seed market growth. • Comparison of user perceptions with industry marketing. • Detailed policy recommendations to support energy benefits of smart home technologies.

  3. Probabilistic aspects of risk analyses for hazardous facilities

    International Nuclear Information System (INIS)

    Morici, A.; Valeri, A.; Zaffiro, C.

    1989-01-01

    The work described in the paper discusses the aspects of the risk analysis concerned with the use of the probabilistic methodology, in order to see how this approach may affect the risk management of industrial hazardous facilities. To this purpose reference is done to the Probabilistic Risk Assessment (PRA) of nuclear power plants. The paper points out that even though the public aversion towards nuclear risks is still far from being removed, the probabilistic approach may provide a sound support to the decision making and authorization process for any industrial activity implying risk for the environment and the public health. It is opinion of the authors that the probabilistic techniques have been developed to a great level of sophistication in the nuclear industry and provided much more experience in this field than in others. For some particular areas of the nuclear applications, such as the plant reliability and the plant response to the accidents, these techniques have reached a sufficient level of maturity and so some results have been usefully taken as a measure of the safety level of the plant itself. The use of some limited safety goals is regarded as a relevant item of the nuclear licensing process. The paper claims that it is time now that these methods would be applied with equal success to other hazardous facilities, and makes some comparative consideration on the differences of these plants with nuclear power plants in order to understand the effect of these differences on the PRA results and on the use one intends to make with them. (author)

  4. Natural-technological risk assessment and management

    Science.gov (United States)

    Burova, Valentina; Frolova, Nina

    2016-04-01

    EM-DAT statistical data on human impact and economic damages in the 1st semester 2015 are the highest since 2011: 41% of disasters were floods, responsible for 39% of economic damage and 7% of events were earthquakes responsible for 59% of total death toll. This suggests that disaster risk assessment and management still need to be improved and stay the principle issue in national and international related programs. The paper investigates the risk assessment and management practice in the Russian Federation at different levels. The method is proposed to identify the territories characterized by integrated natural-technological hazard. The maps of the Russian Federation zoning according to the integrated natural-technological hazard level are presented, as well as the procedure of updating the integrated hazard level taking into account the activity of separate processes. Special attention is paid to data bases on past natural and technological processes consequences, which are used for verification of current hazard estimation. The examples of natural-technological risk zoning for the country and some regions territory are presented. Different output risk indexes: both social and economic, are estimated taking into account requirements of end-users. In order to increase the safety of population of the Russian Federation the trans-boundaries hazards are also taken into account.

  5. Analysis of Blade Fragment Risk at a Wind Energy Facility

    Energy Technology Data Exchange (ETDEWEB)

    Simms, David A [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Larwood, Scott [University of the Pacific

    2018-04-06

    An analysis was performed to determine the risk posed by wind turbine fragments on roads and buildings at the National Wind Technology Center at the National Renewable Energy Laboratory. The authors used a previously developed model of fragment trajectory and took into account the wind speed/direction distribution at the site and the probability of rotor failure. The risk was assessed by determining the likelihood of impact and related consequences. For both the roads and buildings, the risk varied from low to routine, which was considered acceptable. The analysis was compared with previous recommendations on wind turbine setback distances. The results showed that a setback to property lines of 2 times the overall turbine height would be acceptable. However, the setback to dwellings should probably be increased from 3 to 3.5 times the overall turbine height for an acceptable risk.

  6. Development of Demonstration Facility Design Technology for Advanced Nuclear Fuel Cycle Process

    International Nuclear Information System (INIS)

    Cho, Il Je; You, G. S.; Choung, W. M.

    2010-04-01

    The main objective of this R and D is to develop the PRIDE (PyRoprocess Integrated inactive DEmonstration) facility for engineering-scale inactive test using fresh uranium, and to establish the design requirements of the ESPF (Engineering Scale Pyroprocess Facility) for active demonstration of the pyroprocess. Pyroprocess technology, which is applicable to GEN-IV systems as one of the fuel cycle options, is a solution of the spent fuel accumulation problems. PRIDE Facility, pyroprocess mock-up facility, is the first facility that is operated in inert atmosphere in the country. By using the facility, the functional requirements and validity of pyroprocess technology and facility related to the advanced fuel cycle can be verified with a low cost. Then, PRIDE will contribute to evaluate the technology viability, proliferation resistance and possibility of commercialization of the pyroprocess technology. The PRIDE evaluation data, such as performance evaluation data of equipment and operation experiences, will be directly utilized for the design of ESPF

  7. Unanticipated potential cancer risk near metal recycling facilities

    Energy Technology Data Exchange (ETDEWEB)

    Raun, Loren, E-mail: raun@rice.edu [Department of Statistics, MS 138, Rice University, P.O. Box 1892, Houston, TX 77251-1892 (United States); Pepple, Karl, E-mail: pepple.karl@epa.gov [State and Local Programs Group, Air Quality Policy Division, Office of Air Quality Planning and Standards, Policy, Analysis, and Communications Staff, Mail Drop C404-03, U.S. EPA, Research Triangle Park, NC 27711 (United States); Hoyt, Daniel, E-mail: hoyt.daniel@epa.gov [Air Surveillance Section, US EPA, Region 6, 6EN-AS, 1445 Ross Avenue, Dallas, TX 75202-2733 (United States); Richner, Donald, E-mail: Donald.Richner@houstontx.gov [Houston Department of Health and Human Services, Bureau of Pollution Control and Prevention, 7411 Park Place Blvd., Houston, TX 77087 (United States); Blanco, Arturo, E-mail: arturo.blanco@houstontx.gov [Pollution Control and Prevention, Environmental Health Division, Houston Department of Health and Human Services, 7411 Park Place Blvd., Houston, TX 77087 (United States); Li, Jiao, E-mail: jiao.li@rice.edu [Wiess School of Natural Science, Rice University, 6100 Main St., Houston, TX 77005 (United States)

    2013-07-15

    Metal recycling is an important growing industry. Prior to this study, area sources consisting of metal recycling facilities fell in a category of limited regulatory scrutiny because of assumed low levels of annual emissions. Initiating with community complaints of nuisance from smoke, dust and odor, the Houston Department of Health and Human Services (HDHHS) began a monitoring program outside metal recycler facilities and found metal particulates in outdoor ambient air at levels which could pose a carcinogenic human health risk. In a study of five similar metal recycler facilities which used a torch cutting process, air downwind and outside the facility was sampled for eight hours between 6 and 10 times each over 18 months using a mobile laboratory. Ten background locations were also sampled. Iron, manganese, copper, chromium, nickel, lead, cobalt, cadmium and mercury were detected downwind of the metal recyclers at frequencies ranging from 100% of the time for iron to 2% of the time for mercury. Of these metals, chromium, nickel, lead, cobalt, cadmium and mercury were not detected in any sample in the background. Two pairs of samples were analyzed for total chromium and hexavalent chromium to establish a ratio of the fraction of hexavalent chromium in total chromium. This fraction was used to estimate hexavalent chromium at all locations. The carcinogenic risk posed to a residential receptor from metal particulate matter concentrations in the ambient air attributed to the metal recyclers was estimated from each of the five facilities in an effort to rank the importance of this source and inform the need for further investigation. The total risk from these area sources ranged from an increased cancer risk of 1 in 1,000,000 to 6 in 10,000 using the 95th upper confidence limit of the mean of the carcinogenic metal particulate matter concentration, assuming the point of the exposure is the sample location for a residential receptor after accounting for wind direction

  8. Unanticipated potential cancer risk near metal recycling facilities

    International Nuclear Information System (INIS)

    Raun, Loren; Pepple, Karl; Hoyt, Daniel; Richner, Donald; Blanco, Arturo; Li, Jiao

    2013-01-01

    Metal recycling is an important growing industry. Prior to this study, area sources consisting of metal recycling facilities fell in a category of limited regulatory scrutiny because of assumed low levels of annual emissions. Initiating with community complaints of nuisance from smoke, dust and odor, the Houston Department of Health and Human Services (HDHHS) began a monitoring program outside metal recycler facilities and found metal particulates in outdoor ambient air at levels which could pose a carcinogenic human health risk. In a study of five similar metal recycler facilities which used a torch cutting process, air downwind and outside the facility was sampled for eight hours between 6 and 10 times each over 18 months using a mobile laboratory. Ten background locations were also sampled. Iron, manganese, copper, chromium, nickel, lead, cobalt, cadmium and mercury were detected downwind of the metal recyclers at frequencies ranging from 100% of the time for iron to 2% of the time for mercury. Of these metals, chromium, nickel, lead, cobalt, cadmium and mercury were not detected in any sample in the background. Two pairs of samples were analyzed for total chromium and hexavalent chromium to establish a ratio of the fraction of hexavalent chromium in total chromium. This fraction was used to estimate hexavalent chromium at all locations. The carcinogenic risk posed to a residential receptor from metal particulate matter concentrations in the ambient air attributed to the metal recyclers was estimated from each of the five facilities in an effort to rank the importance of this source and inform the need for further investigation. The total risk from these area sources ranged from an increased cancer risk of 1 in 1,000,000 to 6 in 10,000 using the 95th upper confidence limit of the mean of the carcinogenic metal particulate matter concentration, assuming the point of the exposure is the sample location for a residential receptor after accounting for wind direction

  9. Technological stigmatism, risk perception, and truth

    Energy Technology Data Exchange (ETDEWEB)

    Garrick, B.John

    1998-01-01

    Technological stigmas can be a source of confusion and misunderstandings of the effect on public health and safety of technological activities. The result can be a gross waste of national resources to fix the 'stigma' rather than the real problem. Fueling technological stigmas has become a visible activity, especially among non-technical professionals. Further, it is not clear that these same critics are accountable for their influence on policy and practices that may adversely affect people's lives and financial resources. Their bad news of alleged high risk and incompetent technologists is more appealing to the press than the more technical and apparently boring news of finding engineering solutions to real problems. The issue of technological stigma is especially visible in relation to the environmental and safety effects of the nuclear and chemical industries. These industries are in an extremely defensive position because the stigmatizes put much more emphasis on their risks than on their benefits to society. There is the genuine threat of the denial of important technologies in the nuclear and chemical fields and a resulting loss of lives and resources. The actions required to better tell the whole cost-risk-benefit story of specific technologies have to come from all of the groups involved. The critics and stigmatizers need to be more accountable for their assertions, the technologists need to involve the public more in their consideration of technological solutions to environmental and safety issues, and the press needs to present all of the facts rather than just the sensational or 'outrage' part of the story.

  10. Technological stigmatism, risk perception, and truth

    International Nuclear Information System (INIS)

    Garrick, B.John

    1998-01-01

    Technological stigmas can be a source of confusion and misunderstandings of the effect on public health and safety of technological activities. The result can be a gross waste of national resources to fix the 'stigma' rather than the real problem. Fueling technological stigmas has become a visible activity, especially among non-technical professionals. Further, it is not clear that these same critics are accountable for their influence on policy and practices that may adversely affect people's lives and financial resources. Their bad news of alleged high risk and incompetent technologists is more appealing to the press than the more technical and apparently boring news of finding engineering solutions to real problems. The issue of technological stigma is especially visible in relation to the environmental and safety effects of the nuclear and chemical industries. These industries are in an extremely defensive position because the stigmatizes put much more emphasis on their risks than on their benefits to society. There is the genuine threat of the denial of important technologies in the nuclear and chemical fields and a resulting loss of lives and resources. The actions required to better tell the whole cost-risk-benefit story of specific technologies have to come from all of the groups involved. The critics and stigmatizers need to be more accountable for their assertions, the technologists need to involve the public more in their consideration of technological solutions to environmental and safety issues, and the press needs to present all of the facts rather than just the sensational or 'outrage' part of the story

  11. 48 CFR 3004.470 - Security requirements for access to unclassified facilities, Information Technology resources...

    Science.gov (United States)

    2010-10-01

    ... access to unclassified facilities, Information Technology resources, and sensitive information. 3004.470... Technology resources, and sensitive information. ... ACQUISITION REGULATION (HSAR) GENERAL ADMINISTRATIVE MATTERS Safeguarding Classified and Sensitive Information...

  12. The development of robot application technology in nuclear facilities

    International Nuclear Information System (INIS)

    Kim, Seung Ho; Lee, Jong Min; Kim, Chang Hoe; Kim, Byung Soo; Sohn, Surg Won; Hwoang, Suk Yeoung; Lee, Yong Bum; Kim, Woong Ki

    1992-12-01

    The objective of this project is to establish the basic technologies for advanced robotic systems operated in unstructured environment. The developed robotic system, which is remotely controlled, is expected to reduce the radiation dosage for workers who do the maintenance, inspection, and repairing work in nuclear facilities. The two major work scopes of this project in this year are to study the control scheme of advanced robotic system and develop a mobile robot. An inverse kinematic algorithm of 7 degrees of freedom anthropomorphic manipulator is investigated for dexterous control. Extended closed-loop schemes for solving the inverse kinematics of the redundant manipulator have been proposed and decentralized adaptive controller was designed by utilizing a new cartesian space controller. Control architecture of neural network has been developed, which has a strong capability on solving the kinematics of manipulator. The planetary wheel assembly has been implemented in the design to be suitable for plant. The design of manipulator has been implemented to operate with the battery power in the mobile system. This project will continue to be a major technical driver, with nuclear plant maintenance and waste management applications in conjunction with 'Long-term nuclear development program' over the next decade. (Author)

  13. Risk assessment research and technology assessment

    International Nuclear Information System (INIS)

    Albach, H.; Schade, D.; Sinn, H.

    1991-01-01

    The concepts and approaches for technology assessment, the targets and scientific principles, as well as recognizable deficits and recommendations concerning purposeful strategies for the promotion of this research field require a dialog between those concerned. Conception, deficits, and the necessary measures for risk assessment research and technology assessment were discussed as well as ethical aspects. The problematic nature of using organisms altered through genetic engineering in the open land, traffic and transport, site restoration, nuclear energy, and isotope applications were subjects particularly dealt with. (DG) [de

  14. Citizen perceptions of information flow around a nuclear facility: A study in risk communication

    International Nuclear Information System (INIS)

    Price, M.O.

    1997-01-01

    Responses of focus group members from the region around a Nuclear Facility provide the data for this qualitative study concerning citizen perceptions of available site information. Analyses of three of the focus group discussion questions and the answers they elicited showed a dominant perception among participants of insufficient easily available information about the site. These respondents also indicated that most of them obtain site information through mass media and hearsay, that many lack trust in the information they have and would trust only an independent entity to provide accurate information. A new area in communication studies, variously called environmental risk communication, risk communication and health risk communication, continues to evolve among those working in various allied disciplines, some far removed from communication. As science attempts to solve environmental problems caused by technological advances, this field acquires numerous practitioners. Some of these risk communication experts may however, be overlooking basic and necessary components of effective communication, because their expertise is in another discipline. One result of this can be communication breakdown in which those involved, assume that meaning is shared, when in fact the opposite is true. This paper seeks to clarify a necessary ingredient of effective interpersonal risk communication, using data obtained from citizens living around one of the nation's nuclear facilities as an example

  15. Information Technology Sector Baseline Risk Assessment

    Science.gov (United States)

    2009-08-01

    alternative root be economically advantageous , an actor’s ability to exploit market forces and create an alternative root would be significantly improved...conduct their operations. Therefore, a loss or disruption to Internet services would not be advantageous for the desired outcomes of these syndicates.26... eCommerce Service loss or disruption [C] Traffic Redirection [C] = Undesired consequence Information Technology Sector Baseline Risk Assessment

  16. Applying new safeguards technology to existing nuclear facilities

    International Nuclear Information System (INIS)

    Johnson, C.E.; Wagner, E.P.

    1979-01-01

    The application and operation of safeguards instrumentation in a facility containing special nuclear material is most successful when the installation is designed for the operation of the specific facility. Experience at the Idaho National Engineering Laboratory demonstrates that installation designs must consider both Safeguards and Production requirements of specific facilities. Equipment selection and installation design influenced by the training and experience of production operations and safeguards personnel at a specific facility help assure successful installation, reliable operation, and minimal operator training. This minimizes impacts on existing plant production activities while maximizing utility of the safeguards information obtained

  17. Applying new safeguards technology to existing nuclear facilities

    International Nuclear Information System (INIS)

    Harris, W.J.; Wagner, E.P.

    1979-01-01

    The application and operation of safeguards instrumentation in a facility containing special nuclear material is most successful when the installation is desinged for the operation of the specific facility. Experience at the Idaho National Engineering Laboratory demonstrates that installation designs must consider both safeguards and production requirements of specific facilities. Equipment selection and installation design influenced by the training and experience of production operations and safeguards personnel at a specific facility help assure successful installation, reliable operation, and minimal operator training. This minimizes impacts on existing plant production activities while maximizing utility of the safeguards information obtained

  18. Needs of Advanced Safeguards Technologies for Future Nuclear Fuel Cycle (FNFC) Facilities and a Trial Application of SBD Concept to Facility Design of a Hypothetical FNFC Facility

    International Nuclear Information System (INIS)

    Seya, M.; Hajima, R.; Nishimori, N.; Hayakawa, T.; Kikuzawa, N.; Shizuma, T.; Fujiwara, M.

    2010-01-01

    Some of future nuclear fuel cycle (FNFC) facilities are supposed to have the characteristic features of very large throughput of plutonium, low decontamination reprocessing (no purification process; existence of certain amount of fission products (FP) in all process material), full minor actinides (MA) recycle, and treatment of MOX with FP and MA in fuel fabrication. In addition, the following international safeguards requirements have to be taken into account for safeguards approaches of the FNFC facilities. -Application of integrated safeguards (IS) approach; -Remote (unattended) verification; - 'Safeguards by Design' (SBD) concept. These features and requirements compel us to develop advanced technologies, which are not emerged yet. In order to realize the SBD, facility designers have to know important parts of design information on advanced safeguards systems before starting the facility design. The SBD concept requires not only early start of R and D of advanced safeguards technologies (before starting preliminary design of the facility) but also interaction steps between researchers working on safeguards systems and nuclear facility designers. The interaction steps are follows. Step-1; researchers show images of advanced safeguards systems to facility designers based on their research. Step-2; facility designers take important design information on safeguards systems into process systems of demonstration (or test) facility. Step-3; demonstration and improvement of both systems based on the conceptual design. Step-4; Construction of a FNFC facility with the advanced safeguards systems We present a trial application of the SBD concept to a hypothetical FNFC facility with an advanced hybrid K-edge densitometer and a Pu NDA system for spent nuclear fuel assembly using laser Compton scattering (LCS) X-rays and γ-rays and other advanced safeguards systems. (author)

  19. Seismic risk analysis for the Atomics International Nuclear Materials Development Facility, Santa Susana California

    International Nuclear Information System (INIS)

    1978-01-01

    This report presents the results of a detailed seismic risk analysis of the Nuclear Materials Development Facility (NMDF) operated by Atomics International at Santa Susana, California. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases including the USGS, California Institute of Technology and NEIS data bases. The resulting seismic record, covering the period 1969 to 1977, was used to identify all possible sources of seismicity that could affect the site. The best estimate curve indicates that the facility will experience 30% g with a return period of 55 years and 60% g with a return period of 750 years

  20. Seismic risk analysis for the Atomics International Nuclear Materials Development Facility, Santa Susana California

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-29

    This report presents the results of a detailed seismic risk analysis of the Nuclear Materials Development Facility (NMDF) operated by Atomics International at Santa Susana, California. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases including the USGS, California Institute of Technology and NEIS data bases. The resulting seismic record, covering the period 1969 to 1977, was used to identify all possible sources of seismicity that could affect the site. The best estimate curve indicates that the facility will experience 30% g with a return period of 55 years and 60% g with a return period of 750 years.

  1. Affect and Acceptability: Exploring Teachers' Technology-Related Risk Perceptions

    Science.gov (United States)

    Howard, Sarah K.

    2011-01-01

    Educational change, such as technology integration, involves risk. Teachers are encouraged to "take risks", but what risks they are asked to take and how do they perceive these risks? Developing an understanding of teachers' technology-related risk perceptions can help explain their choices and behaviours. This paper presents a way to…

  2. IFMIF (International Fusion Materials Irradiation Facility) key element technology phase task description

    Energy Technology Data Exchange (ETDEWEB)

    Ida, M.; Nakamura, H.; Sugimoto, M.; Yutani, T.; Takeuchi, H. [eds.] [Japan Atomic Energy Research Inst., Tokai Research Establishment, Fusion Neutron Laboratory, Tokai, Ibaraki (Japan)

    2000-08-01

    In 2000, a 3 year Key Element technology Phase (KEP) of the International Fusion Materials Irradiation Facility (IFMIF) has been initiated to reduce the key technology risk factors needed to achieve continuous wave (CW) beam with the desired current and energy and to reach the corresponding power handling capabilities in the liquid lithium target system. In the KEP, the IFMIF team (EU, Japan, Russian Federation, US) will perform required tasks. The contents of the tasks are described in the task description sheet. As the KEP tasks, the IFMIF team have proposed 27 tasks for Test Facilities, 12 tasks for Target, 26 tasks for Accelerator and 18 tasks for Design Integration. The task description by RF is not yet available. The task items and task descriptions may be added or revised with the progress of KEP activities. These task description sheets have been compiled in this report. After 3 years KEP, the results of the KEP tasks will be reviewed. Following the KEP, 3 years Engineering Validation Phase (EVP) will continue for IFMIF construction. (author)

  3. Fairness hypothesis and managing the risks of societal technology choices

    International Nuclear Information System (INIS)

    Cantor, R.; Rayner, S.

    1986-08-01

    Much of the literature on risk perception and management has asked how society should resolve the question, ''How safe is safe enough'' There has been political and technical disagreement over the types of answers that may be given, as well as over the social values attached to perceived probabilities and magnitudes of various outcomes. Despite controversy, there seems to have been a large measure of consensus that, ''How safe is safe enough'' is the right question to ask. This paper sets out to question that assumption. Various ingenious techniques of risk analysis have sought to discover the real risks inherent in various activities, but from a sociocultural viewpoint it can be seen that no single answer can be given to the problem of adequate safety in a complex society which contains a wide variety of perceptual biases about danger, expectations of the good life, and levels of demand for safety. The paper argues that, from a societal risk-management perspective, we should be addressing a different range of questions that views societal risk as a whole rather than as the sum of individual hazards. Resolving the question, ''How safe is safe enough'' is less important in making societal technology choices than ''How fair is safe enough?'' A recent empirical pilot study is reported which explored the fairness hypotheses in the context of nuclear power. The results indicate that the process of technology choice should recognize explicitly the preferred principles different parties hold with respect to obtaining consent from those affected by the risks, distributing the liabilities, and justifying trust in the relevant institutions. The paper closes with a discussion of future prospects for the fairness approach in areas such as noxious facility siting

  4. Risk assessment of mitigated domino scenarios in process facilities

    International Nuclear Information System (INIS)

    Landucci, Gabriele; Necci, Amos; Antonioni, Giacomo; Argenti, Francesca; Cozzani, Valerio

    2017-01-01

    The propagation of accidents among process units may lead to severe cascading events or domino effects with catastrophic consequences. Prevention, mitigation and management of domino scenarios is of utmost importance and may be achieved in industrial facilities through the adoption of multiple safety layers. The present study was aimed at developing an innovative methodology to address the quantitative risk assessment (QRA) of domino scenarios accounting for the presence and role of safety barriers. Based on the expected performance of safety barriers, a dedicated event tree analysis allowed the identification and the assessment of the frequencies of the different end-point events deriving from unmitigated and partially mitigated domino chains. Specific criteria were introduced in consequence analysis to consider the mitigation effects of end-point scenarios deriving from safety barriers. Individual and societal risk indexes were calculated accounting for safety barriers and the mitigated scenarios that may result from their actions. The application of the methodology to case-studies of industrial interest proved the importance of introducing a specific systematic and quantitative analysis of safety barrier performance when addressing escalation leading to domino effect. - Highlights: • A methodology was developed to account for safety barrier performance in escalation prevention. • The methodology allows quantitative assessment accounting for safety barrier performance. • A detailed analysis of transient mitigated scenarios is allowed by the developed procedure. • The procedure allows accounting for safety barrier performance in QRA of domino scenarios. • An important reduction in the risk due to domino scenarios is evidenced when considering safety barriers.

  5. Information technology project risk management in Peru

    OpenAIRE

    Del Carpio Gallegos, Javier

    2014-01-01

    This article shows how some principles, uses, and practices of risk management are applied in information technology projects in Peru; in the last four years, in representative sectors like manufacturing, banking, information and communications, academics institutions, construction, government, consulting, services, and others. El presente artículo muestra algunos principios, usos y prácticas de cómo la gestión de riesgos de proyectos de tecnología se ha llevado a cabo en los últimos cuatr...

  6. Comparison of risk-dominant scenario assumptions for several TRU waste facilities in the DOE complex

    International Nuclear Information System (INIS)

    Foppe, T.L.; Marx, D.R.

    1999-01-01

    In order to gain a risk management perspective, the DOE Rocky Flats Field Office (RFFO) initiated a survey of other DOE sites regarding risks from potential accidents associated with transuranic (TRU) storage and/or processing facilities. Recently-approved authorization basis documents at the Rocky Flats Environmental Technology Site (RFETS) have been based on the DOE Standard 3011 risk assessment methodology with three qualitative estimates of frequency of occurrence and quantitative estimates of radiological consequences to the collocated worker and the public binned into three severity levels. Risk Class 1 and 2 events after application of controls to prevent or mitigate the accident are designated as risk-dominant scenarios. Accident Evaluation Guidelines for selection of Technical Safety Requirements (TSRs) are based on the frequency and consequence bin assignments to identify controls that can be credited to reduce risk to Risk Class 3 or 4, or that are credited for Risk Class 1 and 2 scenarios that cannot be further reduced. This methodology resulted in several risk-dominant scenarios for either the collocated worker or the public that warranted consideration on whether additional controls should be implemented. RFFO requested the survey because of these high estimates of risks that are primarily due to design characteristics of RFETS TRU waste facilities (i.e., Butler-type buildings without a ventilation and filtration system, and a relatively short distance to the Site boundary). Accident analysis methodologies and key assumptions are being compared for the DOE sites responding to the survey. This includes type of accidents that are risk dominant (e.g., drum explosion, material handling breach, fires, natural phenomena, external events, etc.), source term evaluation (e.g., radionuclide material-at-risk, chemical and physical form, damage ratio, airborne release fraction, respirable fraction, leakpath factors), dispersion analysis (e.g., meteorological

  7. The role of new technologies in risks from natural hazards

    International Nuclear Information System (INIS)

    Gardner, J.S.

    1982-01-01

    The author places some prior natural hazards research into the context of risk from new technologies to show that some beneficial technologies increase the risk from natural hazards. He examines the role of new technologies in risks from natural hazards in a historical perspective, using examples from research on mountain hazards

  8. Control technology for radioactive emissions to the atmosphere at US Department of Energy facilities

    Energy Technology Data Exchange (ETDEWEB)

    Moore, E.B.

    1984-10-01

    The purpose of this report is to provide information to the US Environmental Protection agency (EPA) on existing technology for the control of radionuclide emissions into the air from US Department of Energy (DOE) facilities, and to provide EPA with information on possible additional control technologies that could be used to further reduce these emissions. Included in this report are generic discussions of emission control technologies for particulates, iodine, rare gases, and tritium. Also included are specific discussions of existing emission control technologies at 25 DOE facilities. Potential additional emission control technologies are discussed for 14 of these facilities. The facilities discussed were selected by EPA on the basis of preliminary radiation pathway analyses. 170 references, 131 figures, 104 tables.

  9. Control technology for radioactive emissions to the atmosphere at US Department of Energy facilities

    International Nuclear Information System (INIS)

    Moore, E.B.

    1984-10-01

    The purpose of this report is to provide information to the US Environmental Protection agency (EPA) on existing technology for the control of radionuclide emissions into the air from US Department of Energy (DOE) facilities, and to provide EPA with information on possible additional control technologies that could be used to further reduce these emissions. Included in this report are generic discussions of emission control technologies for particulates, iodine, rare gases, and tritium. Also included are specific discussions of existing emission control technologies at 25 DOE facilities. Potential additional emission control technologies are discussed for 14 of these facilities. The facilities discussed were selected by EPA on the basis of preliminary radiation pathway analyses. 170 references, 131 figures, 104 tables

  10. Facilities & Technology: The Transformation of "Campus." APPA Thought Leaders Series 2015

    Science.gov (United States)

    APPA: Association of Higher Education Facilities Officers, 2015

    2015-01-01

    The 2015 Thought Leaders symposium focused on the topic of "Facilities & Technology: The Transformation of 'Campus.'" Educational institutions that master new technologies will have an edge in the increasingly competitive higher education landscape. This report discusses the factors related to integrating technology and the campus…

  11. Proactive information provision for reducing social construct risk of nuclear facility

    International Nuclear Information System (INIS)

    Kitamura, Masaharu; Takahashi, Makoto; Hashizume, Hidetoshi; Shiraishi, Natsuki; Yagi, Ekou

    2006-01-01

    Outlines of, and the empirical observations from, an action research project aiming at improvement of relationship between nuclear community and the public have been reported in this paper. Ultimate goal of the project is effective reduction of social construct risk of nuclear power plants. As an initial approach to the goal, a proactive information provision scheme has been designed based on the knowledge acquired during our previous attempt of public communication named repetitive dialogue forum. The information contents consistent with the actual need of local citizens has been derived from the previous experiences and provided in the present project. Although the project is in its incipient stage, the observations are informative enough to develop the project further to attain the ultimate purpose of reducing the social construct component of technological risk of nuclear facilities. (author)

  12. Development of demonstration facility design technology for advanced nuclear fuel cycle process

    International Nuclear Information System (INIS)

    Cho, Il Je; You, G. S.; Choung, W. M.; Lee, E. P.; Hong, D. H.; Lee, W. K.; Ku, J. H.; Moon, S. I.; Kwon, K. C.; Lee, K. I. and other

    2012-04-01

    PRIDE Facility, pyroprocess mock-up facility, is the first facility that is operated in inert atmosphere in the country. By using the facility, the functional requirements and validity of pyroprocess technology and facility related to the advanced fuel cycle can be verified with a low cost. Then, PRIDE will contribute to evaluate the technology viability, proliferation resistance and possibility of commercialization of the pyroprocess technology. It is essential to develop design technologies for the advanced nuclear fuel cycle demonstration facilities and complete the detailed design of PRIDE facility with capabilities of the stringent inert atmosphere control, fully remote operation which are necessary to develop the high-temperature molten salts technology. For these, it is necessary to design the essential equipment of large scale inert cell structure and the control system to maintain the inert atmosphere, and evaluate the safety. To construct the hot cell system which is appropriate for pyroprocess, some design technologies should be developed, which include safety evaluation for effective operation and maintenance, radiation safety analysis for hot cell, structural analysis, environmental evaluation, HVAC systems and electric equipment

  13. Risk of hypertensive disorders in pregnancies following assisted reproductive technology

    DEFF Research Database (Denmark)

    Opdahl, S; Henningsen, A A; Tiitinen, A

    2015-01-01

    STUDY QUESTION: Is the risk of hypertensive disorders in pregnancies conceived following specific assisted reproductive technology (ART) procedures different from the risk in spontaneously conceived (SC) pregnancies? SUMMARY ANSWER: ART pregnancies had a higher risk of hypertensive disorders, in ...

  14. Use of risk-matrix methods in the radiation safety analysis of PET/CT facilities

    International Nuclear Information System (INIS)

    Calderón Marín, Carlos F.; González González, Joaquín J.; Quesada Cepero, Waldo; Sinconegui Gómez, Belkys; Solá Rodríguez, Yeline; Duménigo Ámbar, Cruz; Guerrero Cancio, Mayka

    2016-01-01

    produce high exposure in public and the high concentration of 68 Ge in the circumvention of the Ge-Ga generator. To reduce the frequency of high-risk IEs, the facilities were designed following the recommendations given in internationally recognized methodologies, such as the AAPM TG 108, NCRP No 107 and IAEA Human Health Series 11 reports. The productions of 68 Ga radiopharmaceuticals according to the limits established in the European Pharmacopoeia [11,12]. RFMs and RCMs with a greater impact on risk reduction (> 10% of IEs) are related to staff training, the existence of procedures and protocols of good clinical practice, and periodic external / internal audits. The personnel responsible for the implementation of the service, the acceptance of the instrumentation and its maintenance were trained in centers of experience in clinical practice with this technology.Conclusions. The IEs were identified and the accident risks were evaluated in Patients, Public and TOEs. Because most IEs originate in human errors, staff training is strongly recommended prior to inclusion in the work team, as well as the implementation of QC programs for the release of 68 Ga radiopharmaceutical production. The implementation of QA programs will increase the security of the center.

  15. The construction technology of Chinese ancient city drainage facilities

    Science.gov (United States)

    Hequn, Li; Yufengyun

    2018-03-01

    In ancient china, according to the local natural environment, a variety of drainage facilities were built in order to excrete rainwater, domestic sewage, production wastewater and so on. These drainage facilities were mainly made of pottery, bricks, wood, stone, etc. For example, ceramic water pipelines, buried in the ground, connect together one by one, and there was a slight drop from one end to the other in favor of drainage. These measures can also be used for reference in today’s urban drainage and flood control.

  16. Application of information and communication technology facilities in ...

    African Journals Online (AJOL)

    Information Impact | Jorunal of Information and Knowledge Management

    Findings also revealed that inadequate training of staff on ICT application to technical services; poor electricity supply and insufficient fund were some of the challenges plaguing the application of ICT facilities to technical unit of the library. The study recommends that there should be adequate straining of staff, provision of ...

  17. Hong kong chemical waste treatment facilities: a technology overview

    Energy Technology Data Exchange (ETDEWEB)

    Siuwang, Chu [Enviropace Ltd., Hong Kong (Hong Kong)

    1993-12-31

    The effective management of chemical and industrial wastes represents one of the most pressing environmental problems confronting the Hong Kong community. In 1990, the Hong Kong government contracted Enviropace Limited for the design, construction and operation of a Chemical Waste Treatment Facility. The treatment and disposal processes, their integration and management are the subject of discussion in this paper

  18. Hong kong chemical waste treatment facilities: a technology overview

    Energy Technology Data Exchange (ETDEWEB)

    Siuwang, Chu [Enviropace Ltd., Hong Kong (Hong Kong)

    1994-12-31

    The effective management of chemical and industrial wastes represents one of the most pressing environmental problems confronting the Hong Kong community. In 1990, the Hong Kong government contracted Enviropace Limited for the design, construction and operation of a Chemical Waste Treatment Facility. The treatment and disposal processes, their integration and management are the subject of discussion in this paper

  19. The Mixed Waste Management Facility: Technology selection and implementation plan, Part 2, Support processes

    International Nuclear Information System (INIS)

    Streit, R.D.; Couture, S.A.

    1995-03-01

    The purpose of this document is to establish the foundation for the selection and implementation of technologies to be demonstrated in the Mixed Waste Management Facility, and to select the technologies for initial pilot-scale demonstration. Criteria are defined for judging demonstration technologies, and the framework for future technology selection is established. On the basis of these criteria, an initial suite of technologies was chosen, and the demonstration implementation scheme was developed. Part 1, previously released, addresses the selection of the primary processes. Part II addresses process support systems that are considered ''demonstration technologies.'' Other support technologies, e.g., facility off-gas, receiving and shipping, and water treatment, while part of the integrated demonstration, use best available commercial equipment and are not selected against the demonstration technology criteria

  20. Periodic inspections of lightning protection systems in intermediate storage facilities of nuclear technological plants

    International Nuclear Information System (INIS)

    Witzel, Andre; Schulz, Olav

    2013-01-01

    Especially for nuclear technological plants, periodic inspections of lightning protection systems are of great importance. This article shows the sequence of maintenance programs using the examples of the intermediate storage facilities of the nuclear technological plants Grohnde and Unterweser as well as the central intermediate storage facility in Gorleben and gives a description of the extensive measures of inspecting the external and internal lightning protection and the global earth termination system.

  1. Safeguarding uranium enrichment facilities. Review and analysis of the status of safeguards technology for uranium enrichment facilities

    International Nuclear Information System (INIS)

    1977-09-01

    The objective of this paper is to examine critically the diversion potential at uranium enrichment facilities and to outline a basic safeguards strategy which counters all identified hazards as completely as possible yet with a minimum of non-essential redundancy. Where existing technology does not appear to be adequate for effective safeguards, the limitations are examined, and suggestions for further R and D effort are made. Parts of this report are generally applicable to all currently known enrichment processes, while other parts are specifically directed toward facilities based on the gas centrifuge process. It is hoped that additional sections discussing a safeguards strategy for gas diffusion facilities can be added later. It should be emphasized that this is a technical report, and does not reflect any legal positions. The safeguards strategy and subsequent inspection procedures are intended as guidelines, not as negotiating positions

  2. Accident risks in nuclear facilities (a bibliography with abstracts). Report for 1964-Sep 77

    International Nuclear Information System (INIS)

    Grooms, D.W.

    1977-10-01

    The bibliography presents risk analysis and hazards evaluation of the design, construction and operation of nuclear facilities, including the risk and hazards of transporting radioactive materials to and from these facilities. Radiological calculations for environmental effects of nuclear accidents are also included

  3. Accident risks in nuclear facilities (a bibliography with abstracts). Report for 1964-Sep 76

    International Nuclear Information System (INIS)

    Grooms, D.W.

    1976-10-01

    The bibliography presents risk analysis and hazards evaluation of the design, construction and operation of nuclear facilities including the risk and hazards of transporting radioactive materials to and from these facilities. Radiological calculations for environmental effects of nuclear accidents are included. (This updated bibliography contains 195 abstracts, 64 of which are new entries to the previous edition.)

  4. Technology requirements to be addressed by the NASA Lewis Research Center Cryogenic Fluid Management Facility program

    Science.gov (United States)

    Aydelott, J. C.; Rudland, R. S.

    1985-01-01

    The NASA Lewis Research Center is responsible for the planning and execution of a scientific program which will provide advance in space cryogenic fluid management technology. A number of future space missions were identified that require or could benefit from this technology. These fluid management technology needs were prioritized and a shuttle attached reuseable test bed, the cryogenic fluid management facility (CFMF), is being designed to provide the experimental data necessary for the technology development effort.

  5. Nuclear material facilities - security systems and technology R and D trends

    International Nuclear Information System (INIS)

    Ellis, D.; Steele, B.

    2002-01-01

    Full text: In the US, physical security research and development (R and D) during the 1970s and 1980s created a body of technology and systems engineering that largely defined the industry for several decades. However, despite today's terrorists threats and risks, the overall funding of new and innovative physical security solutions is relatively very small. Such factors constraining physical security R and D include the expansion of overall security responsibilities, the emphasis on programmatic and business performance, in addition to evolving (mis)perceptions that 'the problem has been solved' or that 'anyone can do security'. Underlying these factors, the lack of robust standards and certifications has limited the development and application of physical security products, systems, and services. The research and development of new security technologies must be evaluated against very demanding constraints - including costs/benefits, emerging threats, and policies. Going forward, the goal will be to create a more comprehensive approach to physical security of nuclear material facilities that matches evolving threats and that will complement the transition to an integrated security/operations management environment. Such a management model evaluates the additional value of increasing security alternatives in addition to determining trade-offs between the programmatic mission and security issues. Correspondingly, more explicit and strategically useful measures must be developed to determine importance that, in turn, will influence security-related R and D efforts. The research and development of security technologies should be based upon identified needs and requirements resulting from a systematic analysis of the threat and other conditions. In particular, security technologies and systems must be evaluated in terms of current and long-term impacts. Such needs are (will be) diverse and will depend upon sustained research investments in a broad range of technologies

  6. Information and communications technology facilities at the tertiary level education in some urban universities in Bangladesh

    Directory of Open Access Journals (Sweden)

    F. M. Shahriar

    2016-07-01

    Full Text Available With the advent of digitalization, information and communications technology facilities have become an indispensable part of education especially at the universities. This study has been undertaken with dual purposes - to find the existing scenario of information and communications technology facilities and to gauge the perception of the students onthe quality of those facilities - at the universities in Bangladesh. To that end, a survey was conducted on the undergraduate and graduate students of 9 private and public universities. To assess the quality of information and communications technology services, participants’ views on various aspects like the sufficiency of computers, availability of required software, maintenance and troubleshooting, internet and data sharing facilities, etc. were collected and analyzed. The study finds that although students are on the happier side with the information and communications technology installations and equipment, they are fairly unhappy about the maintenance services and internet facilities available at their universities. It gives some valuable insights about the information and communications technology facilities scenario at the universities that can be taken into consideration while planning future action plan and development of information and communications technology at the universities in Bangladesh.

  7. Operation technology of air treatment system in nuclear facilities

    CERN Document Server

    Chun, Y B; Hwong, Y H; Lee, H K; Min, D K; Park, K J; Uom, S H; Yang, S Y

    2001-01-01

    Effective operation techniques were reviewed on the air treatment system to protect the personnel in nuclear facilities from the contamination of radio-active particles and to keep the environment clear. Nuclear air treatment system consisted of the ventilation and filtering system was characterized by some test. Measurement of air velocity of blowing/exhaust fan in the ventilation system, leak tests of HEPA filters in the filtering, and measurement of pressure difference between the areas defined by radiation level were conducted. The results acquired form the measurements were reflected directly for the operation of air treatment. In the abnormal state of virus parts of devices composted of the system, the repairing method, maintenance and performance test were also employed in operating effectively the air treatment system. These measuring results and techniques can be available to the operation of air treatment system of PIEF as well as the other nuclear facilities in KAERI.

  8. Radiation facilities and irradiation technology for food irradiation

    International Nuclear Information System (INIS)

    Sunaga, Hiromi

    2005-01-01

    Progress made during these 30 years in the field of radiation treatment of food is reviewed by describing features of the process including elementary processes, quality control of the products and the dosimetric techniques widely employed. The Co-60 gamma-ray irradiation facilities to be used for radiation-sterilization of medical supplies and food preservation are presented. For electron beam irradiation, accelerators for processing with the energy from 0.3 to 10 MeV are generally employed. The electron-guns, the method of acceleration such as rectification, types of acceleration as Cockcroft-Walton, dynamitron, or linear acceleration and X-ray producing facility, with various countermeasures for safety management, are briefly explained. The concepts of dose and traceability are given. The dosimeters including reference dosimeter and routine ones with validation are explained. (S. Ohno)

  9. The technological safety in facilities that manage radioactive sources

    International Nuclear Information System (INIS)

    Lizcano, D.

    2014-10-01

    The sealed radioactive sources are used inside a wide range of applications in the medicine, industry and investigation around the world. These sources can contain a great radionuclides variety, exhibiting a wide spectrum of activities and radiological half lives. This way, we can find pattern sources of radionuclides as Americium-241, Plutonium-238, Plutonium-239, Thorium-228 and Thorium-230, etc., with some activity of kBq in research laboratories, Iridium-192 and Cesium-137 sources used in brachytherapy with GBq activities, until sources with P Bq activities in industrial irradiators of Cobalt-60 and Cesium-137. This document approach the physical safety that entities like the IAEA recommends for the facilities that contain sealed sources, especially the measures that are taking in the Instituto Nacional de Investigaciones Nucleares (ININ) and others government facilities. (Author)

  10. Analysis of the formation, expression, and economic impacts of risk perceptions associated with nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Allison, T.; Hunter, S.; Calzonetti, F.J.

    1992-10-01

    This report investigates how communities hosting nuclear facilities form and express perceptions of risk and how these risk perceptions affect local economic development. Information was collected from site visits and interviews with plant personnel, officials of local and state agencies, and community activists in the hosting communities. Six commercial nuclear fuel production facilities and five nuclear facilities operated for the US Department of Energy by private contractors were chosen for analysis. The results presented in the report indicate that the nature of risk perceptions depends on a number of factors. These factors are (1) level of communication by plant officials within the local community, (2) track record of the facility. operator, (3) process through which community and state officials receive information and form opinions, (4) level of economic links each plant has with the local community, and (15) physical characteristics of the facility itself. This report finds that in the communities studied, adverse ask perceptions have not affected business location decisions, employment levels in the local community, tourism, or agricultural development. On the basis of case-study findings, this report recommends that nuclear facility siting programs take the following observations into account when addressing perceptions of risk. First, the quality of a facility`s participation with community activists, interest groups, and state agencies helps to determine the level of perceived risk within a community. Second, the development of strong economic links between nuclear facilities and their host communities will produce a higher level of acceptance of the nuclear facilities.

  11. Proceedings of the 9. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

    International Nuclear Information System (INIS)

    Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Aziz, Ferhat; Untoro, Pudji; Su'ud, Zaki; Zarkasi, Amin Santoso; Lasman, As Natio

    2003-08-01

    The ninth proceedings of seminar safety and technology of nuclear power plant and nuclear facilities held by National Nuclear Energy Agency and PLN-JTK. The aims of seminar is to exchange and disseminate information about Safety and Nuclear Power Plant Technology and Nuclear Facilities consist of Technology High Temperature Reactor and Application for National Development Sustainable and High Technology. This seminar cover all aspects Technology, Power Reactor, Research Reactor High Temperature Reactor and Nuclear Facilities. There are 20 articles have separated index

  12. Risk management for operations of the LANL Critical Experiments Facility

    International Nuclear Information System (INIS)

    Paternoster, R.; Butterfield, K.

    1998-01-01

    The Los Alamos Critical Experiments Facility (LACEF) currently operates two burst reactors (Godiva-IV and Skua), one solution assembly [the Solution High-Energy Burst Assembly (SHEBA)], two fast-spectrum benchmark assemblies (Flattop and Big Ten), and five general-purpose remote assembly machines that may be configured with nuclear materials and assembled by remote control. Special nuclear materials storage vaults support these and other operations at the site. With this diverse set of operations, several approaches are possible in the analysis and management of risk. The most conservative approach would be to write a safety analysis report (SAR) for each assembly and experiment. A more cost-effective approach is to analyze the probability and consequences of several classes of operations representative of operations on each critical assembly machine and envelope the bounding case accidents. Although the neutron physics of these machines varies widely, the operations performed at LACEF fall into four operational modes: steady-state mode, approach-to-critical mode, prompt burst mode, and nuclear material operations, which can include critical assembly fuel loading. The operational sequences of each mode are very nearly identical, whether operated on one assembly machine or another. The use of an envelope approach to accident analysis is facilitated by the use of classes of operations and the use of bounding case consequence analysis. A simple fault tree analysis of operational modes helps resolve which operations are sensitive to human error and which are initiated by hardware of software failures. Where possible, these errors and failures are blocked by TSR LCOs. Future work will determine the probability of accidents with various initiators

  13. [Technology transfer to the facility for production of medicines].

    Science.gov (United States)

    Beregovykh, V V; Spitskiĭ, O P

    2013-01-01

    Innovation development of pharmaceutical industry is close connected to knowledge transfer going to each subsequent life cycle phase of medicinal product. Formal regulation of technology and knowledge transfer is essential for achievement high quality during production of medicines designed during development phase. Conceptual tools, approaches and requirements are considered that are necessary for knowledge and technology transfer across all the life cycle phases of medicines. They are based on scientific knowledge of medicinal products and take into account both international and Russian regulations in the area of development, production and distribution of medicines. Importance of taking into consideration all aspects related to quality of medicines in all steps of technology transfer is shown. An approach is described for technology transfer organization for Russian pharmaceutical manufacturers based on international guides in this area.

  14. Improving Operational Risk Management Using Business Performance Management Technologies

    OpenAIRE

    Bram Pieket Weeserik; Marco Spruit

    2018-01-01

    Operational Risk Management (ORM) comprises the continuous management of risks resulting from: human actions, internal processes, systems, and external events. With increasing requirements, complexity and a growing volume of risks, information systems provide benefits for integrating risk management activities and optimizing performance. Business Performance Management (BPM) technologies are believed to provide a solution for effective Operational Risk Management by offering several combined ...

  15. Bioaerosol releases from compost facilities: Evaluating passive and active source terms at a green waste facility for improved risk assessments

    Science.gov (United States)

    Taha, M. P. M.; Drew, G. H.; Longhurst, P. J.; Smith, R.; Pollard, S. J. T.

    The passive and active release of bioaerosols during green waste composting, measured at source is reported for a commercial composting facility in South East (SE) England as part of a research programme focused on improving risk assessments at composting facilities. Aspergillus fumigatus and actinomycetes concentrations of 9.8-36.8×10 6 and 18.9-36.0×10 6 cfu m -3, respectively, measured during the active turning of green waste compost, were typically 3-log higher than previously reported concentrations from static compost windrows. Source depletion curves constructed for A. fumigatus during compost turning and modelled using SCREEN3 suggest that bioaerosol concentrations could reduce to background concentrations of 10 3 cfu m -3 within 100 m of this site. Authentic source term data produced from this study will help to refine the risk assessment methodologies that support improved permitting of compost facilities.

  16. Conceptual design of a technology development facility (TDF)

    International Nuclear Information System (INIS)

    Doggett, J.N.; Damm, C.C.

    1981-01-01

    We have developed a concept for employing a single-cell mirror machine in a facility for testing and developing fusion reactor materials, components, and subsystems in a fusion reactor environment. Our approach is similar to that of the 1974 FERF study, except that we have added an auxiliary thermal-barrier cell at each end of the yin-yang magnet. In this way, we provide for plasma microstability by confining a warm plasma component between potential peaks at each end of the device (just as in the tandem mirror with auxiliary barrier cells) while we further improve confinement by the inherent reduction in ambipolar potential drop in the central cell

  17. A singular facility scientific technological to promote the hydrogen economy

    International Nuclear Information System (INIS)

    Montes, M.

    2010-01-01

    Declining fossil fuel reserves raises concerns about new energy resources that will lead to energy systems based on distributed generation and active distribution systems that require new energy storage systems. Hydrogen is a good candidate to operate as storage and as energy carrier that still needs scientific and technological breakthroughs to facilitate their integration into this new energy culture. Spain has supported numerous public-private cooperative efforts that have culminated in the creation of the National Center for Hydrogen Technology Experiment and Fuel Cells. (Author)

  18. Analysis of the formation, expression, and economic impacts of risk perceptions associated with nuclear facilities

    International Nuclear Information System (INIS)

    Allison, T.; Hunter, S.; Calzonetti, F.J.

    1992-10-01

    This report investigates how communities hosting nuclear facilities form and express perceptions of risk and how these risk perceptions affect local economic development. Information was collected from site visits and interviews with plant personnel, officials of local and state agencies, and community activists in the hosting communities. Six commercial nuclear fuel production facilities and five nuclear facilities operated for the US Department of Energy by private contractors were chosen for analysis. The results presented in the report indicate that the nature of risk perceptions depends on a number of factors. These factors are (1) level of communication by plant officials within the local community, (2) track record of the facility. operator, (3) process through which community and state officials receive information and form opinions, (4) level of economic links each plant has with the local community, and (15) physical characteristics of the facility itself. This report finds that in the communities studied, adverse ask perceptions have not affected business location decisions, employment levels in the local community, tourism, or agricultural development. On the basis of case-study findings, this report recommends that nuclear facility siting programs take the following observations into account when addressing perceptions of risk. First, the quality of a facility's participation with community activists, interest groups, and state agencies helps to determine the level of perceived risk within a community. Second, the development of strong economic links between nuclear facilities and their host communities will produce a higher level of acceptance of the nuclear facilities

  19. METHODOLOGY-TECHNOLOGICAL BASES AND COMMUNICATION FACILITIES OF COMMUNICATION IN DISTANCE LEARNING

    OpenAIRE

    O. Gnedkova; V. Lyakutin

    2010-01-01

    In this article methodical and technological principles of communication process in distance learning, which are the important constituents of the effective distance course, are analyzed. Communication facilities for the conducting communication process in distance learning are examined. Recommendations for teachers (tutors) for organization of successful and effective learning process with the use of modern communication technologies are pointed.

  20. State-of-the-art WEB -technologies and ecological safety of nuclear power engineering facilities

    International Nuclear Information System (INIS)

    Batij, V.G.; Batij, E.V.; Rud'ko, V.M.; Kotlyarov, V.T.

    2004-01-01

    Prospects of web-technologies using in the field of improvement radiation safety level of nuclear power engineering facilities is seen. It is shown that application of such technologies will enable entirely using the data of all information systems of radiation control

  1. Accident risks in nuclear facilities. (Latest citations from the NTIS Bibliographic database). Published Search

    International Nuclear Information System (INIS)

    1994-02-01

    The bibliography contains citations concerning risk analysis and hazards evaluation of the design, construction, and operation of nuclear facilities. The citations also explore the risk and hazards of transporting radioactive materials to and from these facilities. Radiological calculations for environmental effects of nuclear accidents and the use of computer models in risk analysis are also included. (Contains 250 citations and includes a subject term index and title list.)

  2. Risk management technique for liquefied natural gas facilities

    Science.gov (United States)

    Fedor, O. H.; Parsons, W. N.

    1975-01-01

    Checklists have been compiled for planning, design, construction, startup and debugging, and operation of liquefied natural gas facilities. Lists include references to pertinent safety regulations. Methods described are applicable to handling of other hazardous materials.

  3. Analyses in support of risk-informed natural gas vehicle maintenance facility codes and standards :

    Energy Technology Data Exchange (ETDEWEB)

    Ekoto, Isaac W.; Blaylock, Myra L.; LaFleur, Angela Christine; LaChance, Jeffrey L.; Horne, Douglas B.

    2014-03-01

    Safety standards development for maintenance facilities of liquid and compressed gas fueled large-scale vehicles is required to ensure proper facility design and operation envelopes. Standard development organizations are utilizing risk-informed concepts to develop natural gas vehicle (NGV) codes and standards so that maintenance facilities meet acceptable risk levels. The present report summarizes Phase I work for existing NGV repair facility code requirements and highlights inconsistencies that need quantitative analysis into their effectiveness. A Hazardous and Operability study was performed to identify key scenarios of interest. Finally, scenario analyses were performed using detailed simulations and modeling to estimate the overpressure hazards from HAZOP defined scenarios. The results from Phase I will be used to identify significant risk contributors at NGV maintenance facilities, and are expected to form the basis for follow-on quantitative risk analysis work to address specific code requirements and identify effective accident prevention and mitigation strategies.

  4. Development of Integrated Assessment Technology of Risk and Performance

    International Nuclear Information System (INIS)

    Yang, Jun Eon; Kang, Dae Il; Kang, Hyun Gook

    2010-04-01

    The main idea and contents are summarized as below 1) Development of new risk/performance assessment system innovating old labor-intensive risk assessment structure - New consolidated risk assessment technology from various hazard(flood, fire, seismic in NPP) - BOP model development for performance monitoring - Consolidated risk/performance management system for consistency and efficiency of NPP 2) Resolution technology for pending issues in PSA - Base technology for PSA of digital I and C system - Base technology for seismic PSA reflecting domestic seismic characteristics and aging effect - Uncertainty reduction technology for level 2 PSA and best estimation of containment failure frequency 3) Next generation risk/performance assessment technology - Human-induced error reduction technology for efficient operation of a NPP

  5. Development programs on decommissioning technology for reactors and fuel cycle facilities in Japan

    International Nuclear Information System (INIS)

    Fujiki, K.

    1992-01-01

    The Science and Technology Agency (STA) of Japan is promoting technology development for decommissioning of nuclear facilities by entrusting various research programs to concerned research organisations: JAERI, PNC and RANDEC, including first full scale reactor decommissioning of JPDR. According to the results of these programs, significant improvement on dismantling techniques, decontamination, measurement etc. has been achieved. Further development of advanced decommissioning technology has been started in order to achieve reduction of duration of decommissioning work and occupational exposures in consideration of the decommissioning of reactors and fuel cycle facilities. (author) 5 refs.; 7 figs.; 1 tab

  6. RCRA Facility Investigation/Remedial Investigation Report with Baseline Risk Assessment for the Fire Department Hose Training Facility (904-113G)

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, E. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1997-04-01

    This report documents the Resource Conservation and Recovery Act (RCRA) Facility Investigation/Remedial Investigation/Baseline Risk Assessment (RFI/RI/BRA) for the Fire Department Hose Training Facility (FDTF) (904-113G).

  7. Designing a Physical Security System for Risk Reduction in a Hypothetical Nuclear Facility

    International Nuclear Information System (INIS)

    Saleh, A.A.; Abd Elaziz, M.

    2017-01-01

    Physical security in a nuclear facility means detection, prevention and response to threat, the ft, sabotage, unauthorized access and illegal transfer involving radioactive and nuclear material. This paper proposes a physical security system designing concepts to reduce the risk associated with variant threats to a nuclear facility. This paper presents a study of the unauthorized removal and sabotage in a hypothetical nuclear facility considering deter, delay and response layers. More over, the study involves performing any required upgrading to the security system by investigating the nuclear facility layout and considering all physical security layers design to enhance the weakness for risk reduction

  8. The formation and economic impact of perceptions of risk surrounding nuclear facilities

    International Nuclear Information System (INIS)

    Allison, T.; Calzonetti, F.; Hunter, S.

    1993-01-01

    This paper summarizes the results of an investigation of factors determining the nature of risk perceptions associated with eleven nuclear facilities and their impact on local economic development. The paper indicates that the nature of risk perceptions depends primarily on the level of communication by plant officials within the local community, the track record of the facility operator, the process through which community and state officials receive information and form opinions, and the level of economic links each facility has with the local community. The research indicates that adverse risk perceptions have not affected economic development

  9. Incremental Risks of Transporting NARM to the LLW Disposal Facility at Hanford

    International Nuclear Information System (INIS)

    Weiner, R.F.

    1999-01-01

    This study models the incremental radiological risk of transporting NARM to the Hanford commercial LLW facility, both for incident-free transportation and for possible transportation accidents, compared with the radiological risk of transporting LLW to that facility. Transportation routes are modeled using HIGHWAY 3.1 and risks are modeled using RADTRAN 4. Both annual population doses and risks, and annual average individual doses and risks are reported. Three routes to the Hanford site were modeled from Albany, OR, from Coeur d'Alene, ID (called the Spokane route), and from Seattle, WA. Conservative estimates are used in the RADTRAN inputs, and RADTRAN itself is conservative

  10. Risk calculations in the manufacturing technology selection process

    DEFF Research Database (Denmark)

    Farooq, S.; O'Brien, C.

    2010-01-01

    Purpose - The purpose of this paper is to present result obtained from a developed technology selection framework and provide a detailed insight into the risk calculations and their implications in manufacturing technology selection process. Design/methodology/approach - The results illustrated...... in the paper are the outcome of an action research study that was conducted in an aerospace company. Findings - The paper highlights the role of risk calculations in manufacturing technology selection process by elaborating the contribution of risk associated with manufacturing technology alternatives...... in the shape of opportunities and threats in different decision-making environments. Practical implications - The research quantifies the risk associated with different available manufacturing technology alternatives. This quantification of risk crystallises the process of technology selection decision making...

  11. Marine and Hydrokinetic Technology Development Risk Management Framework

    Energy Technology Data Exchange (ETDEWEB)

    Snowberg, David [National Renewable Energy Lab. (NREL), Golden, CO (United States); Weber, Jochem [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2015-09-01

    Over the past decade, the global marine and hydrokinetic (MHK) industry has suffered a number of serious technological and commercial setbacks. To help reduce the risks of industry failures and advance the development of new technologies, the U.S. Department of Energy (DOE) and the National Renewable Energy Laboratory (NREL) developed an MHK Risk Management Framework. By addressing uncertainties, the MHK Risk Management Framework increases the likelihood of successful development of an MHK technology. It covers projects of any technical readiness level (TRL) or technical performance level (TPL) and all risk types (e.g. technological risk, regulatory risk, commercial risk) over the development cycle. This framework is intended for the development and deployment of a single MHK technology—not for multiple device deployments within a plant. This risk framework is intended to meet DOE’s risk management expectations for the MHK technology research and development efforts of the Water Power Program (see Appendix A). It also provides an overview of other relevant risk management tools and documentation.1 This framework emphasizes design and risk reviews as formal gates to ensure risks are managed throughout the technology development cycle. Section 1 presents the recommended technology development cycle, Sections 2 and 3 present tools to assess the TRL and TPL of the project, respectively. Section 4 presents a risk management process with design and risk reviews for actively managing risk within the project, and Section 5 presents a detailed description of a risk registry to collect the risk management information into one living document. Section 6 presents recommendations for collecting and using lessons learned throughout the development process.

  12. Apperception and assessment of technological risks

    International Nuclear Information System (INIS)

    Hoyos, C.; Hauke, G.

    1986-01-01

    Risk is defined to be the possibility to induce damage or loss. Any person confronted with risk in his activities has to assess the risk in every case. The author explains a number of actions and events that have been worked out to train people in better management of risk, especially in the working environment. (DG) [de

  13. Risk assessment and early warning systems for industrial facilities in seismic zones

    International Nuclear Information System (INIS)

    Salzano, Ernesto; Garcia Agreda, Anita; Di Carluccio, Antonio; Fabbrocino, Giovanni

    2009-01-01

    Industrial equipments and systems can suffer structural damage when hit by earthquakes, so that accidental scenarios as fire, explosion and dispersion of toxic substances can take place. As a result, overall damage to people, environment and properties increases. The present paper deals with seismic risk analysis of industrial facilities where atmospheric storage tanks (anchored or unanchored to ground), horizontal pressurised tanks, reactors and pumps are installed. Simplified procedures and methodologies based on historical database and literature data on natural-technological (Na-Tech) accidents for seismic risk assessment are discussed. Equipment-specific fragility curves have been thus derived depending on a single earthquake measure, peak ground acceleration (PGA). Fragility parameters have been then transformed to linear probit coefficients in order to obtain reliable threshold values for earthquake intensity measure, both for structural damage and loss of containment. These threshold values are of great interest when development of active and passive mitigation actions and systems, safety management, and the implementation of early warning system are concerned. The approach is general and can be implemented in any available code or procedure for risk assessment. Some results of seismic analysis of atmospheric storage tanks are also presented for validation.

  14. Risk assessment for civil engineering facilities: critical overview and discussion

    International Nuclear Information System (INIS)

    Faber, M.H.; Stewart, M.G.

    2003-01-01

    The present paper should be seen as a basis for discussion of important aspects of risk analysis and assessment, as well as attempting to describe risk assessment in accordance with the present state of the art. Risk assessment is thus presented in an overview form from the viewpoint of being a means for decision-making and thus within the formal framework of decision theory. First the motivation for risk analysis is given and the theoretical basis together with the practical aspects, methodologies and techniques for the implementation of risk assessment in civil engineering applications are explained and discussed. The paper furthermore addresses the problems associated with risk acceptance criteria, risk aversion and value of human life and attempts to provide suggestions for the rational treatment of these aspects. Finally a number of problem areas are highlighted and the needs for further education, research and dissemination are stressed

  15. A probabilistic risk assessment of the LLNL Plutonium facility's evaluation basis fire operational accident

    International Nuclear Information System (INIS)

    Brumburgh, G.

    1994-01-01

    The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous involving plutonium to include device fabrication, development of fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed rational safety and acceptable risk to employees, the public, government property, and the environment. This paper outlines the PRA analysis of the Evaluation Basis Fire (EDF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

  16. Development of Design Concept and Applied Technology for RCP Performance Test Facility

    International Nuclear Information System (INIS)

    Park, Sang Jin; Lee, Jung Ho; Yoon, Seok Ho

    2010-02-01

    Performance test facility for RCP (reactor coolant pump) is essential to verify the performance and reliability of RCP before installation in the nuclear power plant. The development of RCP for new-type reactor and the performance verification of hydraulic revolving body also needs the RCP test facility. The design concept of test loop and the technology of flow rate measurement are investigated in this research

  17. Wikipedia use: Risk for developing technology addiction

    OpenAIRE

    Manoj Kumar Sharma

    2016-01-01

    The present case highlights the addictive potential of Wikipedia usage. The users approached a technology addiction clinic for the management of excessive use of technology. A clinical interview was used to elicit information about usages. It indicates the addictive use of Wikipedia and associated dysfunction in lifestyle. It has implication for promotion of healthy use of technology.

  18. Wikipedia use: Risk for developing technology addiction

    Directory of Open Access Journals (Sweden)

    Manoj Kumar Sharma

    2016-01-01

    Full Text Available The present case highlights the addictive potential of Wikipedia usage. The users approached a technology addiction clinic for the management of excessive use of technology. A clinical interview was used to elicit information about usages. It indicates the addictive use of Wikipedia and associated dysfunction in lifestyle. It has implication for promotion of healthy use of technology.

  19. The development of robot application technology in nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Jong Min; Kim, Seung Ho; Kim, Chang Hoi; Kim, Byung Soo; Hwang, Suk Young; Sohn, Surg Won; Lee, Yong Bum; Kim, Woong Ki

    1991-01-01

    The project of this study is intended to develop the application technology for autonomous robotic systems operated in hostile environments where human access is prohibited. The mobile robot, named as KAEROT, has been designed by adopting the controller of multiprocessor of distributed system architecture in order to get flexibility. 2 driving wheel assembles and 1 steering mechanism has been adopted and each of them is made of planetary wheel which is composed of a couple of star-like arms with 3 wheels. The 6 D.O.F of manipulator is controlled by CCD camera mounted on the elbow and base, to provide wide view of the working area for tele-operation. The off-line programming system is being developed for checking robot constraint violations within workspace prior to execution of robot programming. (Author)

  20. Specific factors influencing information system/information and communication technology sourcing strategies in healthcare facilities.

    Science.gov (United States)

    Potančok, Martin; Voříšek, Jiří

    2016-09-01

    Healthcare facilities use a number of information system/information and communication technologies. Each healthcare facility faces a need to choose sourcing strategies most suitable to ensure provision of information system/information and communication technology services, processes and resources. Currently, it is possible to observe an expansion of sourcing possibilities in healthcare informatics, which creates new requirements for sourcing strategies. Thus, the aim of this article is to identify factors influencing information system/information and communication technology sourcing strategies in healthcare facilities. The identification was based on qualitative research, namely, a case study. This study provides a set of internal and external factors with their impact levels. The findings also show that not enough attention is paid to these factors during decision-making. © The Author(s) 2015.

  1. Development of Risk Management Technology/Development of Risk-Informed Application Technology

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Joon Eon; Kim, K. Y.; Ahn, K. I.; Lee, Y. H.; Lim, H. G.; Jung, W. S.; Choi, S. Y.; Han, S. J.; Ha, J. J.; Hwang, M. J.; Park, S. Y.; Yoon, C

    2007-06-15

    This project aims at developing risk-informed application technologies to enhance the safety and economy of nuclear power plant altogether. For this, the Integrated Level 1 and 2 PSA model is developed. In addition, the fire and internal flooding PSA models are improved according to the PSA standard of U.S.A. To solve the issues of domestic PSA model, the best-estimate thermal hydraulic analyses are preformed for the ATWS and LSSB. In order to reduce the uncertainty of PSA, several new PSA technologies are developed: (1) more exact quantification of large fault tree, (2) importance measure including the effects of external PSA. As feasibility studies of Option 2 and 3, the class of 6 systems' SSC are re-classified based on the risk information and the sensitivity analyses is performed for the EDG starting time, respectively. It is also improved that the methodology to identify the vital area of NPP. The research results of this project can be used in the regulatory body and the industry projects for risk-informed applications.

  2. Development of Risk Management Technology/Development of Risk-Informed Application Technology

    International Nuclear Information System (INIS)

    Yang, Joon Eon; Kim, K. Y.; Ahn, K. I.; Lee, Y. H.; Lim, H. G.; Jung, W. S.; Choi, S. Y.; Han, S. J.; Ha, J. J.; Hwang, M. J.; Park, S. Y.; Yoon, C.

    2007-06-01

    This project aims at developing risk-informed application technologies to enhance the safety and economy of nuclear power plant altogether. For this, the Integrated Level 1 and 2 PSA model is developed. In addition, the fire and internal flooding PSA models are improved according to the PSA standard of U.S.A. To solve the issues of domestic PSA model, the best-estimate thermal hydraulic analyses are preformed for the ATWS and LSSB. In order to reduce the uncertainty of PSA, several new PSA technologies are developed: (1) more exact quantification of large fault tree, (2) importance measure including the effects of external PSA. As feasibility studies of Option 2 and 3, the class of 6 systems' SSC are re-classified based on the risk information and the sensitivity analyses is performed for the EDG starting time, respectively. It is also improved that the methodology to identify the vital area of NPP. The research results of this project can be used in the regulatory body and the industry projects for risk-informed applications

  3. Analyses in Support of Risk-Informed Natural Gas Vehicle Maintenance Facility Codes and Standards: Phase II.

    Energy Technology Data Exchange (ETDEWEB)

    Blaylock, Myra L.; LaFleur, Chris Bensdotter; Muna, Alice Baca; Ehrhart, Brian David

    2018-03-01

    Safety standards development for maintenance facilities of liquid and compressed natural gas fueled vehicles is required to ensure proper facility design and operating procedures. Standard development organizations are utilizing risk-informed concepts to develop natural gas vehicle (NGV) codes and standards so that maintenance facilities meet acceptable risk levels. The present report summarizes Phase II work for existing NGV repair facility code requirements and highlights inconsistencies that need quantitative analysis into their effectiveness. A Hazardous and Operability study was performed to identify key scenarios of interest using risk ranking. Detailed simulations and modeling were performed to estimate the location and behavior of natural gas releases based on these scenarios. Specific code conflicts were identified, and ineffective code requirements were highlighted and resolutions proposed. These include ventilation rate basis on area or volume, as well as a ceiling offset which seems ineffective at protecting against flammable gas concentrations. ACKNOWLEDGEMENTS The authors gratefully acknowledge Bill Houf (SNL -- Retired) for his assistance with the set-up and post-processing of the numerical simulations. The authors also acknowledge Doug Horne (retired) for his helpful discussions. We would also like to acknowledge the support from the Clean Cities program of DOE's Vehicle Technology Office.

  4. Test facilities for radioactive material transport packages (AEA Technology plc, Winfrith,UK)

    International Nuclear Information System (INIS)

    Gillard, J.E.

    2001-01-01

    Transport containers for radioactive materials are tested to demonstrate compliance with national and international standards. Transport package design, testing, assessment and approval requires a wide range of skills and facilities. The comprehensive capability of AEA Technology in these areas is described. The facilities described include drop-test cranes and targets (up to 700 tonne); pool fires, furnaces and rigs for thermal tests, including heat dissipation on prototype flasks; shielding facilities; criticality simulations and leak test techniques. These are illustrated with photographs demonstrating the comprehensive nature of package testing services supplied to customers. (author)

  5. Test facilities for radioactive material transport packages (AEA Technology plc, Winfrith,UK)

    Energy Technology Data Exchange (ETDEWEB)

    Gillard, J.E

    2001-07-01

    Transport containers for radioactive materials are tested to demonstrate compliance with national and international standards. Transport package design, testing, assessment and approval requires a wide range of skills and facilities. The comprehensive capability of AEA Technology in these areas is described. The facilities described include drop-test cranes and targets (up to 700 tonne); pool fires, furnaces and rigs for thermal tests, including heat dissipation on prototype flasks; shielding facilities; criticality simulations and leak test techniques. These are illustrated with photographs demonstrating the comprehensive nature of package testing services supplied to customers. (author)

  6. Assessment of technologies for hazardous waste site remediation: Non-treatment technologies and pilot scale facility implementation -- monitoring technology

    International Nuclear Information System (INIS)

    Johnson, H.R.; Overbey, W.K. Jr.; Molnar, D.L.

    1994-02-01

    The objective of this study was to investigate and evaluate existing proven technologies for the monitoring of hazardous waste sites during remediation activities and to protect the health and safety of all related entities while complying with government regulations. The study began with a literature search to determine manufacturers and related instrumentation which would be applicable to the most complex (in terms of toxicity and mediums affected) sites. Criteria for monitoring and analyses were established and a functional analysis was performed to select the most appropriate instrumentation available. Gas Chromatography/Mass Spectrometry is the most widely accepted method for generating quantitative data given the characterization of the Winfield site. Fourier Transform Infrared Spectroscopy, while not a new technology, has the distinct advantage of measuring simultaneously hundreds of gaseous pollutants which can also be sparged from water and this technology received the highest score as per the functional analysis. To protect workers and the public surrounding remediation sites which are known to contain VOCs, on site monitoring prior to, and during the excavation operations, is recommended until enough data are obtained to assess the health risks to workers. The conclusion of this study is to recommend evaluation of both the mobile GC/MS and FTIR systems simultaneously in identical operating conditions

  7. R2 TRI facilities with 1999-2011 risk related estimates throughout the census blockgroup

    Data.gov (United States)

    U.S. Environmental Protection Agency — This dataset delineates the distribution of estimate risk from the TRI facilities for 1999 - 2011 throughout the census blockgroup of the region using Office of...

  8. effectiveness of technological options for minimising production risks

    African Journals Online (AJOL)

    ACSS

    preferred technologies in reducing production risk related to climate variability in Eastern Uganda. Data for this study were ..... Set of technological options employed by farmers to reduce climate-induced production risk. Dummy = 1 if farmer. 0.71. 0.46 ..... cation exchange capacity for holding nutrients against leaching loss.

  9. Assessment of major nuclear technologies with decision and risk analysis

    International Nuclear Information System (INIS)

    Winterfeldt, D. von

    1995-01-01

    Selecting technologies for major nuclear programs involves several complexities, including multiple stakeholders, multiple conflicting objectives, uncertainties, and risk. In addition, the programmatic risks related to the schedule, cost, and performance of these technologies often become major issues in the selection process. This paper describes a decision analysis approach for addressing these complexities in a logical manner

  10. Farm Technologies and Production Risk in the Face of Climate ...

    African Journals Online (AJOL)

    In countries where insurance and credit markets are thin or missing, production and consumption risks play a critical role in the choice and use of production inputs and adoption of new farm technologies. This paper investigated the effect of selected farm technologies and their risk implications in different rainfall patterns of ...

  11. Interpersonal amplification of risk? Citizen discussions and their impact on perceptions of risks and benefits of a biological research facility.

    Science.gov (United States)

    Binder, Andrew R; Scheufele, Dietram A; Brossard, Dominique; Gunther, Albert C

    2011-02-01

    Much risk communication research has demonstrated how mass media can influence individual risk perceptions, but lacks a comprehensive conceptual understanding of another key channel of communication: interpersonal discussion. Using the social amplification of risk as a theoretical framework, we consider the potential for discussions to function as amplification stations. We explore this possibility using data from a public opinion survey of residents living in potential locations for a new biological research facility in the United States. Controlling for a variety of key information variables, our results show that two dimensions of discussion-frequency and valence-have impacts on residents' perceptions of the facility's benefits and its risks. We also explore the possibility that an individual's overall attitude moderates the effect of discussion on their perceptions of risks and benefits. Our results demonstrate the potential for discussions to operate as amplifiers or attenuators of perceptions of both risks and benefits. © 2010 Society for Risk Analysis.

  12. The Performativity of Risk Management Frameworks and Technologies

    DEFF Research Database (Denmark)

    Neerup Themsen, Tim; Skærbæk, Peter

    2018-01-01

    This article examines the long-term dynamics among a best-practice risk management framework, risk management technologies and the translation of uncertainties into risks by using a longitudinal case study of a large mega-project. We show that the framework and technologies through the visual power...... of impure risks challenges the predictions of the framework causing a false sense of security for the project objectives, and that the continuous readjustment of technologies, in particular, is necessary to ensure the long-term realisation of these predictions. Finally, this article contributes...... of inscriptions and the purifying work of risk consultants as experts establish the boundaries of the forms of uncertainties that are accepted and included as risks. We term the accepted and included risks ‘pure risks’ and the risks excluded after disagreement ‘impure risks’. We also show that the construction...

  13. Who delivers where? The effect of obstetric risk on facility delivery in East Africa.

    Science.gov (United States)

    Virgo, Sandra; Gon, Giorgia; Cavallaro, Francesca L; Graham, Wendy; Woodd, Susannah

    2017-09-01

    Skilled attendance at birth is key for the survival of pregnant women. This study investigates whether women at increased risk of maternal and newborn complications in four East African countries are more likely to deliver in a health facility than those at lower risk. Demographic and Health Survey data for Kenya 2014, Rwanda 2014-15, Tanzania 2015-16 and Uganda 2011 were used to study women with a live birth in the three years preceding the survey. A three-level obstetric risk index was created using known risk factors. Generalised linear Poisson regression was used to investigate the association between obstetric risk and facility delivery. We analysed data from 13 119 women across the four countries of whom 42-45% were considered at medium risk and 12-17% at high risk, and the remainder were at low risk. In Rwanda, 93% of all women delivered in facilities but this was lower (59-66%) in the other three countries. There was no association between a woman's obstetric risk level and her place of delivery in any country; greater wealth and more education were, however, independently strongly associated with facility delivery. In four East African countries, women at higher obstetric risk were not more likely to deliver in a facility than those with lower risk. This calls for a renewed focus on antenatal risk screening and improved communication on birth planning to ensure women with an increased chance of maternal and newborn complications are supported to deliver in facilities with skilled care. © 2017 John Wiley & Sons Ltd.

  14. Air pollution control systems and technologies for waste-to-energy facilities

    International Nuclear Information System (INIS)

    Getz, N.P.; Amos, C.K. Jr.; Siebert, P.C.

    1991-01-01

    One of the primary topics of concern to those planning, developing, and operating waste-to-energy (W-T-E) [also known as municipal waste combustors (MWCs)] facilities is air emissions. This paper presents a description of the state-of-the-art air pollution control (APC) systems and technology for particulate, heavy metals, organics, and acid gases control for W-T-E facilities. Items covered include regulations, guidelines, and control techniques as applied in the W-T-E industry. Available APC technologies are viewed in detail on the basis of their potential removal efficiencies, design considerations, operations, and maintenance costs

  15. The systematic risk study in technology companies at Brazil

    Directory of Open Access Journals (Sweden)

    Marcio Marcelo Belli

    2017-09-01

    Full Text Available This work tested if brasilian technology companies has a greater systematic risk than traditional companies in Brazil. For to achieve tje purpose, two companies samples , one of technology companies and the other of traditional companies, were composed. The tecnique employed was a multiple regression analysis considering a dichotomous variable wich represents the technological factor and another numerical variable wich represents the intangibility degree of  companies. As a dependent variable was considered the CAPM systematic risk. The results indicated that technology companies have a greater systematic risk than traditional companies regardless of the degree of intangibility.

  16. On fire risk/methodology for the next generation of reactors and nuclear facilities

    International Nuclear Information System (INIS)

    Majumdar, K.C.; Alesso, H.P.; Altenbach, T.J.

    1992-01-01

    Methodologies for including fire in probabilistic risk assessments (PRAs) have been evolving during the last ten years. Many of these studies show that fire risk constitutes a significant percentage of external events, as well as the total core damage frequency. This paper summarizes the methodologies used in the fire risk analysis of the next generation of reactors and existing DOE nuclear facilities. Methodologies used in other industries, as well as existing nuclear power plants, are also discussed. Results of fire risk studies for various nuclear plants and facilities are shown and compared

  17. Seismic risk and heavy industrial facilities conference: proceedings

    International Nuclear Information System (INIS)

    1983-01-01

    Summaries of over 50 papers related to seismic risk analysis were presented. The papers cover areas such as seismic input description, response of components and structures, assessment of risk and reliability including human factors, and results of integrated studies. Papers have been individually abstracted for the Energy Data Base

  18. Risk assessment of several incidents in nuclear waste management facilities

    International Nuclear Information System (INIS)

    Buetow, E.; Memmert, G.; Storck, R.; Weymann, J.; Matthies, M.; Vogt, K.J.

    1981-01-01

    Regarding surface facilities two incidents of MAVA (failure of the filter in the exhaust gas system, fire in the bituminization system) and one incident in the Krypton storage and regarding underground systems the water inlet in the pit building have been evaluated. According to the calculations only the two nuclides Tc-99 and J-129 can involve a considerable exposure. The barrier system of overlying rocks and the pit system as a whole is largely redundant and diverse. (DG) [de

  19. Interim guidance risk assessment of the device assembly facility at the Nevada test site

    International Nuclear Information System (INIS)

    Altenbach, T.J.

    1996-05-01

    The risks of plutonium dispersal and/or high explosive detonation from nuclear explosive operations at the Device Assembly Facility were examined in accordance with DOE Order 5610.11 and the Interim Guidance. The assessment consisted of a qualitative task and hazards analysis, and a quantitative risk screening. Results are displayed on risk matrices for the major types of operations. Most accident scenarios were considered to have Low risk; a few scenarios have Moderate risk; and none have High risk. The highest risk scenarios (Moderate category) consist of a high explosive detonation during assembly operations in a cell, with bare conventional high explosive surrounding the pit

  20. Comparative, collaborative, and integrative risk governance for emerging technologies

    OpenAIRE

    LINKOV IGOR; TRUMP BENJAMIN D.; ANKLAM ELKE; BERBUBE DAVID; BOISSEAU PATRICK; CUMMINGS CHRISTOPHER; FERSON SCOTT; FLORIN MARIE-VALENTINE; GOLDSTEIN BERNARD; HRISTOZOV DANAIL; JENSEN KELD ASTRUP; KATALAGARIANAKIS GEORGIOS; KUZMA JENNIFER; LAMBERT JAMES H.; MALLOY TIMOTHY

    2018-01-01

    Various emerging technologies challenge existing governance processes to identify, assess, and manage risk. Though the existing risk-based paradigm has been essential for assessment of many chemical, biological, radiological, and nuclear technologies, a complementary approach may be warranted for the early-stage assessment and management challenges of high uncertainty technologies ranging from nanotechnology to synthetic biology to artificial intelligence, among many others. This ...

  1. Quantification of Technology Innovation Usinga Risk-Based Framework

    OpenAIRE

    Gerard E. Sleefe

    2010-01-01

    There is significant interest in achieving technology innovation through new product development activities. It is recognized, however, that traditional project management practices focused only on performance, cost, and schedule attributes, can often lead to risk mitigation strategies that limit new technology innovation. In this paper, a new approach is proposed for formally managing and quantifying technology innovation. This approach uses a risk-based framework that s...

  2. Technology and At-Risk Young Readers and Their Classrooms

    Science.gov (United States)

    Blachowicz, Camille L. Z.; Bates, Ann; Berne, Jennifer; Bridgman, Teresa; Chaney, Jeanne; Perney, Jan

    2009-01-01

    This study examined the ways in which 18 first-grade teachers and their students in 11 high-risk urban schools began to use literacy-focused technology. The goal of the study was to observe the technology in use by the students, to observe the classroom dynamics and teachers' instructional choices centered around technology use, to look at student…

  3. Evaluation and Selection of Renewable Energy Technologies for Highway Maintenance Facilities

    Science.gov (United States)

    Andrews, Taylor

    The interest in renewable energy has been increasing in recent years as attempts to reduce energy costs as well the consumption of fossil fuels are becoming more common. Companies and organizations are recognizing the increasing reliance on limited fossil fuels' resources, and as competition and costs for these resources grow, alternative solutions are becoming more appealing. Many federally run buildings and associations also have the added pressure of meeting the mandates of federal energy policies that dictate specific savings or reductions. Federal highway maintenance facilities run by the Department of Transportation fall into this category. To help meet energy saving goals, an investigation into potential renewable energy technologies was completed for the Ohio Department of Transportation. This research examined several types of renewable energy technologies and the major factors that affect their performance and evaluated their potential for implementation at highway maintenance facilities. Facilities energy usage data were provided, and a facility survey and site visits were completed to enhance the evaluation of technologies and the suitability for specific projects. Findings and technology recommendations were presented in the form of selection matrices, which were designed to help make selections in future projects. The benefits of utilization of other tools such as analysis software and life cycle assessments were also highlighted. These selection tools were designed to be helpful guides when beginning the pursuit of a renewable energy technology for highway maintenance facilities, and can be applied to other similar building types and projects. This document further discusses the research strategies and findings as well as the recommendations that were made to the personnel overseeing Ohio's highway maintenance facilities.

  4. Facilities for technology testing of ITER divertor concepts, models, and prototypes in a plasma environment

    International Nuclear Information System (INIS)

    Cohen, S.A.

    1991-12-01

    The exhaust of power and fusion-reaction products from ITER plasma are critical physics and technology issues from performance, safety, and reliability perspectives. Because of inadequate pulse length, fluence, flux, scrape-off layer plasma temperature and density, and other parameters, the present generation of tokamaks, linear plasma devices, or energetic beam facilities are unable to perform adequate technology testing of divertor components, though they are essential contributors to many physics issues such as edge-plasma transport and disruption effects and control. This Technical Requirements Documents presents a description of the capabilities and parameters divertor test facilities should have to perform accelerated life testing on predominantly technological divertor issues such as basic divertor concepts, heat load limits, thermal fatigue, tritium inventory and erosion/redeposition. The cost effectiveness of such divertor technology testing is also discussed

  5. Challenges Associated With Managing Suicide Risk in Long-Term Care Facilities.

    Science.gov (United States)

    O'Riley, Alisa; Nadorff, Michael R; Conwell, Yeates; Edelstein, Barry

    2013-06-01

    Little information about suicidal ideation and behavior in long-term care (LTC) facilities is available. Nonetheless, the implementation of the Minimum Data Set 3.0 requires that LTC facilities screen their residents for suicide risk and have protocols in place to effectively manage residents' responses. In this article, the authors briefly discuss the risk factors of suicide in the elderly and the problems that suicidal ideation and behavior pose in the LTC environment. The authors explain issues that arise when trying to manage suicide risk in the elderly LTC population with general, traditional approaches. These inherent issues make it difficult to develop an effective protocol for managing suicide risk in LTC facilities, leading the authors to propose their own framework for assessing and managing suicide risk in the LTC setting.

  6. A Measurement Management Technology for Improving Energy Efficiency in Data Centers and Telecommunication Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Hendrik Hamann, Levente Klein

    2012-06-28

    Data center (DC) electricity use is increasing at an annual rate of over 20% and presents a concern for the Information Technology (IT) industry, governments, and the society. A large fraction of the energy use is consumed by the compressor cooling to maintain the recommended operating conditions for IT equipment. The most common way to improve the DC efficiency is achieved by optimally provisioning the cooling power to match the global heat dissipation in the DC. However, at a more granular level, the large range of heat densities of today's IT equipment makes the task of provisioning cooling power optimized to the level of individual computer room air conditioning (CRAC) units much more challenging. Distributed sensing within a DC enables the development of new strategies to improve energy efficiency, such as hot spot elimination through targeted cooling, matching power consumption at rack level with workload schedule, and minimizing power losses. The scope of Measurement and Management Technologies (MMT) is to develop a software tool and the underlying sensing technology to provide critical decision support and control for DC and telecommunication facilities (TF) operations. A key aspect of MMT technology is integration of modeling tools to understand how changes in one operational parameter affect the overall DC response. It is demonstrated that reduced ordered models for DC can generate, in less than 2 seconds computational time, a three dimensional thermal model in a 50 kft{sup 2} DC. This rapid modeling enables real time visualization of the DC conditions and enables 'what if' scenarios simulations to characterize response to 'disturbances'. One such example is thermal zone modeling that matches the cooling power to the heat generated at a local level by identifying DC zones cooled by a specific CRAC. Turning off a CRAC unit can be simulated to understand how the other CRAC utilization changes and how server temperature responds

  7. Cost (non)-recovery by platform technology facilities in the Bio21 Cluster.

    Science.gov (United States)

    Gibbs, Gerard; Clark, Stella; Quinn, Julieanne; Gleeson, Mary Joy

    2010-04-01

    Platform technologies (PT) are techniques or tools that enable a range of scientific investigations and are critical to today's advanced technology research environment. Once installed, they require specialized staff for their operations, who in turn, provide expertise to researchers in designing appropriate experiments. Through this pipeline, research outputs are raised to the benefit of the researcher and the host institution. Platform facilities provide access to instrumentation and expertise for a wide range of users beyond the host institution, including other academic and industry users. To maximize the return on these substantial public investments, this wider access needs to be supported. The question of support and the mechanisms through which this occurs need to be established based on a greater understanding of how PT facilities operate. This investigation was aimed at understanding if and how platform facilities across the Bio21 Cluster meet operating costs. Our investigation found: 74% of platforms surveyed do not recover 100% of direct operating costs and are heavily subsidized by their home institution, which has a vested interest in maintaining the technology platform; platform managers play a major role in establishing the costs and pricing of the facility, normally in a collaborative process with a management committee or institutional accountant; and most facilities have a three-tier pricing structure recognizing internal academic, external academic, and commercial clients.

  8. Engineering and technology in the deconstruction of nuclear materials production facilities

    International Nuclear Information System (INIS)

    Kingsley, R.S.; Reynolds, W.E.; Heffner, D.C.

    1996-01-01

    Technology and equipment exist to support nuclear facility deactivation, decontamination, and decommissioning. In reality, this statement is not surprising because the nuclear industry has been decontaminating and decommissioning production plants for decades as new generations of production technology were introduced. Since the 1950s, the Babcock and Wilcox Company (B ampersand W) has operated a number of nuclear materials processing facilities to manufacture nuclear fuel for the commercial power industry and the U.S. Navy. These manufacturing facilities included a mixed oxide (PuO 2 -UO 2 ) nuclear fuel manufacturing plant, low- and high-enriched uranium (HEU/LEU) chemical and fuel plants, and fuel assembly plants. In addition, B ampersand W designed and build a major nuclear research center in Lynchburg, Virginia, to support these nuclear fuel manufacturing activities and to conduct nuclear power research. These nuclear research facilities included two research reactors, a hot-cell complex for nuclear materials research, four critical experiment facilities, and a plutonium fuels research and development facility. This article describes the B ampersand W deactivation, decomtanimation, and decommisioning program

  9. Ideas concerning the risk problem in technology

    International Nuclear Information System (INIS)

    Schneider, K.W.

    1975-01-01

    Scientific and technical development is primarily meant to improve the quality of life and to reduce mortality. The increased risk thus caused for the individual leads to a longer life expectation of man and to the ethical question of choosing the safety of a technical system. One must critically choose between justifiable effort and risk. Experience in reactor engineering (technical systems with hypothetical extreme risks) leads to considerations of the analysis to determine the risk of large chemical plants for inhabited neighbourhoods and attempts to design a conceptive and computer model for a safety analysis which can be of use in decisions regarding new planning. (HP/LH) [de

  10. Geomatic techniques for assessing ecological and health risk at U.S. Department of Energy facilities

    International Nuclear Information System (INIS)

    Regens, J.L.; White, L.; Albers, B.J.; Purdy, C.

    1994-01-01

    Hazardous substances, including radionuclides, heavy metals, and chlorinated hydrocarbons, pose unique challenges in terms of environmental restoration and waste management, especially in aquatic environments. When stored, used or disposed of improperly, hazardous materials including transuranic wastes, high level wastes, low level wastes, greater than class C wastes, mixed wastes or chemical wastes can contaminate an array of environmental receptors ranging from soils, sediments, groundwater to surface water. Depending on the specific hazardous substance and site attributes, assessing ecological and health risk as a basis for environmental restoration and waste management can be a complex, problematic activity. This is basis for environmental restoration and waste management can be a complex, problematic activity. This is particularly true for the major Defense Programs facilities managed by the U.S. Department of Energy (DOE). The Environmental Restoration (ER) program of DOE was initiated in 1987 to consolidate and coordinate those regulatory activities designed to identify and remediate sites at installations contaminated with radioactive, chemical or mixed wastes. To supply the tools necessary for defining, describing, and characterizing the nature of contaminants within the DOE complex and identifying alternative post-remediation land use options, DOE has implemented a program for the research and development of spatial data technologies to aid in assessing ecological and health risk

  11. New Prototype Safeguards Technology Offers Improved Confidence and Automation for Uranium Enrichment Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Brim, Cornelia P.

    2013-04-01

    An important requirement for the international safeguards community is the ability to determine the enrichment level of uranium in gas centrifuge enrichment plants and nuclear fuel fabrication facilities. This is essential to ensure that countries with nuclear nonproliferation commitments, such as States Party to the Nuclear Nonproliferation Treaty, are adhering to their obligations. However, current technologies to verify the uranium enrichment level in gas centrifuge enrichment plants or nuclear fuel fabrication facilities are technically challenging and resource-intensive. NNSA’s Office of Nonproliferation and International Security (NIS) supports the development, testing, and evaluation of future systems that will strengthen and sustain U.S. safeguards and security capabilities—in this case, by automating the monitoring of uranium enrichment in the entire inventory of a fuel fabrication facility. One such system is HEVA—hybrid enrichment verification array. This prototype was developed to provide an automated, nondestructive assay verification technology for uranium hexafluoride (UF6) cylinders at enrichment plants.

  12. Test facilities for radioactive material transport packages (AEA Technology, Winfrith, UK)

    International Nuclear Information System (INIS)

    Burgess, M.H.

    1991-01-01

    Transport packages for radioactive materials are tested to demonstrate compliance with national and international regulations. The involvement of AEA Technology is traced from the establishment of the early IAEA Regulations. Transport package design, testing, assessment and approval requires a wide variety of skills and facilities. The comprehensive capability of AEA Technology in these areas is described with references to practical experience in the form of a short bibliography. The facilities described include drop-test cranes and targets (up to 700te); air guns for impacts up to sonic velocities; pool fires, furnaces and rigs for thermal tests including heat dissipation on prototype flasks; shielding facilities and instruments; criticality simulations and leak test instruments. These are illustrated with photographs demonstrating the comprehensive nature of package testing services supplied to customers. (author)

  13. Best Available Technology (BAT) guidance for radiological liquid effluents at US Department of Energy Facilities

    International Nuclear Information System (INIS)

    Wallo, A. III; Peterson, H.T. Jr.; Ikenberry, T.A.; Baker, R.E.

    1993-01-01

    The US Department of Energy (DOE), in DOE Order 5400.5 (1990), directs operators of DOE facilities to apply the Best Available Technology (BAT) to control radiological liquid effluents from these facilities when specific conditions are present. DOE has published interim guidance to assist facility operators in knowing when a BAT analysis is needed and how such an analysis should be performed and documented. The purpose of the guidance is to provide a uniform basis in determining BAT throughout DOE and to assist in evaluating BAT determinations during programmatic audits. The BAT analysis process involves characterizing the effluent source; identifying and selecting candidate control technologies; evaluating the potential environmental, operational, resource, and economic impacts of the control technologies; developing an evaluation matrix for comparing the technologies; selecting the BAT; and documenting the evaluation process. The BAT analysis process provides a basis for consistent evaluation of liquid effluent releases, yet allows an individual site or facility the flexibility to address site-specific issues or concerns in the most appropriate manner

  14. Spanish Minister of Science and Technology visits the LHC magnet test facility

    CERN Multimedia

    Patrice Loïez

    2002-01-01

    H.E. Mr Josep Piqué i Camps, Minister for Science and Technology, Spain, toured the test facility for LHC magnets in building SM18 during his visit to CERN in November. Photos 01, 02: Felix Rodriguez Mateos (right) explains some of a cryomagnet's myriad connections to the Minister.

  15. Spanish Minister of Science and Technology visits the LHC magnet test facility

    CERN Multimedia

    Patrice Loïez

    2002-01-01

    H.E. Mr Josep Piqué i Camps, Minister of Science and Technology, Spain, visited CERN in November. Here Felix Rodriguez Mateos (right) explains aspects of the test facility to the Minister (left). Between them are M. Aguilar Benitez, Spanish delegate to CERN Council (left), and Francisco Giménez-Reyna, Spanish delegate to the CERN Finance Committee.

  16. Spanish Minister of Science and Technology visits the LHC magnet test facility

    CERN Multimedia

    Patrice Loïez

    2002-01-01

    H.E. Mr Josep Piqué i Camps, Minister for Science and Technology, Spain, toured the test facility for LHC magnets in building SM18 during his visit to CERN in November. Photo 01: The Minister (left) with M. Cerrada and G. Babé.

  17. Nuclear engineering experiments at experimental facilities of JNC in graduate course of Tokyo Institute of Technology

    International Nuclear Information System (INIS)

    Hayashizaki, Noriyosu; Takahashi, Minoru; Aoyama, Takafumi; Onose, Shoji

    2005-01-01

    Nuclear engineering experiments using outside facilities of the campus have been offered for graduate students in the nuclear engineering course in Tokyo Institute of Technology (Tokyo Tech.). The experiments are managed with the collaboration of Japan Nuclear Cycle Development Institute (JNC), Japan Atomic Energy Research Institute (JAERI) and Research Reactor Institute, Kyoto University (KUR). This report presents the new curriculum of the nuclear engineering experiments at JNC since 2002. The change is due to the shutdown of Deuterium Criticality Assembly Facility (DCA) that was used as an experimental facility until 2001. Reactor physics experiment using the training simulator of the experimental fast reactor JOYO is continued from the previous curriculum with the addition of the criticality approach experiment and control rods calibration. A new experimental subject is an irradiated material experiment at the Material Monitoring Facility (MMF). As a result, both are acceptable as the student experiments on the fast reactor. (author)

  18. Radioactive waste package assay facility. Volume 1. Application of assay technology

    International Nuclear Information System (INIS)

    Findlay, D.J.S.; Green, T.H.; Molesworth, T.V.; Staniforth, D.; Strachan, N.R.; Rogers, J.D.; Wise, M.O.; Forrest, K.R.

    1992-01-01

    This report, in three volumes, covers the work carried out by Taylor Woodrow Construction Ltd., and two major sub-contractors: Harwell Laboratory (AEA Technology) and Siemens Plessey Controls Ltd., on the development of a radioactive waste package assay facility, for cemented 500 litre intermediate level waste drums. In volume 1, the reasons for assay are considered together with the various techniques that can be used, and the information that can be obtained. The practical problems associated with the use of the various techniques in an integrated assay facility are identified, and the key parameters defined. Engineering and operational features are examined and provisional designs proposed for facilities at three throughput levels: 15,000, 750 and 30 drums per year respectively. The capital and operating costs for such facilities have been estimated. A number of recommendations are made for further work. 16 refs., 14 figs., 13 tabs

  19. Gender and risk assessment in contraceptive technologies

    NARCIS (Netherlands)

    van Kammen, Jessika; Oudshoorn, Nelly E.J.

    This paper concerns a comparison of risk assessment practices of contraceptives for women and men. Our analysis shows how the evaluation of health risks of contraceptives does not simply reflect the specific effects of chemical compounds in the human body. Rather, we show how side-effects were rated

  20. Risk-based systems analysis for emerging technologies: Applications of a technology risk assessment model to public decision making

    International Nuclear Information System (INIS)

    Quadrel, M.J.; Fowler, K.M.; Cameron, R.; Treat, R.J.; McCormack, W.D.; Cruse, J.

    1995-01-01

    The risk-based systems analysis model was designed to establish funding priorities among competing technologies for tank waste remediation. The model addresses a gap in the Department of Energy's (DOE's) ''toolkit'' for establishing funding priorities among emerging technologies by providing disciplined risk and cost assessments of candidate technologies within the context of a complete remediation system. The model is comprised of a risk and cost assessment and a decision interface. The former assesses the potential reductions in risk and cost offered by new technology relative to the baseline risk and cost of an entire system. The latter places this critical information in context of other values articulated by decision makers and stakeholders in the DOE system. The risk assessment portion of the model is demonstrated for two candidate technologies for tank waste retrieval (arm-based mechanical retrieval -- the ''long reach arm'') and subsurface barriers (close-coupled chemical barriers). Relative changes from the base case in cost and risk are presented for these two technologies to illustrate how the model works. The model and associated software build on previous work performed for DOE's Office of Technology Development and the former Underground Storage Tank Integrated Demonstration, and complement a decision making tool presented at Waste Management 1994 for integrating technical judgements and non-technical (stakeholder) values when making technology funding decisions

  1. Improvement of the cogeneration facilities, considering the aspects of financial risks

    International Nuclear Information System (INIS)

    Santos, A.H.M.; Nogueira, L.A.H.; Costa Bortoni, E. da

    1992-01-01

    This paper proposes a methodology to include the tools of the Portfolio Theory in the design of the cogeneration facilities. So, the effects of the risk on the return can be take in account. A computer program was developed to simulate the impacts of the thermal and mechanical (or electrical) loads on energy surplus and the potential risk. (C.M.)

  2. Risk management for existing energy facilities. A global approach to numerical safety goals

    International Nuclear Information System (INIS)

    Pate-Cornell, M.E.

    1993-01-01

    This paper presents a structured set of numerical safety goals for risk management of existing energy facilities. The rationale behind these safety goals is based on principles of equity and economic efficiency. Some of the issues involved when using probabilistic risk analyses results for safety decisions are discussed. A brief review of existing safety targets and open-quotes floating numbersclose quotes is presented, and a set of safety goals for industrial risk management is proposed. Relaxation of these standards for existing facilities, the relevance of the lifetime of the plant, the treatment of uncertainties, and problems of failure dependencies are discussed briefly. 17 refs., 1 fig

  3. Technology, socio-political acceptance, and the low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Andrews, L.J.; Domenech, J.S.

    1986-01-01

    The technology which is required to develop and operate low-level radioactive waste disposal sites in the 1990's is available today. The push for best available technology is a response to the political difficulties in securing public acceptance of the site selection process. Advances in waste management technologies include development of High Integrity Containers (HIC), solidification media, liquid volume reduction techniques using GEODE/sub sm/ and DeVoe-Holbein technology of selective removal of target radioisotopes, and CASTOR V storage casks. Advances in technology alone, however, do not make the site selection process easier and without socio-political acceptance there may be no process at all. Chem-Nuclear has been successful in achieving community acceptance at the Barnwell facility and elsewhere. For example, last June in Fall River County, South Dakota, citizens voted almost 2:1 to support the development of a low-level radioactive waste disposal facility. In Edgemont, the city nearest the proposed site, 85% of the voters were in favor of the proposed facility

  4. Emerging Radiation Health-Risk Mitigation Technologies

    International Nuclear Information System (INIS)

    Wilson, J.W.; Cucinotta, F.A.; Schimmerling, W.

    2004-01-01

    Past space missions beyond the confines of the Earth's protective magnetic field have been of short duration and protection from the effects of solar particle events was of primary concern. The extension of operational infrastructure beyond low-Earth orbit to enable routine access to more interesting regions of space will require protection from the hazards of the accumulated exposures of Galactic Cosmic Rays (GCR). There are significant challenges in providing protection from the long-duration exposure to GCR: the human risks to the exposures are highly uncertain and safety requirements places unreasonable demands in supplying sufficient shielding materials in the design. A vigorous approach to future radiation health-risk mitigation requires a triage of techniques (using biological and technical factors) and reduction of the uncertainty in radiation risk models. The present paper discusses the triage of factors for risk mitigation with associated materials issues and engineering design methods

  5. Improving Operational Risk Management Using Business Performance Management Technologies

    Directory of Open Access Journals (Sweden)

    Bram Pieket Weeserik

    2018-02-01

    Full Text Available Operational Risk Management (ORM comprises the continuous management of risks resulting from: human actions, internal processes, systems, and external events. With increasing requirements, complexity and a growing volume of risks, information systems provide benefits for integrating risk management activities and optimizing performance. Business Performance Management (BPM technologies are believed to provide a solution for effective Operational Risk Management by offering several combined technologies including: work flow, data warehousing, (advanced analytics, reporting and dashboards. BPM technologies can be integrated with an organization’s Planning & Control cycle and related to strategic objectives. This manuscript aims to show how ORM can benefit from BPM technologies via the development and practical validation of a new maturity model. The B4ORM maturity model was developed following the Design Science Research approach. The maturity model relates specific maturity levels of ORM processes with BPM technologies applicable for a specific maturity stage. There appears to be a strong relationship (0.78 with ORM process maturity and supporting BPM technologies. The B4ORM maturity model as described in this manuscript provides an ideal path of BPM technologies related to six distinctive stages of ORM, leading towards technologies suitable for continuous improvement of ORM processes and organization-wide integration.

  6. Got risk? risk-centric perspective for spacecraft technology decision-making

    Science.gov (United States)

    Feather, Martin S.; Cornford, Steven L.; Moran, Kelly

    2004-01-01

    A risk-based decision-making methodology conceived and developed at JPL and NASA has been used to aid in decision making for spacecraft technology assessment, adoption, development and operation. It takes a risk-centric perspective, through which risks are used as a reasoning step to interpose between mission objectives and risk mitigation measures.

  7. The spectre of uncertainty in communicating technological risk

    Energy Technology Data Exchange (ETDEWEB)

    Broesius, Michael T. [Univ. of California, Livermore, CA (United States)

    1993-12-01

    The literature does not clearly describe the potential moral and ethical conflicts that can exist between technology sponsors and the technical communicators whose job it is to present potentially risky technology to the non-technical people most likely to be imperiled by such risk. Equally important, the literature does not address the issue of uncertainty -- not the uncertainty likely to be experienced by the community at risk, but the unreliable processes and methodologies used by technology sponsors to define, quantify, and develop strategies to mitigate technological risks. In this paper, the author goes beyond a description of risk communication, the nature of the generally predictable interaction between technology advocates and non-technically trained individuals, and current trends in the field. Although that kind of information is critical to the success of any risk communication activity, and he has included it when necessary to provide background and perspective, without knowing how and why risk assessment is done, it has limited practical applicability outside the sterile, value-free vacuum in which it is usually framed. Technical communicators, particularly those responsible for communicating potential technological risk, must also understand the social, political, economic, statistical, and ethical issues they will invariably encounter.

  8. Discussion and acceptance of technology-induced risks

    International Nuclear Information System (INIS)

    Esser, R.

    1986-01-01

    The Gesellschaft fuer Sicherheitswissenschaft (GfS) chose as the main topic of its 7th International Summer Symposium held from May 26-28, 1986 the question of how our highly industrialized society, which not only lives on industry's efficiency, but also has to live with its technological risks, copes with this challenge. About 200 experts gathered for the seminar and discussed about 30 lectures presented, dealing with subjects such as: Technological risks between law and practice; - Risk minimization as a public good; - Risks and related problems, and safety science; - Do the institutionalized procedures create more safety. (orig./HP) [de

  9. Process cost and facility considerations in the selection of primary cell culture clarification technology.

    Science.gov (United States)

    Felo, Michael; Christensen, Brandon; Higgins, John

    2013-01-01

    The bioreactor volume delineating the selection of primary clarification technology is not always easily defined. Development of a commercial scale process for the manufacture of therapeutic proteins requires scale-up from a few liters to thousands of liters. While the separation techniques used for protein purification are largely conserved across scales, the separation techniques for primary cell culture clarification vary with scale. Process models were developed to compare monoclonal antibody production costs using two cell culture clarification technologies. One process model was created for cell culture clarification by disc stack centrifugation with depth filtration. A second process model was created for clarification by multi-stage depth filtration. Analyses were performed to examine the influence of bioreactor volume, product titer, depth filter capacity, and facility utilization on overall operating costs. At bioreactor volumes 5,000 L, clarification using centrifugation followed by depth filtration offers significant cost savings. For bioreactor volumes of ∼ 2,000 L, clarification costs are similar between depth filtration and centrifugation. At this scale, factors including facility utilization, available capital, ease of process development, implementation timelines, and process performance characterization play an important role in clarification technology selection. In the case study presented, a multi-product facility selected multi-stage depth filtration for cell culture clarification at the 500 and 2,000 L scales of operation. Facility implementation timelines, process development activities, equipment commissioning and validation, scale-up effects, and process robustness are examined. © 2013 American Institute of Chemical Engineers.

  10. A perspective on the comparison of risks from different technologies

    International Nuclear Information System (INIS)

    Kastenberg, W.E.; Griesmeyer, J.M.; Johnson, D.H.

    1982-01-01

    Comparisons between the risks of various technologies have been used in evaluating different technologies which produce particular benefits, in developing perspectives on the acceptability of risks, and in developing suitable priorities for risk reductions. Although difficult and controversial these comparisons will continue to be used in design, in regulation and in the socio-political process. In this paper, some of the problems that arise in the comparison of risk are discussed. These include the choice of the proper range of impacts to be addressed in the risk assessments, the difficulty of ensuring completeness in the treatment of the impacts that are addressed, and uncertainties that arise from modeling and from the scarcity of data and its interpretation. In addition, the disparate manner in which the various risks are manifested (types, magnitude and distribution of consequences as well as frequency) makes the comparison of the risks controversial

  11. Economic reassessment of energy technologies with risk-management techniques

    International Nuclear Information System (INIS)

    Mohr, Markus; Unger, Hermann

    1999-01-01

    A new approach for the reassessment of modern energy technologies is discussed. This mainly addresses renewable-energy systems, like photovoltaics or wind converters. A new number called the 'Marginal Energy Risk Price (MERP) for Hedging' is introduced. (Author)

  12. Technology and Risk Sciences Program. FY99 Annual Report

    International Nuclear Information System (INIS)

    Regens, James L.

    2000-01-01

    In making the transition from weapons production to environmental restoration, DOE has found that it needs to develop reliable means of defining and understanding health and environmental risks and of selecting cost-efficient environmental management technologies so that cleanup activities can be appropriately directed. Through the Technology and Risk Sciences Project, the Entergy Spatial Analysis Research Laboratory attempts to provide DOE with products that incorporate spatial analysis techniques in the risk assessment, communication, and management processes; design and evaluate methods for evaluating innovative environmental technologies; and collaborate and access technical information on risk assessment methodologies, including multimedia modeling and environmental technologies in Russia and the Ukraine, while in addition training and developing the skills of the next generation of scientists and environmental professionals

  13. Technology and Risk Sciences Program. FY99 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Regens, James L.

    2000-01-01

    In making the transition from weapons production to environmental restoration, DOE has found that it needs to develop reliable means of defining and understanding health and environmental risks and of selecting cost-efficient environmental management technologies so that cleanup activities can be appropriately directed. Through the Technology and Risk Sciences Project, the Entergy Spatial Analysis Research Laboratory attempts to provide DOE with products that incorporate spatial analysis techniques in the risk assessment, communication, and management processes; design and evaluate methods for evaluating innovative environmental technologies; and collaborate and access technical information on risk assessment methodologies, including multimedia modeling and environmental technologies in Russia and the Ukraine, while in addition training and developing the skills of the next generation of scientists and environmental professionals.

  14. Managing the Perception of Advanced Technology Risks in Mission Proposals

    Science.gov (United States)

    Bellisario, Sebastian Nickolai

    2012-01-01

    Through my work in the project proposal office I became interested in how technology advancement efforts affect competitive mission proposals. Technology development allows for new instruments and functionality. However, including technology advancement in a mission proposal often increases perceived risk. Risk mitigation has a major impact on the overall evaluation of the proposal and whether the mission is selected. In order to evaluate the different approaches proposals took I compared the proposals claims of heritage and technology advancement to the sponsor feedback provided in the NASA debriefs. I examined a set of Discovery 2010 Mission proposals to draw patterns in how they were evaluated and come up with a set of recommendations for future mission proposals in how they should approach technology advancement to reduce the perceived risk.

  15. [Radon risk in healthcare facilities: environmental monitoring and effective dose].

    Science.gov (United States)

    Cammarota, B; Cascone, Maria Teresa; De Paola, L; Schillirò, F; Del Prete, U

    2009-01-01

    Radon, the second cause of lung cancer after smoking (WHO- IARC), is a natural, radioactive gas, which originates from the soil and pollutes indoor air, especially in closed or underground spaces. The purpose of this study was to determine the concentration of radon gas, its effective dose, and the measurement of microclimatic degrees C; U.R. % and air velocity in non-academic intensive care units of public hospitals in the Naples area. The annual average concentrations of radon gas were detected with EIC type ionization electret chambers, type LLT with exposure over four 3-month periods. The concentrations varied for all health facilities between 186 and 1191 Bq/m3. Overall, the effective dose of exposure to radon gas of 3mSv/a recommended by Italian legislation was never exceeded. The concentration of radon gas showed a decreasing trend starting from the areas below ground level to those on higher floors; such concentrations were also influenced by natural and artificial ventilation of the rooms, building materials used for walls, and by the state of maintenance and improvements of the building (insulation of floors and walls). The data obtained confirmed the increased concentration of radionuclides in the yellow tuff of volcanic origin in the Campania Region and the resulting rate of release of radon gas, whereas the reinforced concrete structure (a hospital located on the hillside), which had the lowest values, proved to provide good insulation against penetration and accumulation of radon gas.

  16. Mixed and low-level waste treatment facility project. Volume 3, Waste treatment technologies (Draft)

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-01

    The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

  17. Shuttle Laser Technology Experiment Facility (LTEF)-to-airplane lasercom experiment: Airplane considerations

    Science.gov (United States)

    Kalil, Ford

    1990-01-01

    NASA is considering the use of various airplanes for a Shuttle Laser Technology Experiment Facility (LTEF)-to-Airplane laser communications experiment. As supporting documentation, pertinent technical details are included about the potential use of airplanes located at Ames Research Center and Wallops Flight Facility. The effects and application of orbital mechanics considerations are also presented, including slant range, azimuth, elevation, and time. The pros and cons of an airplane equipped with a side port with a bubble window versus a top port with a dome are discussed.

  18. Nanotechnology risk perceptions and communication: emerging technologies, emerging challenges.

    Science.gov (United States)

    Pidgeon, Nick; Harthorn, Barbara; Satterfield, Terre

    2011-11-01

    Nanotechnology involves the fabrication, manipulation, and control of materials at the atomic level and may also bring novel uncertainties and risks. Potential parallels with other controversial technologies mean there is a need to develop a comprehensive understanding of processes of public perception of nanotechnology uncertainties, risks, and benefits, alongside related communication issues. Study of perceptions, at so early a stage in the development trajectory of a technology, is probably unique in the risk perception and communication field. As such it also brings new methodological and conceptual challenges. These include: dealing with the inherent diversity of the nanotechnology field itself; the unfamiliar and intangible nature of the concept, with few analogies to anchor mental models or risk perceptions; and the ethical and value questions underlying many nanotechnology debates. Utilizing the lens of social amplification of risk, and drawing upon the various contributions to this special issue of Risk Analysis on Nanotechnology Risk Perceptions and Communication, nanotechnology may at present be an attenuated hazard. The generic idea of "upstream public engagement" for emerging technologies such as nanotechnology is also discussed, alongside its importance for future work with emerging technologies in the risk communication field. © 2011 Society for Risk Analysis.

  19. Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory

    International Nuclear Information System (INIS)

    Lucas, D.E.; Ikenberry, T.A.

    1993-09-01

    Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91. The DOE nuclear safety policy states that the general public shall be protected such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL, and are not intended for evaluation of routine exposures. A safety analyst uses the,frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy. The radiological risk evaluation guidelines are an effective tool for assisting in the management of risk at DOE nonreactor nuclear facilities. These guidelines (1) meet the nuclear safety policy of DOE, (2) establish a tool for managing risk at a consistent level within the defined constraints, and (3) set risk at an appropriate level, as compared with other risks encountered by the public and worker. Table S.1 summarizes the guidelines developed in this report

  20. Scientific and Technological Facilities in CIEMAT; Informe sobre Instalaciones del CIEMAT

    Energy Technology Data Exchange (ETDEWEB)

    Vaquero Ortiz, E. M.; Cascante Díaz, E.; González Pineda, L. M.

    2015-07-01

    The precise knowledge of the available Resources in an Organization, regardless the work it carries out, is an essential strategic enabler to achieve its goals. Material Resources are part of the resources in an organization, The “Material Resources” expression includes a wide span of elements, because a Material Resource, as a generic concept, is each and every specific physical mean, utilized to get any of the Organization objectives. In CIEMAT, as Public Research Agency, its Material Resources consist of its scientific and technological facilities. These resources are the basis of this Agency numerous amount of technical capabilities, allowing it to carry out its research, development and innovation activity to transfer its results to the society later. This report is a summary on CIEMAT scientific and technological facilities, whose spread can help to show its scientific and technological capabilities, to enable the execution of a wide variety of projects and to open new external cooperation channels. Outstanding among these facilities are two “Unique Scientific and Technological Infrastructures” (ICTS) and the Ionizing Radiations Metrology Laboratory (LMRI) which is the Spanish National Standards Laboratory for ionising radiations.

  1. Risk-Based Disposal Plan for PCB Paint in the TRA Fluorinel Dissolution Process Mockup and Gamma Facilities Canal

    Energy Technology Data Exchange (ETDEWEB)

    R. A. Montgomery

    2008-05-01

    This Toxic Substances Control Act Risk-Based Polychlorinated Biphenyl Disposal plan was developed for the Test Reactor Area Fluorinel Dissolution Process Mockup and Gamma Facilities Waste System, located in Building TRA-641 at the Reactor Technology Complex, Idaho National Laboratory Site, to address painted surfaces in the empty canal under 40 CFR 761.62(c) for paint, and under 40 CFR 761.61(c) for PCBs that may have penetrated into the concrete. The canal walls and floor will be painted with two coats of contrasting non-PCB paint and labeled as PCB. The canal is covered with open decking; the access grate is locked shut and signed to indicate PCB contamination in the canal. Access to the canal will require facility manager permission. Protective equipment for personnel and equipment entering the canal will be required. Waste from the canal, generated during ultimate Decontamination and Decommissioning, shall be managed and disposed as PCB Bulk Product Waste.

  2. Reducing the potential for conflict between proponents and the public regarding the risks entailed by radioactive waste management facilities

    International Nuclear Information System (INIS)

    Rogers, B.G.

    1984-01-01

    Sources of potential conflict between proponents and the public regarding the risks entailed by radioactive waste management facilities are identified and analyzed. Programs and policies are suggested that could reduce conflict over the siting and operation of such facilities

  3. The development of application technology for image processing in nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Jong Min; Lee, Yong Bum; Kim, Woog Ki; Sohn, Surg Won; Kim, Seung Ho; Hwang, Suk Yeoung; Kim, Byung Soo

    1991-01-01

    The object of this project is to develop application technology of image processing in nuclear facilities where image signal are used for reliability and safety enhancement of operation, radiation exposure reduce of operator, and automation of operation processing. We has studied such application technology for image processing in nuclear facilities as non-tactile measurement, remote and automatic inspection, remote control, and enhanced analysis of visual information. On these bases, automation system and real-time image processing system are developed. Nuclear power consists in over 50% share of electic power supply of our country nowdays. So, it is required of technological support for top-notch technology in nuclear industry and its related fields. Especially, it is indispensable for image processing technology to enhance the reliabilty and safety of operation, to automate the process in a place like a nuclear power plant and radioactive envionment. It is important that image processing technology is linked to a nuclear engineering, and enhance the reliability abd safety of nuclear operation, as well as decrease the dose rate. (Author)

  4. A probabilistic risk assessment of the LLNL Plutonium Facility's evaluation basis fire operational accident. Revision 1

    International Nuclear Information System (INIS)

    Brumburgh, G.P.

    1995-01-01

    The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous programmatic activities involving plutonium to include device fabrication, development of improved and/or unique fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed in July 1994 to address operational safety and acceptable risk to employees, the public, government property, and the environmental. This paper outlines the PRA analysis of the Evaluation Basis Fire (EBF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

  5. Probabilistic risk analysis for Test Area North Hot Shop Storage Pool Facility

    International Nuclear Information System (INIS)

    Meale, B.M.; Satterwhite, D.G.

    1990-01-01

    A storage pool facility used for storing spent fuel and radioactive debris from the Three Mile Island (TMI) accident was evaluated to determine the risk associated with its normal operations. Several hazards were identified and examined to determine if any any credible accident scenarios existed. Expected annual occurrence frequencies were calculated for hazards for which accident scenarios were identified through use of fault trees modeling techniques. Fault tree models were developed for two hazards: (1) increased radiation field and (2) spread of contamination. The models incorporated facets of the operations within the facility as well as the facility itself. 6 refs

  6. Integrating Technology into the Curriculum for "At-Risk" Youth

    Science.gov (United States)

    McCall, Denise

    2009-01-01

    This Independent Learning Project (ILP) discusses the best practices in educational technology to improve the behavior, instruction, and learning of at-risk youth, for whom technology offers unique opportunities. Research is compiled from numerous scholarly print and online sources. A guide for teachers provides detailed strategies, software…

  7. Incorporating the Technology Roadmap Uncertainties into the Project Risk Assessment

    International Nuclear Information System (INIS)

    Bonnema, B.E.

    2002-01-01

    This paper describes two methods, Technology Roadmapping and Project Risk Assessment, which were used to identify and manage the technical risks relating to the treatment of sodium bearing waste at the Idaho National Engineering and Environmental Laboratory. The waste treatment technology under consideration was Direct Vitrification. The primary objective of the Technology Roadmap is to identify technical data uncertainties for the technologies involved and to prioritize the testing or development studies to fill the data gaps. Similarly, project management's objective for a multi-million dollar construction project includes managing all the key risks in accordance to DOE O 413.3 - ''Program and Project Management for the Acquisition of Capital Assets.'' In the early stages, the Project Risk Assessment is based upon a qualitative analysis for each risk's probability and consequence. In order to clearly prioritize the work to resolve the technical issues identified in the Technology Roadmap, the issues must be cross- referenced to the project's Risk Assessment. This will enable the project to get the best value for the cost to mitigate the risks

  8. Risk assessment associated to possible concrete degradation of a near surface disposal facility

    Science.gov (United States)

    Capra, B.; Billard, Y.; Wacquier, W.; Gens, R.

    2013-07-01

    This article outlines a risk analysis of possible concrete degradation performed in the framework of the preparation of the Safety Report of ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste and Enriched Fissile Materials, for the construction and operation of a near surface disposal facility of category A waste - short-lived low and intermediate level waste - in Dessel. The main degradation mechanism considered is the carbonation of different concrete components over different periods (from the building phase up to 2000 years), which induces corrosion of the rebars. A dedicated methodology mixing risk analysis and numerical modeling of concrete carbonation has been developed to assess the critical risks of the disposal facility at different periods. According to the results obtained, risk mapping was used to assess the impact of carbonation of concrete on the different components at the different stages. The most important risk is related to an extreme situation with complete removal of the earth cover and side embankment.

  9. 137Cs Radiological risk estimation of NSD facility at Karawang site by using RESRAD onsite application: effect of cover thickness

    Science.gov (United States)

    Setiawan, B.; Prihastuti, S.; Moersidik, S. S.

    2018-02-01

    The operational of near surface disposal facility during waste packages loading activity into the facility, or in a monitoring activity around disposal facility at Karawang area is predicted to give a radiological risk to radiation workers. The thickness of disposal facility cover system affected the number of radiological risk of workers. Due to this reason, a radiological risk estimation needs to be considered. RESRAD onsite code is applied for this purpose by analyse the individual accepted dose and radiological risk data of radiation workers. The obtained results and then are compared with radiation protection reference in accordance with national regulation. In this case, the data from the experimental result of Karawang clay as host of disposal facility such as Kd value of 137Cs was used. Results showed that the thickness of the cover layer of disposal facility affected to the radiological risk which accepted by workers in a near surface disposal facility.

  10. Use of reliability engineering tools in safety and risk assessment of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Raso, Amanda Laureano; Vasconcelos, Vanderley de; Marques, Raíssa Oliveira; Soares, Wellington Antonio; Mesquita, Amir Zacarias, E-mail: amandaraso@hotmail.com, E-mail: vasconv@cdtn.br, E-mail: raissaomarques@gmail.com, E-mail: soaresw@cdtn.br, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil). Serviço de Tecnologia de Reatores

    2017-07-01

    Safety, reliability and availability are fundamental criteria in design, construction and operation of nuclear facilities, as nuclear power plants. Deterministic and probabilistic risk assessments of such facilities are required by regulatory authorities in order to meet licensing regulations, contributing to assure safety, as well as reduce costs and environmental impacts. Probabilistic Risk Assessment has become an important part of licensing requirements of the nuclear power plants in Brazil and in the world. Risk can be defined as a qualitative and/or quantitative assessment of accident sequence frequencies (or probabilities) and their consequences. Risk management is a systematic application of management policies, procedures and practices to identify, analyze, plan, implement, control, communicate and document risks. Several tools and computer codes must be combined, in order to estimate both probabilities and consequences of accidents. Event Tree Analysis (ETA), Fault Tree Analysis (FTA), Reliability Block Diagrams (RBD), and Markov models are examples of evaluation tools that can support the safety and risk assessment for analyzing process systems, identifying potential accidents, and estimating consequences. Because of complexity of such analyzes, specialized computer codes are required, such as the reliability engineering software develop by Reliasoft® Corporation. BlockSim (FTA, RBD and Markov models), RENO (ETA and consequence assessment), Weibull++ (life data and uncertainty analysis), and Xfmea (qualitative risk assessment) are some codes that can be highlighted. This work describes an integrated approach using these tools and software to carry out reliability, safety, and risk assessment of nuclear facilities, as well as, and application example. (author)

  11. Use of reliability engineering tools in safety and risk assessment of nuclear facilities

    International Nuclear Information System (INIS)

    Raso, Amanda Laureano; Vasconcelos, Vanderley de; Marques, Raíssa Oliveira; Soares, Wellington Antonio; Mesquita, Amir Zacarias

    2017-01-01

    Safety, reliability and availability are fundamental criteria in design, construction and operation of nuclear facilities, as nuclear power plants. Deterministic and probabilistic risk assessments of such facilities are required by regulatory authorities in order to meet licensing regulations, contributing to assure safety, as well as reduce costs and environmental impacts. Probabilistic Risk Assessment has become an important part of licensing requirements of the nuclear power plants in Brazil and in the world. Risk can be defined as a qualitative and/or quantitative assessment of accident sequence frequencies (or probabilities) and their consequences. Risk management is a systematic application of management policies, procedures and practices to identify, analyze, plan, implement, control, communicate and document risks. Several tools and computer codes must be combined, in order to estimate both probabilities and consequences of accidents. Event Tree Analysis (ETA), Fault Tree Analysis (FTA), Reliability Block Diagrams (RBD), and Markov models are examples of evaluation tools that can support the safety and risk assessment for analyzing process systems, identifying potential accidents, and estimating consequences. Because of complexity of such analyzes, specialized computer codes are required, such as the reliability engineering software develop by Reliasoft® Corporation. BlockSim (FTA, RBD and Markov models), RENO (ETA and consequence assessment), Weibull++ (life data and uncertainty analysis), and Xfmea (qualitative risk assessment) are some codes that can be highlighted. This work describes an integrated approach using these tools and software to carry out reliability, safety, and risk assessment of nuclear facilities, as well as, and application example. (author)

  12. Cancer risks near nuclear facilities: the importance of research design and explicit study hypotheses.

    Science.gov (United States)

    Wing, Steve; Richardson, David B; Hoffmann, Wolfgang

    2011-04-01

    In April 2010, the U.S. Nuclear Regulatory Commission asked the National Academy of Sciences to update a 1990 study of cancer risks near nuclear facilities. Prior research on this topic has suffered from problems in hypothesis formulation and research design. We review epidemiologic principles used in studies of generic exposure-response associations and in studies of specific sources of exposure. We then describe logical problems with assumptions, formation of testable hypotheses, and interpretation of evidence in previous research on cancer risks near nuclear facilities. Advancement of knowledge about cancer risks near nuclear facilities depends on testing specific hypotheses grounded in physical and biological mechanisms of exposure and susceptibility while considering sample size and ability to adequately quantify exposure, ascertain cancer cases, and evaluate plausible confounders. Next steps in advancing knowledge about cancer risks near nuclear facilities require studies of childhood cancer incidence, focus on in utero and early childhood exposures, use of specific geographic information, and consideration of pathways for transport and uptake of radionuclides. Studies of cancer mortality among adults, cancers with long latencies, large geographic zones, and populations that reside at large distances from nuclear facilities are better suited for public relations than for scientific purposes.

  13. Determination and acceptance of the risks of technologies

    International Nuclear Information System (INIS)

    Jungermann, H.

    1982-01-01

    As a consequence of the problems posed by modern technologies (e.g. nuclear power), a new discipline 'risk assessment' has developed over the last decade. The paper describes, first, some studies on determinants of perceived risk, e.g. frequency of accidents, catastrophic potential, voluntariness, dreadfulness, and controllability. Cognitive factors which help explaining research findings include availability, overconfidence, and perceptual set. Secondly, studies on the acceptability of risk are presented in which the focus is on the relation between perceived risk and perceived benefit. Following this, a brief outline of methods is given that have been suggested for determining the acceptability of risk (revealed preferences, expressed preferences, cost-benefit analysis, and decision analysis). Finally, the impact of the development of risky technologies and of risk research is discussed as it is evidenced in the controversies that have emerged within the scientific community, between science and politics, and between science and the public. (orig./HSCH) [de

  14. Imaging the risks - risking the image: Social impact assessment of the final disposal facility

    International Nuclear Information System (INIS)

    Avolahti, J.; Vira, J.

    1999-01-01

    Preparations for the final disposal of spent nuclear fuel in Finland started about twenty years ago. At present the work is carried out by Posiva Oy, which in 1996 took over the programme managed earlier by Teollisuuden Voima Oy, one of the country's nuclear power companies. From 1996 on the preparations have been made for all the spent fuel from Finnish nuclear power stations. The site for the final disposal facility will be selected among four alternatives by the end of 2000 and - assuming that the technical approach proposed by Posiva is accepted by the Government and the Parliament - the construction of the repository will start in the 2010s. The disposal operations are planned to be started in 2020. The alternative four sites have gone through a systematic site selection process based on geologic siting criteria and on environmental and cultural considerations. One of the objectives of the process was to avoid inhabited areas, agricultural fields, valuable groundwater or preservation areas as well as areas which might draw interest as regards the potential for ore deposits. The idea was that the field investigations and later the possible disposal facility should not cause any harm to local people. Two of the candidate sites are at present nuclear power plant sites situated at the coast, the two other candidates are inland sites with no nuclear activities. The geologic siting investigations were started in 1987. Interim assessments of the results so far have been made in 1992 and 1996 and a final report of all the investigations will be published before the end of 2000. The present view is that all four candidates are geologically suitable for siting the repository. Posiva's EIA for the final disposal of spent fuel in Finland is nearing completion. A considerable effort was made to involve local groups and individuals in the assessment process. Yet the participation remained limited and consisted mainly of active opponents of the project and of those who were

  15. Imaging the risks - risking the image: Social impact assessment of the final disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Avolahti, J.; Vira, J. [Posiva Oy, Helsinki (Finland)

    1999-12-01

    Preparations for the final disposal of spent nuclear fuel in Finland started about twenty years ago. At present the work is carried out by Posiva Oy, which in 1996 took over the programme managed earlier by Teollisuuden Voima Oy, one of the country's nuclear power companies. From 1996 on the preparations have been made for all the spent fuel from Finnish nuclear power stations. The site for the final disposal facility will be selected among four alternatives by the end of 2000 and - assuming that the technical approach proposed by Posiva is accepted by the Government and the Parliament - the construction of the repository will start in the 2010s. The disposal operations are planned to be started in 2020. The alternative four sites have gone through a systematic site selection process based on geologic siting criteria and on environmental and cultural considerations. One of the objectives of the process was to avoid inhabited areas, agricultural fields, valuable groundwater or preservation areas as well as areas which might draw interest as regards the potential for ore deposits. The idea was that the field investigations and later the possible disposal facility should not cause any harm to local people. Two of the candidate sites are at present nuclear power plant sites situated at the coast, the two other candidates are inland sites with no nuclear activities. The geologic siting investigations were started in 1987. Interim assessments of the results so far have been made in 1992 and 1996 and a final report of all the investigations will be published before the end of 2000. The present view is that all four candidates are geologically suitable for siting the repository. Posiva's EIA for the final disposal of spent fuel in Finland is nearing completion. A considerable effort was made to involve local groups and individuals in the assessment process. Yet the participation remained limited and consisted mainly of active opponents of the project and of those

  16. Technologies for Assessing Behavioral and Cognitive Markers of Suicide Risk

    Science.gov (United States)

    2017-10-01

    assessing behavioral and cognitive markers of risk for suicide among U.S. Army National Guard personnel. Journal of Environmental Research and Public Policy...effective ways to prevent injury and death from suicide • No reliable method for predicting suicide risk in military personnel • Behavioral (e.g...AWARD NUMBER: W81XWH-15-1-0632 TITLE: Technologies for Assessing Behavioral and Cognitive Markers of Suicide Risk PRINCIPAL INVESTIGATOR: Brian

  17. Overview of the Defense Programs Research and Technology Development Program for fiscal year 1993. Appendix II research laboratories and facilities

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-30

    This document contains summaries of the research facilities that support the Defense Programs Research and Technology Development Program for FY 1993. The nine program elements are aggregated into three program clusters as follows: (1) Advanced materials sciences and technologies; chemistry and materials, explosives, special nuclear materials (SNM), and tritium. (2) Design sciences and advanced computation; physics, conceptual design and assessment, and computation and modeling. (3) Advanced manufacturing technologies and capabilities; system engineering science and technology, and electronics, photonics, sensors, and mechanical components. Section I gives a brief summary of 23 major defense program (DP) research and technology facilities and shows how these major facilities are organized by program elements. Section II gives a more detailed breakdown of the over 200 research and technology facilities being used at the Laboratories to support the Defense Programs mission.

  18. Risk Management Technologies With Logic and Probabilistic Models

    CERN Document Server

    Solozhentsev, E D

    2012-01-01

    This book presents intellectual, innovative, information technologies (I3-technologies) based on logical and probabilistic (LP) risk models. The technologies presented here consider such models for structurally complex systems and processes with logical links and with random events in economics and technology.  The volume describes the following components of risk management technologies: LP-calculus; classes of LP-models of risk and efficiency; procedures for different classes; special software for different classes; examples of applications; methods for the estimation of probabilities of events based on expert information. Also described are a variety of training courses in these topics. The classes of risk models treated here are: LP-modeling, LP-classification, LP-efficiency, and LP-forecasting. Particular attention is paid to LP-models of risk of failure to resolve difficult economic and technical problems. Amongst the  discussed  procedures of I3-technologies  are the construction of  LP-models,...

  19. Technology of mirror machines: LLL facilities for magnetic mirror fusion experiments

    International Nuclear Information System (INIS)

    Batzer, T.H.

    1977-01-01

    Significant progress in plasma confinement and temperature has been achieved in the 2XIIB facility at Livermore. These encouraging results, and their theoretical corroboration, have provided a firm basis for the design of a new generation of magnetic mirror experiments, adding support to the mirror concept of a fusion reactor. Two new mirror experiments have been proposed to succeed the currently operating 2XIIB facility. The first of these called TMX (Tandem Mirror Experiment) has been approved and is currently under construction. TMX is designed to utilize the intrinsic positive plasma potential of two strong, and relatively small, minimum B mirror cells to enhance the confinement of a much larger, magnetically weaker, centrally-located mirror cell. The second facility, MFTF (Mirror Fusion Test Facility), is currently in preliminary design with line item approval anticipated for FY 78. MFTF is designed primarily to exploit the experimental and theoretical results derived from 2XIIB. Beyond that, MFTF will develop the technology for the transition from the present small mirror experiments to large steady-state devices such as the mirror FERF/FTR. The sheer magnitude of the plasma volume, magnetic field, neutral beam power, and vacuum pumping capacity, particularly in the case of MFTF, has placed new and exciting demands on engineering technology. An engineering overview of MFTF, TMX, and associated MFE activities at Livermore will be presented

  20. Prospective Teachers’ Tendencies to Utilize From the Facilities of Contemporary Educational Technology

    OpenAIRE

    Gizem SAYGILI; Teoman İsmail KESERCİOĞLU

    2015-01-01

    In terms of effectiveness and efficiency, it is important to determine the views of prospective teachers related to taking advantage of the facilities of contemporary educational technology. This study which aims to identify prospective teachers’ attitudes towards computer-assisted learning was conducted with 140 prospective teachers (86 female, 54 male) who have been attending pedagogical formation education at Süleyman Demirel University in the 2013 academic year. In this study, in eight di...

  1. Large-scale decontamination and decommissioning technology demonstration project at a former uranium metal production facility

    International Nuclear Information System (INIS)

    Martineit, R.A.; Borgman, T.D.; Peters, M.S.; Stebbins, L.L.

    1997-01-01

    The Department of Energy's (DOE) Office of Science and Technology Decontamination and Decommissioning (D ampersand D) Focus Area, led by the Federal Energy Technology Center, has been charged with improving upon baseline D ampersand D technologies with the goal of demonstrating and validating more cost-effective and safer technologies to characterize, deactivate, survey, decontaminate, dismantle, and dispose of surplus structures, buildings, and their contents at DOE sites. The D ampersand D Focus Area's approach to verifying the benefits of the improved D ampersand D technologies is to use them in large-scale technology demonstration (LSTD) projects at several DOE sites. The Fernald Environmental Management Project (FEMP) was selected to host one of the first three LSTD's awarded by the D ampersand D Focus Area. The FEMP is a DOE facility near Cincinnati, Ohio, that was formerly engaged in the production of high quality uranium metal. The FEMP is a Superfund site which has completed its RUFS process and is currently undergoing environmental restoration. With the FEMP's selection to host an LSTD, the FEMP was immediately faced with some challenges. The primary challenge was that this LSTD was to be integrated into the FEMP's Plant 1 D ampersand D Project which was an ongoing D ampersand D Project for which a firm fixed price contract had been issued to the D ampersand D Contractor. Thus, interferences with the baseline D ampersand D project could have significant financial implications. Other challenges include defining and selecting meaningful technology demonstrations, finding/selecting technology providers, and integrating the technology into the baseline D ampersand D project. To date, twelve technologies have been selected, and six have been demonstrated. The technology demonstrations have yielded a high proportion of open-quotes winners.close quotes All demonstrated, technologies will be evaluated for incorporation into the FEMP's baseline D ampersand D

  2. Applicability of water-jet cutting technology to nuclear facility decommissioning

    International Nuclear Information System (INIS)

    Abe, Tadashi; Nisizaki, Tadashi; Matumura, Hiroyuki; Ikemoto, Yosikazu; Simizu, Hideki

    1991-01-01

    In nuclear facilities there exist, besides relatively simple components, such as vessels and piping, numerous complex components including the multilayered plate with water layer in between, a bunch of thin tubes and composite lamination of dissimilar materials like metal/non-metal. In conventional development of reactor dismantling technology, the technology development has been made mainly for remote cutting of thick-walled structures like the reactor pressure vessel and the reactor internals. These techniques, however, are not always suitable in cutting the above-mentioned structures. As means of cutting such structures efficiently, these is available the abrasion water-jet cutting technology. This technology is now drawing attention for cutting or shaping new materials like composite material and ceramics in high precision and high efficiency. In the present report by way of its feasibility in nuclear facilities decommissioning the following are described. Principle and features of the water-jet cutting technology, system con-figuration, cutting or shaping performance, and some examples of the cutting and shaping. (author)

  3. Proceedings of the 8. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

    International Nuclear Information System (INIS)

    Antariksawan, Anhar R.; Soetrisnanto, Arnold Y.; Aziz, Ferhat; Untoro, Pudji; Su'ud, Zaki; Zarkasi, Amin Santosa; Umar, Faraz H.; Teguh Bambang; Hafnan, M.; Mustafa, Bustani; Rosfian, H.

    2002-10-01

    The eight proceeding of National Seminar on Technology and Safety of Nuclear Power Plant and Nuclear Facilities held by National Atomic Energy Agency and University of Trisakti. The aims of Seminar is to exchange and disseminate information about safety and nuclear Power Plant Temperature Reactor and Application for National Development sustain able and High Technology. This Seminar covers all aspect Technology, Power Reactor : Research Reactor; High Temperature Reactor and Nuclear Facilities. There are 33 articles have separated index

  4. Advancing nuclear technology and research. The advanced test reactor national scientific user facility

    Energy Technology Data Exchange (ETDEWEB)

    Benson, Jeff B; Marshall, Frances M [Idaho National Laboratory, Idaho Falls, ID (United States); Allen, Todd R [Univ. of Wisconsin, Madison, WI (United States)

    2012-03-15

    The Advanced Test Reactor (ATR), at the Idaho National Laboratory (INL), is one of the world's premier test reactors for providing the capability for studying the effects of intense neutron and gamma radiation on reactor materials and fuels. The INL also has several hot cells and other laboratories in which irradiated material can be examined to study material radiation effects. In 2007 the US Department of Energy (DOE) designated the ATR as a National Scientific User Facility (NSUF) to facilitate greater access to the ATR and the associated INL laboratories for material testing research. The mission of the ATR NSUF is to provide access to world-class facilities, thereby facilitating the advancement of nuclear science and technology. Cost free access to the ATR, INL post irradiation examination facilities, and partner facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to United States Department of Energy. To increase overall research capability, ATR NSUF seeks to form strategic partnerships with university facilities that add significant nuclear research capability to the ATR NSUF and are accessible to all ATR NSUF users. (author)

  5. Integrated Electrical and Thermal Grid Facility - Testing of Future Microgrid Technologies

    Directory of Open Access Journals (Sweden)

    Sundar Raj Thangavelu

    2015-09-01

    Full Text Available This paper describes the Experimental Power Grid Centre (EPGC microgrid test facility, which was developed to enable research, development and testing for a wide range of distributed generation and microgrid technologies. The EPGC microgrid facility comprises a integrated electrical and thermal grid with a flexible and configurable architecture, and includes various distributed energy resources and emulators, such as generators, renewable, energy storage technologies and programmable load banks. The integrated thermal grid provides an opportunity to harness waste heat produced by the generators for combined heat, power and cooling applications, and support research in optimization of combined electrical-thermal systems. Several case studies are presented to demonstrate the testing of different control and operation strategies for storage systems in grid-connected and islanded microgrids. One of the case studies also demonstrates an integrated thermal grid to convert waste heat to useful energy, which thus far resulted in a higher combined energy efficiency. Experiment results confirm that the facility enables testing and evaluation of grid technologies and practical problems that may not be apparent in a computer simulated environment.

  6. Efficiency and cost advantages of an advanced-technology nuclear electrolytic hydrogen-energy production facility

    Science.gov (United States)

    Donakowski, T. D.; Escher, W. J. D.; Gregory, D. P.

    1977-01-01

    The concept of an advanced-technology (viz., 1985 technology) nuclear-electrolytic water electrolysis facility was assessed for hydrogen production cost and efficiency expectations. The facility integrates (1) a high-temperature gas-cooled nuclear reactor (HTGR) operating a binary work cycle, (2) direct-current (d-c) electricity generation via acyclic generators, and (3) high-current-density, high-pressure electrolyzers using a solid polymer electrolyte (SPE). All subsystems are close-coupled and optimally interfaced for hydrogen production alone (i.e., without separate production of electrical power). Pipeline-pressure hydrogen and oxygen are produced at 6900 kPa (1000 psi). We found that this advanced facility would produce hydrogen at costs that were approximately half those associated with contemporary-technology nuclear electrolysis: $5.36 versus $10.86/million Btu, respectively. The nuclear-heat-to-hydrogen-energy conversion efficiency for the advanced system was estimated as 43%, versus 25% for the contemporary system.

  7. Present state of inspection robot technology in nuclear power facilities. Case of fast breeder reactors

    International Nuclear Information System (INIS)

    Ara, Kuniaki

    1995-01-01

    In the maintenance works in nuclear power facilities such as checkup, inspection and repair, for the main purpose of radiation protection, remote operation technology was introduced since relatively early stage, and at present, the robots that carry out the inspection works for confirming the soundness of main equipment have been developed and put to practical use. At the time of introducing these technologies, in addition to the research and development of robots proper, the coordination with the design of plant machinery and equipment facilities as the premise of introducing robots is an important requirement. In this report, the present state of the development of remote inspection technology for fast breeder reactors is introduced, and the matters to which attention is paid in the plant design for introducing robots are explained. First, fast breeder reactors are described. The needs of robotizing and adopting remote operation in nuclear power facilities are explained, using the examples of the inspection system for a reactor vessel and the inspection system for steam generator heat transfer tubes. (K.I.)

  8. Risk assessments of innovative technologies for treatment of mixed waste

    International Nuclear Information System (INIS)

    Ragaini, R.C.; Aycock, M.T.; Russell, J.E.

    1993-01-01

    The mission of the US Department of Energy's (DOE'S) Mixed Waste Integrated Program (MWIP) is to develop complete and appropriate technologies for the treatment of DOE mixed low-level waste and transuranic wastes in order to ensure that all affected DOE installations and projects can come into compliance with environmental law and meet DOE's 30-yr cleanup and operational goals. The MWIP will achieve its goal by developing technologies that are in compliance with regulatory requirements, are socially and politically viable, and are cost beneficial and effective in disposed waste source term and volume reduction. The project management plan for MWIP requires that technologies be evaluated in accordance with criteria that rank technologies with regard to performance, risk, and cost-effectiveness. This paper addresses the methodology used to rank alternative mixed-water treatment technologies with regard to relative risk

  9. Risk Management Technique for design and operation of facilities and equipment

    Science.gov (United States)

    Fedor, O. H.; Parsons, W. N.; Coutinho, J. De S.

    1975-01-01

    The Risk Management System collects information from engineering, operating, and management personnel to identify potentially hazardous conditions. This information is used in risk analysis, problem resolution, and contingency planning. The resulting hazard accountability system enables management to monitor all identified hazards. Data from this system are examined in project reviews so that management can decide to eliminate or accept these risks. This technique is particularly effective in improving the management of risks in large, complex, high-energy facilities. These improvements are needed for increased cooperation among industry, regulatory agencies, and the public.

  10. Dealing with uncertainty and pursuing superior technology options in risk management-The inherency risk analysis

    International Nuclear Information System (INIS)

    Helland, Aasgeir

    2009-01-01

    Current regulatory systems focus on the state of scientific evidence as the predominant factor for how to handle risks to human health and the environment. However, production and assessment of risk information are costly and time-consuming, and firms have an intrinsic disincentive to produce and distribute information about risks of their products as this could endanger their production opportunities and sales. An emphasis on more or better science may result in insufficient thought and attention going into the exploration of technology alternatives, and that risk management policies miss out on the possible achievement of a more favorable set of consequences. In this article, a method is proposed that combines risk assessment with the search for alternative technological options as a part of the risk management procedure. The method proposed is the inherency risk analysis where the first stage focuses on the original agent subject to investigation, the second stage focuses on identifying technological options whereas the third stage reviews the different alternatives, searching for the most attractive tradeoffs between costs and inherent safety. This is then used as a fundament for deciding which technology option to pursue. This method aims at providing a solution-focused, systematic technology-based approach for addressing and setting priorities for environmental problems. By combining risk assessment with a structured approach to identify superior technology options within a risk management system, the result could very well be a win-win situation for both company and the environment.

  11. A new framework to assess risk for a spent fuel dry storage facility

    International Nuclear Information System (INIS)

    Ryu, J. H.; Jae, M. S.; Jung, C. W.

    2004-01-01

    A spent fuel dry storage facility is a dry cooling storage facility for storing irradiated nuclear fuel and associated radioactive materials. It has very small possibilities to release radiation materials. It means a safety analysis for a spent fuel dry storage facility is required before construction. In this study, a new framework for assessing risk associated with a spent fuel dry storage facility is represented. A safety assessment framework includes 3 modules such as assessment of basket/cylinder failure rates, that of overall storage system, and site modeling. A reliability physics model for failure rates, event tree analysis(ETA)/fault tree analysis for system analysis, Bayesian analysis for initial events data, and MACCS code for consequence analysis have been used in this study

  12. 75 FR 9007 - National Science and Technology Council, Committee on Technology Capstone Workshop Risk...

    Science.gov (United States)

    2010-02-26

    ... Nanotechnology: Public Meeting ACTION: Notice of public meeting. SUMMARY: The National Nanotechnology Coordination Office (NNCO), on behalf of the Nanoscale Science, Engineering, and Technology (NSET) Subcommittee... and Ethical, Legal, and Societal Implications (ELSI) of Nanotechnology. Risk Management Methods is one...

  13. Risk-benefit evaluation for large technological systems

    International Nuclear Information System (INIS)

    Okrent, D.

    1979-01-01

    The related topics of risk-benefit analysis, risk analysis, and risk-acceptance criteria (How safe is safe enough) are of growing importance. An interdisciplinary study on various aspects of these topics, including applications to nuclear power, was recently completed at the University of California, Los Angeles (UCLA), with the support of the National Science Foundation. In addition to more than 30 topical reports and various open-literature publications, a final report (UCLA-ENG-7777) to the study, titled ''A Generalized Evaluation Approach to Risk--Benefit for Large Technological Systems and Its Application to Nuclear Power'', was issued in early 1978. This article briefly summarizes portions of the final report dealing with general aspects of risk-benefit methodology, societal knowledge and perception of risk, and risk-acceptance criteria

  14. Study on technology for minimizing radiation risk

    International Nuclear Information System (INIS)

    Lee, Jeong Ho; Kim, In Gyu; Kim, Jin Kyu; Lee, Kang Suk; Kim, Kug Chan; Chun, Ki Chung.

    1997-01-01

    Apoptosis, also called programmed cell death to discriminate it from necrosis, is characterized by : chromatin condensation, apoptotic body formation, fragmentation of DNA into oligonucleosome sized pieces, swelling and progressive cell degradation. We examined morphological and biochemical changes of T-lymphocytes following gamma irradiation exposure. The results are followings. 1) Murine lymphocytes have several characteristics : The irradiated cells undergo morphological and biochemical changes characteristic of apoptosis, causing growth delay. (0.01, 0.1, 1.0 Gy) 2) The onset of DNA fragmentation in cells occurs after one more cell divisions. 3) DNA fragmentation in cells occurs in all irradiated group (0.1, 1.0, 2.0, 4.0 Gy, 24 hours following gamma radiation exposure) 4) Apoptotic bodies were detected by confocal microscope with ease when compared with electron microscope. For the developing technology for minimizing radiation damage, the following experimental works have been done. 1) Establishment of experimental system for pre-screening of radioprotectants - Screening of protective substances using TSH bioindicator - Efficacy test of some radioprotective materials 2) TSH bioindicator system can make a scientific role in screening unknown materials for their possible radioprotective effect. (author). 42 refs., 3 tabs., 9 figs

  15. Study on technology for minimizing radiation risk

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jeong Ho; Kim, In Gyu; Kim, Jin Kyu; Lee, Kang Suk; Kim, Kug Chan; Chun, Ki Chung

    1997-01-01

    Apoptosis, also called programmed cell death to discriminate it from necrosis, is characterized by : chromatin condensation, apoptotic body formation, fragmentation of DNA into oligonucleosome sized pieces, swelling and progressive cell degradation. We examined morphological and biochemical changes of T-lymphocytes following gamma irradiation exposure. The results are followings. (1) Murine lymphocytes have several characteristics : The irradiated cells undergo morphological and biochemical changes characteristic of apoptosis, causing growth delay. (0.01, 0.1, 1.0 Gy) (2) The onset of DNA fragmentation in cells occurs after one more cell divisions. (3) DNA fragmentation in cells occurs in all irradiated group (0.1, 1.0, 2.0, 4.0 Gy, 24 hours following gamma radiation exposure) (4) Apoptotic bodies were detected by confocal microscope with ease when compared with electron microscope. For the developing technology for minimizing radiation damage, the following experimental works have been done. (1) Establishment of experimental system for pre-screening of radioprotectants - Screening of protective substances using TSH bioindicator - Efficacy test of some radioprotective materials (2) TSH bioindicator system can make a scientific role in screening unknown materials for their possible radioprotective effect. (author). 42 refs., 3 tabs., 9 figs.

  16. Preserving technological secrets vs. proliferation risks

    International Nuclear Information System (INIS)

    Palacios, E.

    2004-01-01

    In July of 1991 Argentina and Brazil assume the commitment exclusively for the pacific use of the nuclear energy and of their respective nuclear programs through a Bilateral agreement. This Agreement also believes the ABACC, for monitoring the execution of the assumed commitments. From their beginnings, the Agency was involved in the application of safeguards in plants of ultra-centrifugation being this a so much topic of relevance for ABACC like for the IAEA. To preserve technological secrets, for demand of the operator, the cascades of centrifuges find hidden behind of panels. ABACC understanding this necessity, it has explored alternatives that allow to reconcile the interests of all the involved parts. A focus of safeguards based on the control of the perimeter one has come using in the plants of small installed capacity and in the first two cascades of a commercial plant in construction. In the work the efficiency of this focus is discussed as increases the capacity of the plant and with it concludes that it will be necessary to begin a dialogue on the future implementation of methods more standardized of control in the commercial plant, giving time so that the designs are adapted to the new reality. (Author)

  17. Risk classification for nuclear facilities in connection with the illegal use of nuclear materials

    International Nuclear Information System (INIS)

    Bahm, W.; Naegele, G.; Sellinschegg, D.

    1976-01-01

    It is shown, and illustrated by an example, that specific conditions at a nuclear facility to a large extent determine the probability of a successful illegal attack against that facility. Therefore, a categorization of nuclear materials according to the associated hazards alone, as practised currently, does not appear to be sufficient for the establishment of a balanced national physical protection system. In this paper a possible way of categorizing nuclear facilities according to the associated risks, determined as objectively as possible, is discussed. It is felt that initially the analysis should be restricted to the determination of the conditional risks, associated with illegal acquisition and use of radioactive materials by a postulated hostile or similar group. (author)

  18. Electron beam facilities and technologies developed in the Institute of Nuclear Chemistry and Technology

    International Nuclear Information System (INIS)

    Chmielewski, A.G.; Walis, L.; Zimek, Z.

    1992-01-01

    The operation of the first electron accelerator has been started at Institute /former Institute for Nuclear Research/ in 1971. This LAE-13/9 accelerator is a two-section lineac with adjustable energy of electrons: 5 to 13 MeV and the beam power up to 9 kW. The main technologies developed on the basis of LAE-13/9 are: sterilization, manufacturing of thermoshrinkable materials and modification of semiconductors. The accelerator is operated 4000 hours per year and used for small scale production and services in these fields. The other problems investigated in laboratory scale are: food preservation and hygenization, hygenization of municipal sewage sludge, and bio-conversion of pig-farm wastes into animal fodder. The laboratory experiments are basis for pilot construction and other industrial applications. The mentioned technology of thermoshrinkable tube production was implemented in industrial scale at ZWUT Czluchow which factory is equipped in the accelerator ILU-6 /20 kW, 2 MeV/. On the basis of similar unit a technological installation was built at Institute. The plant is furnished with a conveyer and the rewinding machines for tubes and tapes manufacturing. This allows continuous production of these materials. The plant will start operation next year and linear accelerator /10 MeV, 15 kW/ for this purpose is already delivered. The pilot plant for food preservation and hygenization has been built. It is equipped in small pilot accelerator 10 MeV, 1 kW and will be furnished with 10 MeV, 10 kW lineac this year. Beside of this technological lines Institute is furnished in Van de Graff accelerator /2, MeV, 100 μA/ and another laboratory unit LAE-10 /10 MeV, 10-100 ns 2 us/ is under construction. (J.P.N.)

  19. EIF onshore discharges : a quantitative environmental risk assessment tool for onshore facilities

    Energy Technology Data Exchange (ETDEWEB)

    Hagemann, R.; Smit, M.G.D.; Frost, T.K. [Statoil ASA, Stavenger (Norway); Firth, S.K. [Firth Consultants, Bristol (United Kingdom); Stone, K. [WorleyParsons, Victoria, BC (Canada)

    2009-07-01

    The proper management of environmental risk is a key requirement of StatoilHydro's governing documents and is a key consideration in all phases of StatoilHydro's activities. In order to help manage risks in an effective and sustainable manner, StatoilHydro has led the development of the environmental impact factor (EIF) risk assessment tool. The EIF is utilized by all operators on the Norwegian Continental Shelf for reporting continuous improvements in produced water management to the authorities. The EIF concept has also been applied to evaluate environmental risk from air emissions, offshore oil spills and drilling discharges, discharges from onshore facilities to sea and discharges and spills from onshore installations. In order to identify the remaining hypothetical risk from a new facility, optimized with respect to environmental protection, this paper presented a case study, where the tool was applied to an oil sands steam assisted gravity drainage facility in Alberta. The paper discussed the EIF model and results of the case study. It was concluded that as a result of the use of generic principles for environmental risk assessment, combined with databases with parameter information for common soil and aquifer types, the EIF tool could be applied to any site ranging from wetlands to deserts. 5 refs., 2 tabs., 3 figs.

  20. RISK ANALYSIS IN INFORMATION TECHNOLOGY AND COMMUNICATION OUTSOURCING

    Directory of Open Access Journals (Sweden)

    Edmir Parada Vasques Prado

    2011-12-01

    Full Text Available This research aims at evaluating the risk analysis process in Information Technology and Communication (ICT outsourcing conducted by organizations of the private sector. The research is characterized by being a descriptive, quantitative and transversal type study, which was used the survey method. Data were collected through questionnaire, the sample is not random and we used a convenience sampling process. The research made contributions to understanding the risk analysis process in ICT services outsourcing, and identified statistically significant relationships between risk analysis, organization's size and its industry, and between risk analysis and diversity of outsourced services

  1. Five walls against risk communication of nuclear technology

    International Nuclear Information System (INIS)

    Tsuchiya, Tomoko

    2012-01-01

    The author has made efforts to establish risk communication in the nuclear industry since the JCO criticality accident. Some people understood the importance and the usefulness of risk communication both for local residents and their own business. Others, however, thought it troublesome, costly, and useless for their organization and nuclear safety. I think, unfortunately, experiences after the Fukushima accident force them to hesitate at communicating risks with the public more and more. I will discuss why and how risk communication of nuclear technology is difficult. (author)

  2. Risk-informed approaches to assess ecological safety of facilities with radioactive waste

    International Nuclear Information System (INIS)

    Vashchenko, V.N.; Zlochevskij, V.V.; Skalozubov, V.I.

    2011-01-01

    Ingenious risk-informed methods to assess ecological safety of facilities with radioactive waste are proposed in the paper. Probabilistic norms on lethal outcomes and reliability of safety barriers are used as safety criteria. Based on the probability measures, it is established that ecological safety conditions are met for the standard criterion of lethal outcomes

  3. Supporting Facility Management Processes through End-Users’ Integration and Coordinated BIM-GIS Technologies

    Directory of Open Access Journals (Sweden)

    Claudio Mirarchi

    2018-05-01

    Full Text Available The integration of facility management and building information modelling (BIM is an innovative and critical undertaking process to support facility maintenance and management. Even though recent research has proposed various methods and performed an increasing number of case studies, there are still issues of communication processes to be addressed. This paper presents a theoretical framework for digital systems integration of virtual models and smart technologies. Based on the comprehensive analysis of existing technologies for indoor localization, a new workflow is defined and designed, and it is utilized in a practical case study to test the model performance. In the new workflow, a facility management supporting platform is proposed and characterized, featuring indoor positioning systems to allow end users to send geo-referenced reports to central virtual models. In addition, system requirements, information technology (IT architecture and application procedures are presented. Results show that the integration of end users in the maintenance processes through smart and easy tools can overcome the existing limits of barcode systems and building management systems for failure localization. The proposed framework offers several advantages. First, it allows the identification of every element of an asset including wide physical building elements (walls, floors, etc. without requiring a prior mapping. Second, the entire cycle of maintenance activities is managed through a unique integrated system including the territorial dimension. Third, data are collected in a standard structure for future uses. Furthermore, the integration of the process in a centralized BIM-GIS (geographical information system information management system admit a scalable representation of the information supporting facility management processes in terms of assets and supply chain management and monitoring from a spatial perspective.

  4. Health risks in perspective: Judging health risks of energy technologies. Revision 5/94

    Energy Technology Data Exchange (ETDEWEB)

    Rowe, M.D.

    1992-09-01

    The purpose of this report is to provide perspective on the various risks to which man is routinely exposed. It serves as a basis for understanding the meaning of quantitative risk estimates and for comparing new or newly-discovered risks with other, better-understood risks. Specific emphasis is placed on health risks of energy technologies. This report is not a risk assessment; nor does it contain instructions on how to do a risk assessment. Rather, it provides background information on how most of us think about risks and why it is difficult to do it rationally, it provides a philosophy and data with which to do a better job of judging risks more rationally, and it provides an overview of where risks of energy technologies fit within the spectrum of all risks. Much of the quantitative information provided here is on relative risk of dying of various causes. This is not because risk of dying is seen as the most important kind of risk, but because the statistics on mortality rates by cause are the highest quality data available on health risks in the general population.

  5. Risk Management in Information Technology Project: An Empirical Study

    Directory of Open Access Journals (Sweden)

    Kornelius Irfandhi

    2016-09-01

    Full Text Available The companies are facing some risks due to changes in a dynamic environment. If risks are not managed properly, it will have some negative impacts on the companies at the present and the future. One important function of the Information Technology (IT governance is risk management. Risk management in IT project aims to provide a safe environment for IT projects undertaken. Risk management becomes an important process for the success of IT projects. This article discussed the risk of IT project and whether there was a relationship between risk management and the success of the project. The method used was performing a literature review of several scientific articles which published between 2010 and 2014. The results of this study are the presence of risk management and risk manager influence the success of the project. Risk analysis and risk monitoring and control also have a relationship with the subjective performance of IT projects. If risk management is applied properly, the chance of the success of the projects undertaken can be increased. 

  6. Novel technologies for the detection of undeclared nuclear activities, materials and facilities

    Energy Technology Data Exchange (ETDEWEB)

    Whichello, Julian V.K.; Annese, Cynthia E. [International Atomic Energy Agency, Vienna (Austria). Division of Technical Support

    2008-07-01

    This paper will discuss the International Atomic Energy Agency's (IAEA's) Novel Technologies Project and its main goal of developing improved methods and technologies that will further enhance the detection of undeclared nuclear activities, materials and facilities. A major and fundamental task within the Project has been the development of methodologies and tools for identifying, documenting and utilizing nuclear fuel cycle (NFC) indicators and signatures (I and S) to facilitate a nuclear safeguards technology gap analysis. The outcome of this work will provide a basis for a novel range of methods and instruments, the development of which will contribute to the IAEA's overall objective of enhanced detection capabilities. (author)

  7. Sitewide risk perspectives for the Rocky Flats Environmental Technology Site

    International Nuclear Information System (INIS)

    Olinger, S.J.

    1998-05-01

    The US Department of Energy (DOE) has recently finalized a closure plan (originally called the Ten Year Plan) for closure and environmental cleanup of previous nuclear weapons facilities. The DOE Rocky Flats Field Office has established priorities for risk reduction work to Support closure activities, as well as addressing those hazards associated with storage and management of radioactive materials and hazardous chemicals. To provide information for future National Environmental Policy Act (NEPA) or other regulatory assessments of specific risk reduction projects identified in the Closure Plan, a risk assessment of normal operations and potential accidents was recently prepared to provide an updated baseline of the cumulative impacts to the worker, public and environment due to the Site's operations, activities, and environmental conditions in light of the Site's change in mission, and of future closure projects. This paper summarizes the risk assessment approach, results, and conclusions

  8. Risk assessment on hazards for decommissioning safety of a nuclear facility

    International Nuclear Information System (INIS)

    Jeong, Kwan-Seong; Lee, Kune-Woo; Lim, Hyeon-Kyo

    2010-01-01

    A decommissioning plan should be followed by a qualitative and quantitative safety assessment of it. The safety assessment of a decommissioning plan is applied to identify the potential (radiological and non-radiological) hazards and risks. Radiological and non-radiological hazards arise during decommissioning activities. The non-radiological or industrial hazards to which workers are subjected during a decommissioning and dismantling process may be greater than those experienced during an operational lifetime of a facility. Workers need to be protected by eliminating or reducing the radiological and non-radiological hazards that may arise during routine decommissioning activities and as well as during accidents. The risk assessment method was developed by using risk matrix and fuzzy inference logic, on the basis of the radiological and non-radiological hazards for a decommissioning safety of a nuclear facility. Fuzzy inference of radiological and non-radiological hazards performs a mapping from radiological and non-radiological hazards to risk matrix. Defuzzification of radiological and non-radiological hazards is the conversion of risk matrix and priorities to the maximum criterion method and the mean criterion method. In the end, a composite risk assessment methodology, to rank the risk level on radiological and non-radiological hazards of the decommissioning tasks and to prioritize on the risk level of the decommissioning tasks, by simultaneously combining radiological and non-radiological hazards, was developed.

  9. Application of advanced remote systems technology to future waste handling facilities

    International Nuclear Information System (INIS)

    Kring, C.T.; Meacham, S.A.

    1987-01-01

    The Consolidated Fuel Reprocessing Program (CFRP) at Oak Ridge National Laboratory (ORNL) has been advancing the technology of remote handling and remote maintenance for in-cell systems planned for future nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor is directly applicable to the proposed in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The application of teleoperated, force-reflecting servomanipulators with television viewing could be a major step forward in waste handling facility design. Primary emphasis in the current program is the operation of a prototype remote handling and maintenance system, the advanced servomanipulator (ASM), which specifically addresses the requirements of fuel reprocessing and waste handling with emphasis on force reflection, remote maintainability, reliability, radiation tolerance, and corrosion resistance. Concurrent with the evolution of dexterous manipulators, concepts have also been developed that provide guidance for standardization of the design of the remotely operated and maintained equipment, the interface between the maintenance tools and the equipment, and the interface between the in-cell components and the facility

  10. Description and Operational Experiences of the Engineering Test Facility - Helium Technology (ETF-HT)

    International Nuclear Information System (INIS)

    Zhang Zuoyi; Yang Mingde; Bo Hanliang; Duan Riqqiang; Zhu Hongye

    2014-01-01

    This paper presents the configuration of the Engineering Test Facility - Helium Technology (ETF-HT) and the information of its key components and subsystems, which is located in the Changping campus of Tsinghua University. The ETF-HT facility began to be constructed in Jan. 2009. The main objective of the facility is to test and verify the thermo-hydraulic performance of one full-sized modular unit of HTR-PM helically coiled SG assembly. In the ETF-HT facility, electricity energy is used to heat the loop helium, centrifugal blower is used to circulate the helium medium, and the heat sink is one would-tested SG module. Up to now, except for the tested SG module, preheater and hot gas duct under way of construction, the other components has been installed in situ. Via the temporary connection of the installed components, the preliminary operation of the loop has been carried out to test its performances as can be done, which include the loop leak tightness, blower pneumatic performance and electrical heater at partial thermal load. (author)

  11. International technology exchange in support of the Defense Waste Processing Facility wasteform production

    International Nuclear Information System (INIS)

    Kitchen, B.G.

    1989-01-01

    The nearly completed Defense Waste Processing Facility (DWPF) is a Department of Energy (DOE) facility at the Savannah River Site that is designed to immobilize defense high level radioactive waste (HLW) by vitrification in borosilicate glass and containment in stainless steel canisters suitable for storage in the future DOE HLW repository. The DWPF is expected to start cold operation later this year (1990), and will be the first full scale vitrification facility operating in the United States, and the largest in the world. The DOE has been coordinating technology transfer and exchange on issues relating to HLW treatment and disposal through bi-lateral agreements with several nations. For the nearly fifteen years of the vitrification program at Savannah River Laboratory, over two hundred exchanges have been conducted with a dozen international agencies involving about five-hundred foreign national specialists. These international exchanges have been beneficial to the DOE's waste management efforts through confirmation of the choice of the waste form, enhanced understanding of melter operating phenomena, support for paths forward in political/regulatory arenas, confirmation of costs for waste form compliance programs, and establishing the need for enhancements of melter facility designs. This paper will compare designs and schedules of the international vitrification programs, and will discuss technical areas where the exchanges have provided data that have confirmed and aided US research and development efforts, impacted the design of the DWPF and guided the planning for regulatory interaction and product acceptance

  12. A beamline systems model for Accelerator-Driven Transmutation Technology (ADTT) facilities

    Energy Technology Data Exchange (ETDEWEB)

    Todd, A.M.M.; Paulson, C.C.; Peacock, M.A. [Grumman Research and Development Center, Princeton, NJ (United States)] [and others

    1995-10-01

    A beamline systems code, that is being developed for Accelerator-Driven Transmutation Technology (ADTT) facility trade studies, is described. The overall program is a joint Grumman, G.H. Gillespie Associates (GHGA) and Los Alamos National Laboratory effort. The GHGA Accelerator Systems Model (ASM) has been adopted as the framework on which this effort is based. Relevant accelerator and beam transport models from earlier Grumman systems codes are being adapted to this framework. Preliminary physics and engineering models for each ADTT beamline component have been constructed. Examples noted include a Bridge Coupled Drift Tube Linac (BCDTL) and the accelerator thermal system. A decision has been made to confine the ASM framework principally to beamline modeling, while detailed target/blanket, balance-of-plant and facility costing analysis will be performed externally. An interfacing external balance-of-plant and facility costing model, which will permit the performance of iterative facility trade studies, is under separate development. An ABC (Accelerator Based Conversion) example is used to highlight the present models and capabilities.

  13. A beamline systems model for Accelerator-Driven Transmutation Technology (ADTT) facilities

    International Nuclear Information System (INIS)

    Todd, Alan M. M.; Paulson, C. C.; Peacock, M. A.; Reusch, M. F.

    1995-01-01

    A beamline systems code, that is being developed for Accelerator-Driven Transmutation Technology (ADTT) facility trade studies, is described. The overall program is a joint Grumman, G. H. Gillespie Associates (GHGA) and Los Alamos National Laboratory effort. The GHGA Accelerator Systems Model (ASM) has been adopted as the framework on which this effort is based. Relevant accelerator and beam transport models from earlier Grumman systems codes are being adapted to this framework. Preliminary physics and engineering models for each ADTT beamline component have been constructed. Examples noted include a Bridge Coupled Drift Tube Linac (BCDTL) and the accelerator thermal system. A decision has been made to confine the ASM framework principally to beamline modeling, while detailed target/blanket, balance-of-plant and facility costing analysis will be performed externally. An interfacing external balance-of-plant and facility costing model, which will permit the performance of iterative facility trade studies, is under separate development. An ABC (Accelerator Based Conversion) example is used to highlight the present models and capabilities

  14. Technological risk: Perception and handling in the EEC

    International Nuclear Information System (INIS)

    Schuster, G.

    1980-01-01

    The Europeans tend to believe that in their own country science is put to use for the benefit of people in general. But this reductance is accompanied by a widespread feeling in all countries that politicians do not give serious enough consideration to the choices that have to be made in this field. The more technology interferes with the moral and physical sphere of man, the more cautious people are, considering such technology to be risky. The more public opinion is conscious of what is at stake with possible risks and hazards, the more people are inclined to run these risks and hazards. (DG)

  15. Development and validation of fall risk screening tools for use in residential aged care facilities.

    Science.gov (United States)

    Delbaere, Kim; Close, Jacqueline C T; Menz, Hylton B; Cumming, Robert G; Cameron, Ian D; Sambrook, Philip N; March, Lyn M; Lord, Stephen R

    2008-08-18

    To develop screening tools for predicting falls in nursing home and intermediate-care hostel residents who can and cannot stand unaided. Prospective cohort study in residential aged care facilities in northern Sydney, New South Wales, June 1999-June 2003. 2005 people aged 65-104 years (mean +/- SD, 85.7+/-7.1 years). Demographic, health, and physical function assessment measures; number of falls over a 6-month period; validity of the screening models. Ability to stand unaided was identified as a significant event modifier for falls. In people who could stand unaided, having either poor balance or two of three other risk factors (previous falls, nursing home residence, and urinary incontinence) increased the risk of falling in the next 6 months threefold (sensitivity, 73%; specificity, 55%). In people who could not stand unaided, having any one of three risk factors (previous falls, hostel residence, and using nine or more medications) increased the risk of falling twofold (sensitivity, 87%; specificity, 29%). These two screening models are useful for identifying older people living in residential aged care facilities who are at increased risk of falls. The screens are easy to administer and contain items that are routinely collected in residential aged care facilities in Australia.

  16. Environmental risk analysis of oil handling facilities in port areas. Application to Tarragona harbor (NE Spain).

    Science.gov (United States)

    Valdor, Paloma F; Gómez, Aina G; Puente, Araceli

    2015-01-15

    Diffuse pollution from oil spills is a widespread problem in port areas (as a result of fuel supply, navigation and loading/unloading activities). This article presents a method to assess the environmental risk of oil handling facilities in port areas. The method is based on (i) identification of environmental hazards, (ii) characterization of meteorological and oceanographic conditions, (iii) characterization of environmental risk scenarios, and (iv) assessment of environmental risk. The procedure has been tested by application to the Tarragona harbor. The results show that the method is capable of representing (i) specific local pollution cases (i.e., discriminating between products and quantities released by a discharge source), (ii) oceanographic and meteorological conditions (selecting a representative subset data), and (iii) potentially affected areas in probabilistic terms. Accordingly, it can inform the design of monitoring plans to study and control the environmental impact of these facilities, as well as the design of contingency plans. Copyright © 2014 Elsevier Ltd. All rights reserved.

  17. Waiting for Disasters: A Risk Reduction Assessment of Technological Disasters

    Science.gov (United States)

    Rovins, Jane; Winningham, Sam

    2010-05-01

    This session provides a risk reduction/mitigation assessment of natural hazards causation of technological disasters and possible solution. People use technology in an attempt to not only control their environment but nature itself in order to make them feel safe and productive. Most strategies for managing hazards followed a traditional planning model i.e. study the problem, identify and implement a solution, and move on to the next problem. This approach is often viewed as static model and risk reduction is more of an upward, positive, linear trend. However, technological disasters do not allow risk reduction action to neatly fit this upward, positive, linear trend with actual or potential threats to the environment and society. There are different types of technological disasters, including industrial accidents; pipeline ruptures; accidents at power, water and heat supply systems and other lines of communication; sudden collapse of buildings and mines; air crashes; shipwrecks; automobile and railway accidents to name a few. Natural factors can play an essential role in triggering or magnifying technological disasters. They can result from the direct destruction of given technical objects by a hazardous natural process such as the destruction of an atomic power plant or chemical plant due to an earthquake. Other examples would include the destruction of communications or infrastructure systems by heavy snowfalls, strong winds, avalanches. Events in the past ten years clearly demonstrate that natural disasters and the technological disasters that accompany them are not problems that can be solved in isolation and risk reduction can play an important part. Risk reduction was designed to head off the continuing rising financial and structural tolls from disasters. All Hazard Risk Reduction planning was supposed to include not only natural, but technological, and human-made disasters as well. The subsequent disaster risk reduction (DRR) indicators were to provide the

  18. Technology assessment - a workable way out of the 'risk society'?

    International Nuclear Information System (INIS)

    Mueller-Brandeck-Bocquet, G.

    1988-01-01

    On the basis of concrete experience and results in the risk assessment process concerning nuclear technology in the Federal Republic of Germany it becomes apparent that technology asessment can make a contribution towards the required technology domestication. The 'risk management' of the circle of nuclear power generators and the consulting and licensing bodies having failed, a new phase of technology assessment began in 1970, whereby proponents and opponents of nuclear energy had a say. Parallel research on the safety of light water reactors and fast breeders gave valuable insight into the danger potential of nuclear energy while the latent risk of technology assessment misuse became apparent in the decision-finding process concerning the problem of radioactive waste management. In the end it were the Enquete Commission 'Future Nuclear Energy Policy' of the German Bundestag and the studies on social agreeability of energy supply systems which resulted in the perspective of a future without the use of nuclear power being a realistic option. The general findings of technology assessment, e.g. the cognition that there can be no scientific decision in favour of assuming responsibility for nuclear energy, opens up new views and possibilities for acting for the decision-makers in the field of energy policy. (orig./HSCH) [de

  19. Nuclear facilities: repair and replacement technologies; Installations nucleaires: technologies de reparation et de remplacement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The oldest operating reactors are more than 35 years old and are now facing major maintenance operations. The first replacement of a pressurizer took place in autumn 2005 at the St-Lucie plant (Usa) while steam generators have been currently replaced since 1983. Nuclear industry has to adapt to this new market by proposing innovative technological solutions in the reactor maintenance field. This document gathers the 9 papers presented at the conference. The main improvements concern repair works on internal components of PWR-type reactors, the replacement of major components of the primary coolant circuit and surface treatments to limit the propagation of damages. The first paper shows that adequate design and feedback experience are good assets to manage the ageing of a nuclear unit. Another paper shows that a new repair method of a relief valve can avoid its replacement. (A.C.)

  20. Emerging Concepts, Technologies and Opportunities for Mezzo-scale Terahertz and Infrared Facilities

    International Nuclear Information System (INIS)

    Swapan Chattopadhyay; Steven T. Corneliussen; Gwyn P. Williams

    2004-01-01

    Recent advances in high-current particle beam, bright photoinjector, laser and radiofrequency technologies, combined with innovative techniques such as energy recovery and laser-slicing of particle beams, have opened up new scientific opportunities with terahertz and infrared sources. They present new scientific frontiers not just in sources but in basic research applications involving timescale measurements and investigations at the quantum level. Such long-wavelength sources complement high-energy, short-wavelength x-ray sources by allowing collective processes and their ''function'' in complex systems to be probed in a fashion complementary to probing 'structure' via x-rays. This paper outlines and gives examples of the scientific reach of such sources and discusses some actual and envisioned facilities worldwide. Such facilities fall in the mezzo-scale category, bracketed by tabletop lasers and large synchrotrons. They offer unique and directed advances in life, materials and other sciences

  1. Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    Bryant, J.W.; Nenni, J.A.

    2003-01-01

    This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, ''Radioactive Waste Management Manual.'' Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

  2. Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    Jeffrey Bryant

    2008-01-01

    This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, 'Radioactive Waste Management Manual'. Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

  3. Risk and Performance Technologies: Identifying the Keys to Successful Implementation

    International Nuclear Information System (INIS)

    McClain, Lynn; Smith, Art; O'Regan, Patrick

    2002-01-01

    The nuclear power industry has been utilizing risk and performance based technologies for over thirty years. Applications of these technologies have included risk assessment (e.g. Individual Plant Examinations), burden reduction (e.g. Risk-Informed Inservice Inspection, RI-ISI) and risk management (Maintenance Rule, 10CFR50.65). Over the last five to ten years the number of risk-informed (RI) burden reduction initiatives has increased. Unfortunately, the efficiencies of some of these applications have been questionable. This paper investigates those attributes necessary to support successful, cost-effective RI-applications. The premise to this paper is that by understanding the key attributes that support one successful application, insights can be gleaned that will streamline/coordinate future RI-applications. This paper is an extension to a paper presented at the Pressure Vessel and Piping (PVP-2001) Conference. In that paper, a number issues and opportunities were identified that needed to be assessed in order to support future (and efficient) RI-applications. It was noted in the paper that a proper understanding and resolution of these issues will facilitate implementation of risk and performance technology in the operation, maintenance and design disciplines. In addition, it will provide the foundation necessary to support regulatory review and approval. (authors)

  4. Assessing systemwide occupational health and safety risks of energy technologies

    International Nuclear Information System (INIS)

    Rowe, M.D.

    1982-01-01

    Input-output modelling is now being used to assess systemwide occupational and public health and safety risks of energy technologies. Some of the advantages and disadvantages of this method are presented and some of its important limitations are discussed. Its primary advantage is that it provides a standard method with which to compare technologies on a consistent basis without extensive economic analysis. Among the disadvantages are limited range of applicability, limited spectrum of health impacts, and inability to identify unusual health impacts unique to a new technology. (author)

  5. Overview of seismic probabilistic risk assessment for structural analysis in nuclear facilities

    International Nuclear Information System (INIS)

    Reed, J.W.

    1989-01-01

    Probabilistic Risk Assessment (PRA) for seismic events is currently being performed for nuclear and DOE facilities. The background on seismic PRA is presented along with a basic description of the method. The seismic PRA technique is applicable to other critical facilities besides nuclear plants. The different approaches for obtained structure fragility curves are discussed and their applications to structures and equipment, in general, are addressed. It is concluded that seismic PRA is a useful technique for conducting probability analysis for a wide range of classes of structures and equipment

  6. Design risk analysis comparison between low-activation composite and aluminum alloy target chamber for the National Ignition Facility

    International Nuclear Information System (INIS)

    Streckert, H.H.; Schleicher, R.W.

    1997-01-01

    The baseline design for the target chamber for the National Ignition Facility (NIF) consists of an aluminum alloy spherical shell. A low-activation composite chamber (e.g., carbon fiber/epoxy) has important advantages such as enhanced environmental and safety characteristics, improved chamber accessibility due to reduced neutron-induced radioactivity, and elimination of the concrete shield. However, it is critical to determine the design and manufacturing risk for the first application. The replacement of such a critical component requires a detailed development risk assessment. A semiquantitative approach to risk assessment has been applied to this problem based on failure modes, effects, and criticality analysis. This analysis consists of a systematic method for organizing the collective judgment of the designers to identify failure modes, estimate probabilities, judge the severity of the consequence, and illustrate risk in a matrix representation. The results of the analyses indicate that the composite chamber has a reasonably high probability of success in the NIF application. The aluminum alloy chamber, however, represents a lower risk, partially based on a more mature technology. 8 refs., 4 figs., 5 tabs

  7. MicroArray Facility: a laboratory information management system with extended support for Nylon based technologies

    Directory of Open Access Journals (Sweden)

    Beaudoing Emmanuel

    2006-09-01

    Full Text Available Abstract Background High throughput gene expression profiling (GEP is becoming a routine technique in life science laboratories. With experimental designs that repeatedly span thousands of genes and hundreds of samples, relying on a dedicated database infrastructure is no longer an option. GEP technology is a fast moving target, with new approaches constantly broadening the field diversity. This technology heterogeneity, compounded by the informatics complexity of GEP databases, means that software developments have so far focused on mainstream techniques, leaving less typical yet established techniques such as Nylon microarrays at best partially supported. Results MAF (MicroArray Facility is the laboratory database system we have developed for managing the design, production and hybridization of spotted microarrays. Although it can support the widely used glass microarrays and oligo-chips, MAF was designed with the specific idiosyncrasies of Nylon based microarrays in mind. Notably single channel radioactive probes, microarray stripping and reuse, vector control hybridizations and spike-in controls are all natively supported by the software suite. MicroArray Facility is MIAME supportive and dynamically provides feedback on missing annotations to help users estimate effective MIAME compliance. Genomic data such as clone identifiers and gene symbols are also directly annotated by MAF software using standard public resources. The MAGE-ML data format is implemented for full data export. Journalized database operations (audit tracking, data anonymization, material traceability and user/project level confidentiality policies are also managed by MAF. Conclusion MicroArray Facility is a complete data management system for microarray producers and end-users. Particular care has been devoted to adequately model Nylon based microarrays. The MAF system, developed and implemented in both private and academic environments, has proved a robust solution for

  8. Best available technology for the Los Alamos National Laboratory Radioactive Liquid Waste Treatment Facility

    International Nuclear Information System (INIS)

    Midkiff, W.S.; Romero, R.L.; Suazo, I.L.; Garcia, R.; Parsons, R.M.

    1993-01-01

    The existing Los Alamos National Laboratory TA-50 liquid radioactive waste treatment plant RLWP has been in service for over thirty years, during this period many technical, regulatory, and processing changes have occurred. The existing facility can no longer comply with the demands and requirements for continued operation, and would not be able to comply with anticipated stringent future contaminant discharge limitations. Either a major upgrading or replacement of the existing facility is required. In order to assess the most appropriate means of providing an adequate facility to comply with predicted requirements for Ta-50, this Best Available Technology (BAT) Study was conducted to compare feasible technical and economic alternatives in order to define the most favorable technology configuration. This report consists of eleven sections. Section 1 provides a general introduction and background of the TA-50 operations and the basis for this study. Section 2 provides a technical discussion of the unit processes at TA-50 and several other comparable operations at other DOE sites. Section 3 addresses the evaluation and selection of appropriate treatment processes. Section 4 provides an analysis of environmental issues and concerns. Section 5 presents the rationale for the selection of preferred process configurations. Section 6 is the evaluation of operational issues. Section 7 addresses energy and resource use topics. Section 8 provides an economic analysis, and Section 9 summarizes the evaluation and the identification of the BAT. These sections are augmented by appendices. The report identifies the construction of a new radioactive liquid waste treatment facility as the BAT. Based on the information analyzed for this study, this option appears to provide the best combination of environmental compliance, operability, and economic value

  9. Technological options for management of hazardous wastes from US Department of Energy facilities

    Energy Technology Data Exchange (ETDEWEB)

    Chiu, S.; Newsom, D.; Barisas, S.; Humphrey, J.; Fradkin, L.; Surles, T.

    1982-08-01

    This report provides comprehensive information on the technological options for management of hazardous wastes generated at facilities owned or operated by the US Department of Energy (DOE). These facilities annually generate a large quantity of wastes that could be deemed hazardous under the Resource Conservation and Recovery Act (RCRA). Included in these wastes are liquids or solids containing polychlorinated biphenyls, pesticides, heavy metals, waste oils, spent solvents, acids, bases, carcinogens, and numerous other pollutants. Some of these wastes consist of nonnuclear hazardous chemicals; others are mixed wastes containing radioactive materials and hazardous chemicals. Nearly 20 unit processes and disposal methods are presented in this report. They were selected on the basis of their proven utility in waste management and potential applicability at DOE sites. These technological options fall into five categories: physical processes, chemical processes, waste exchange, fixation, and ultimate disposal. The options can be employed for either resource recovery, waste detoxification, volume reduction, or perpetual storage. Detailed descriptions of each technological option are presented, including information on process performance, cost, energy and environmental considerations, waste management of applications, and potential applications at DOE sites. 131 references, 25 figures, 23 tables.

  10. Technological options for management of hazardous wastes from US Department of Energy facilities

    International Nuclear Information System (INIS)

    Chiu, S.; Newsom, D.; Barisas, S.; Humphrey, J.; Fradkin, L.; Surles, T.

    1982-08-01

    This report provides comprehensive information on the technological options for management of hazardous wastes generated at facilities owned or operated by the US Department of Energy (DOE). These facilities annually generate a large quantity of wastes that could be deemed hazardous under the Resource Conservation and Recovery Act (RCRA). Included in these wastes are liquids or solids containing polychlorinated biphenyls, pesticides, heavy metals, waste oils, spent solvents, acids, bases, carcinogens, and numerous other pollutants. Some of these wastes consist of nonnuclear hazardous chemicals; others are mixed wastes containing radioactive materials and hazardous chemicals. Nearly 20 unit processes and disposal methods are presented in this report. They were selected on the basis of their proven utility in waste management and potential applicability at DOE sites. These technological options fall into five categories: physical processes, chemical processes, waste exchange, fixation, and ultimate disposal. The options can be employed for either resource recovery, waste detoxification, volume reduction, or perpetual storage. Detailed descriptions of each technological option are presented, including information on process performance, cost, energy and environmental considerations, waste management of applications, and potential applications at DOE sites. 131 references, 25 figures, 23 tables

  11. Privacy and senior willingness to adopt smart home information technology in residential care facilities.

    Science.gov (United States)

    Courtney, K L

    2008-01-01

    With large predicted increases of the older adult (65 years and older) population, researchers have been exploring the use of smart home information technologies (IT) in residential care (RC) facilities to enhance resident quality of life and safety. Older adults' perceptions of privacy can inhibit their acceptance and subsequent adoption of smart home IT. This qualitative study, guided by principles of grounded theory research, investigated the relationship between privacy, living environment and willingness of older adults living in residential care facilities to adopt smart home IT through focus groups and individual interviews. The findings from this study indicate that privacy can be a barrier for older adults' adoption of smart home IT; however their own perception of their need for the technology may override their privacy concerns. Privacy concerns, as a barrier to technology adoption, can be influenced by both individual-level and community-level factors. Further exploration of the factors influencing older adults' perceptions of smart home IT need is necessary.

  12. Potential applications of advanced remote handling and maintenance technology to future waste handling facilities

    International Nuclear Information System (INIS)

    Kring, C.T.; Herndon, J.N.; Meacham, S.A.

    1987-01-01

    The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) has been advancing the technology in remote handling and remote maintenance of in-cell systems planned for future US nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor are directly applicable to the in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The ORNL developments are based on the application of teleoperated force-reflecting servomanipulators controlled by an operator completely removed from the hazardous environment. These developments address the nonrepetitive nature of remote maintenance in the unstructured environments encountered in a waste handling facility. Employing technological advancements in dexterous manipulators, as well as basic design guidelines that have been developed for remotely maintained equipment and processes, can increase operation and maintenance system capabilities, thereby allowing the attainment of two Federal Waste Management System major objectives: decreasing plant personnel radiation exposure and increasing plant availability by decreasing the mean-time-to-repair in-cell maintenance and process equipment

  13. Potential applications of advanced remote handling and maintenance technology to future waste handling facilities

    International Nuclear Information System (INIS)

    Kring, C.T.; Herndon, J.N.; Meacham, S.A.

    1987-01-01

    The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) has been advancing the technology in remote handling and remote maintenance of in-cell systems planned for future U.S. nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor are directly applicable to the in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The ORNL developments are based on the application of teleoperated force-reflecting servomanipulators controlled by an operator completely removed from the hazardous environment. These developments address the nonrepetitive nature of remote maintenance in the unstructured environments encountered in a waste handling facility. Employing technological advancements in dexterous manipulators, as well as basic design guidelines that have been developed for remotely maintained equipment and processes, can increase operation and maintenance system capabilities, thereby allowing the attainment of two Federal Waste Management System major objectives: decreasing plant personnel radiation exposure and increasing plant availability by decreasing the mean-time-to-repair in-cell maintenance and process equipment

  14. Emerging technologies in healthcare: navigating risks, evaluating rewards.

    Science.gov (United States)

    McGrady, Elizabeth; Conger, Sue; Blanke, Sandra; Landry, Brett J L

    2010-01-01

    The purpose of this prescriptive research is to help decision makers become better informed about three technologies emerging in the healthcare arena by providing a basic description of the technology and describing their current applications, future healthcare deployment, potential risks, and related managerial issues. Two of the technologies, radio frequency identification (RFID) and global positioning systems (GPS), are currently available to healthcare organizations and appear capable of decreasing cost but may require significant initial investment and have disruptive potential. The third technology, nanotechnology, has limited current use but may revolutionize both the delivery of medicine and hospital infrastructure management. With cautious attention to managerial issues and meticulous attention to implementation details, healthcare organizations that can successfully navigate the coming technologically driven paradigm shifts will emerge more resilient organizations.

  15. The advanced test reactor national scientific user facility advancing nuclear technology

    International Nuclear Information System (INIS)

    Allen, T.R.; Thelen, M.C.; Meyer, M.K.; Marshall, F.M.; Foster, J.; Benson, J.B.

    2009-01-01

    To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy (DOE) designated the Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The mission of the ATR NSUF is to provide access to world-class nuclear research facilities, thereby facilitating the advancement of nuclear science and technology. The ATR NSUF seeks to create an engaged academic and industrial user community that routinely conducts reactor-based research. Cost free access to the ATR and PIE facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to DOE mission. Extensive publication of research results is expected as a condition for access. During FY 2008, the first full year of ATR NSUF operation, five university-led experiments were awarded access to the ATR and associated post-irradiation examination facilities. The ATR NSUF has awarded four new experiments in early FY 2009, and anticipates awarding additional experiments in the fall of 2009 as the results of the second 2009 proposal call. As the ATR NSUF program mature over the next two years, the capability to perform irradiation research of increasing complexity will become available. These capabilities include instrumented irradiation experiments and post-irradiation examinations on materials previously irradiated in U.S. reactor material test programs. The ATR critical facility will also be made available to researchers. An important component of the ATR NSUF an education program focused on the reactor-based tools available for resolving nuclear science and technology issues. The ATR NSUF provides education programs including a summer short course, internships, faculty-student team

  16. The Advanced Test Reactor National Scientific User Facility Advancing Nuclear Technology

    International Nuclear Information System (INIS)

    Allen, T.R.; Benson, J.B.; Foster, J.A.; Marshall, F.M.; Meyer, M.K.; Thelen, M.C.

    2009-01-01

    To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy (DOE) designated the Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The mission of the ATR NSUF is to provide access to world-class nuclear research facilities, thereby facilitating the advancement of nuclear science and technology. The ATR NSUF seeks to create an engaged academic and industrial user community that routinely conducts reactor-based research. Cost free access to the ATR and PIE facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to DOE mission. Extensive publication of research results is expected as a condition for access. During FY 2008, the first full year of ATR NSUF operation, five university-led experiments were awarded access to the ATR and associated post-irradiation examination facilities. The ATR NSUF has awarded four new experiments in early FY 2009, and anticipates awarding additional experiments in the fall of 2009 as the results of the second 2009 proposal call. As the ATR NSUF program mature over the next two years, the capability to perform irradiation research of increasing complexity will become available. These capabilities include instrumented irradiation experiments and post-irradiation examinations on materials previously irradiated in U.S. reactor material test programs. The ATR critical facility will also be made available to researchers. An important component of the ATR NSUF an education program focused on the reactor-based tools available for resolving nuclear science and technology issues. The ATR NSUF provides education programs including a summer short course, internships, faculty-student team

  17. Mastery of risks: we build the memory of radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Lacourcelle, C.

    2011-01-01

    The ANDRA, the French national agency of radioactive wastes, is organizing today the information needs of tomorrow. The aim is to allow the future generations to have access to the knowledge of the existence of subsurface radioactive waste facilities and to understand the context and technologies of such facilities. The storage of this information is made on 'permanent paper', a high resistant paper with a lifetime of 600 to 1000 years. An updating of these data is made every 5 years for each waste disposal center. Another project, still in progress, concerns the memory management of deep geologic waste disposal facilities for which the time scale to be considered is of the order of millennia. (J.S.)

  18. Normal accidents living with high-risk technologies

    CERN Document Server

    Perrow, Charles

    1984-01-01

    Normal Accidents analyzes the social side of technological risk. Charles Perrow argues that the conventional engineering approach to ensuring safety--building in more warnings and safeguards--fails because systems complexity makes failures inevitable. He asserts that typical precautions, by adding to complexity, may help create new categories of accidents. (At Chernobyl, tests of a new safety system helped produce the meltdown and subsequent fire.) By recognizing two dimensions of risk--complex versus linear interactions, and tight versus loose coupling--this book provides a powerful framework for analyzing risks and the organizations that insist we run them.

  19. Validation of a model for ranking aquaculture facilities for risk-based disease surveillance.

    Science.gov (United States)

    Diserens, Nicolas; Falzon, Laura Cristina; von Siebenthal, Beat; Schüpbach-Regula, Gertraud; Wahli, Thomas

    2017-09-15

    A semi-quantitative model for risk ranking of aquaculture facilities in Switzerland with regard to the introduction and spread of Viral Haemorrhagic Septicaemia (VHS) and Infectious Haematopoietic Necrosis (IHN) was developed in a previous study (Diserens et al., 2013). The objective of the present study was to validate this model using data collected during field visits on aquaculture sites in four Swiss cantons compared to data collected through a questionnaire in the previous study. A discrepancy between the values obtained with the two different methods was found in 32.8% of the parameters, resulting in a significant difference (pranking of Swiss aquaculture facilities according to their risk of getting infected with or spreading of VHS and IHN, as the five facilities that tested positive for these diseases in the last ten years were ranked as medium or high risk. Moreover, because the seven fish farms that were infected with Infectious Pancreatic Necrosis (IPN) during the same period also belonged to the risk categories medium and high, the classification appeared to correlate with the occurrence of this third viral fish disease. Copyright © 2017 Elsevier B.V. All rights reserved.

  20. Simulation of Cascaded Longitudinal-Space-Charge Amplifier at the Fermilab Accelerator Science & Technology (Fast) Facility

    Energy Technology Data Exchange (ETDEWEB)

    Halavanau, A. [Northern Illinois U.; Piot, P. [Northern Illinois U.

    2015-12-01

    Cascaded Longitudinal Space Charge Amplifiers (LSCA) have been proposed as a mechanism to generate density modulation over a board spectral range. The scheme has been recently demonstrated in the optical regime and has confirmed the production of broadband optical radiation. In this paper we investigate, via numerical simulations, the performance of a cascaded LSCA beamline at the Fermilab Accelerator Science & Technology (FAST) facility to produce broadband ultraviolet radiation. Our studies are carried out using elegant with included tree-based grid-less space charge algorithm.

  1. Technological risk: A problem of growing concern to government

    International Nuclear Information System (INIS)

    Jaeckel, H.

    1980-01-01

    The enumeration of rudimentary technological risks alone shows that the governments of the European states must provide both diagnosis and therapy if the continent is not to degenerate into something between a fully automated chamber of horrors and a sordid refuse dump. Each of the European countries has introduced a great deal of valuable legislation. These laws are clearly inadequate. (DG)

  2. Adversarial risks in social experiments with new technologies

    NARCIS (Netherlands)

    Pieters, Wolter; Dechesne, Francien; van der Poel, Ibo; Asveld, Lotte; Mehos, Donna C.

    2017-01-01

    Studies that approach the deployment of new technologies as social experiments have mostly focused on unintentional effects, notably safety. We argue for the inclusion of adversarial risks or security aspects that are the result of intentional, strategic behavior of actors, who aim at using the

  3. Suicide risk in long-term care facilities: a systematic review.

    Science.gov (United States)

    Mezuk, Briana; Rock, Andrew; Lohman, Matthew C; Choi, Moon

    2014-12-01

    Suicide risk is highest in later life; however, little is known about the risk of suicide among older adults in long-term care facilities (e.g., nursing homes and assisted living facilities). The goal of this paper is to review and synthesize the descriptive and analytic epidemiology of suicide in long-term care settings over the past 25 years. Four databases (PubMed, CINAHL Plus, Web of Knowledge, and EBSCOHost Academic Search Complete) were searched for empirical studies of suicide risk in nursing homes, assisted living, and other residential facilities from 1985 to 2013. Of the 4073 unique research articles identified, 37 were selected for inclusion in this review. Of the included reports, 21 were cross-sectional, 8 cohort, 3 qualitative, and 5 intervention studies. Most studies indicate that suicidal thoughts (active and passive) are common among residents (prevalence in the past month: 5-33%), although completed suicide is rare. Correlates of suicidal thoughts among long-term care residents include depression, social isolation, loneliness, and functional decline. Most studies examined only individual-level correlates of suicide, although there is suggestive evidence that organizational characteristics (e.g., bed size and staffing) may also be relevant. Existing research on suicide risk in long-term care facilities is limited but suggests that this is an important issue for clinicians and medical directors to be aware of and address. Research is needed on suicide risk in assisted living and other non-nursing home residential settings, as well as the potential role of organizational characteristics on emotional well-being for residents. Copyright © 2014 John Wiley & Sons, Ltd.

  4. Development of remote handling technology for nuclear fuel cycle facilities in Japan

    International Nuclear Information System (INIS)

    Maekawa, Hiromichi; Sakai, Akira; Miura, Noriaki; Kozaka, Tetsuo; Hamada, Takashi

    2015-01-01

    Remote handling technology has been systematically developed for nuclear fuel cycle facilities in Japan since 1970s, primarily in parallel with the development of reprocessing and HLLW (High Level Liquid Waste) vitrification process. In case of reprocessing and vitrification process to handle highly radioactive and hazardous materials, the most of components are installed in the radiation shielded hot cells and operators are not allowed to enter the work area in the cells for operation and maintenance. Therefore, a completely remote handling system is adopted for the cells to reduce radiation doses of operators and increase the availability of the facility. The hot cells are generally designed considering the scale of components (laboratory, demonstration, or full-scale), the function of the systems (chemical process, material handling, dismantling, decontamination, or chemical analysis), and the environmental conditions (radiation dose rate, airborne concentration, surface contamination, or fume/mist/dust). Throughout our domestic development work for remote handling technology, the concept of the large scale integrated cell has been adopted rather than a number of small scale separated cells, for the reasons to reduce the total installation space and the number of remote handling equipment required for the each cell as much as possible. In our domestic remote maintenance design, several new concepts have been developed, tested, and demonstrated in the Tokai Virtrification Facility (TVF) and the Rokkasho HLLW Vitrification and Storage Facility (K-facility). Layout in the hot cells, the performance of remote handling equipment, and the structure of the in-cell components are important factors for remote maintenance design. In case of TVF (hot tests started in 1995), piping and vessels are prefabricated in the rack modules and installed in two lines on both sides of the cell. These modules are designed to be remotely replaced in the whole rack. Two overhead cranes

  5. Experimental facility for development of high-temperature reactor technology: instrumentation needs and challenges

    Directory of Open Access Journals (Sweden)

    Sabharwall Piyush

    2015-01-01

    Full Text Available A high-temperature, multi-fluid, multi-loop test facility is under development at the Idaho National Laboratory for support of thermal hydraulic materials, and system integration research for high-temperature reactors. The experimental facility includes a high-temperature helium loop, a liquid salt loop, and a hot water/steam loop. The three loops will be thermally coupled through an intermediate heat exchanger (IHX and a secondary heat exchanger (SHX. Research topics to be addressed include the characterization and performance evaluation of candidate compact heat exchangers such as printed circuit heat exchangers (PCHEs at prototypical operating conditions. Each loop will also include an interchangeable high-temperature test section that can be customized to address specific research issues associated with each working fluid. This paper also discusses needs and challenges associated with advanced instrumentation for the multi-loop facility, which could be further applied to advanced high-temperature reactors. Based on its relevance to advanced reactor systems, the new facility has been named the Advanced Reactor Technology Integral System Test (ARTIST facility. A preliminary design configuration of the ARTIST facility will be presented with the required design and operating characteristics of the various components. The initial configuration will include a high-temperature (750 °C, high-pressure (7 MPa helium loop thermally integrated with a molten fluoride salt (KF-ZrF4 flow loop operating at low pressure (0.2 MPa, at a temperature of ∼450 °C. The salt loop will be thermally integrated with the steam/water loop operating at PWR conditions. Experiment design challenges include identifying suitable materials and components that will withstand the required loop operating conditions. The instrumentation needs to be highly accurate (negligible drift in measuring operational data for extended periods of times, as data collected will be

  6. Experimental facility for development of high-temperature reactor technology: instrumentation needs and challenges - 15066

    International Nuclear Information System (INIS)

    Sabharwall, P.; O'Brien, J.E.; Yoon, S.J.; Sun, X.

    2015-01-01

    A high-temperature, multi-fluid, multi-loop test facility is under development at the Idaho National Laboratory for support of thermal hydraulic, materials, and system integration research for high-temperature reactors. The experimental facility includes a high-temperature helium loop, a liquid salt loop, and a hot water/steam loop. The 3 loops will be thermally coupled through an intermediate heat exchanger (IHX) and a secondary heat exchanger (SHX). Research topics to be addressed include the characterization and performance evaluation of candidate compact heat exchangers such as printed circuits heat exchangers (PCHEs) at prototypical operating conditions. Each loop will also include an interchangeable high-temperature test section that can be customized to address specific research issues associated with each working fluid. This paper also discusses needs and challenges associated with advanced instrumentation for the multi-loop facility, which could be further applied to advanced high-temperature reactors. Based on its relevance to advanced reactor systems, the new facility has been named the Advanced Reactor Technology Integrated System Test (ARTIST) facility. A preliminary design configuration of the ARTIST facility will be presented with the required design and operating characteristics of the various components. The initial configuration will include a high-temperature (750 C. degrees), high-pressure (7 MPa) helium loop thermally integrated with a molten fluoride salt (KF-ZrF 4 ) flow loop operating at low pressure (0.2 MPa), at a temperature of ∼ 450 C. degrees. The salt loop will be thermally integrated with the steam/water loop operating at PWR conditions. Experiment design challenges include identifying suitable materials and components that will withstand the required loop operating conditions. The instrumentation needs to be highly accurate (negligible drift) in measuring operational data for extended periods of times, as data collected will be

  7. Identification of risk factors of computer information technologies in education

    Directory of Open Access Journals (Sweden)

    Hrebniak M.P.

    2014-03-01

    Full Text Available The basic direction of development of secondary school and vocational training is computer training of schoolchildren and students, including distance forms of education and widespread usage of world information systems. The purpose of the work is to determine risk factors for schoolchildren and students, when using modern information and computer technologies. Results of researches allowed to establish dynamics of formation of skills using computer information technologies in education and characteristics of mental ability among schoolchildren and students during training in high school. Common risk factors, while operating CIT, are: intensification and formalization of intellectual activity, adverse ergonomic parameters, unfavorable working posture, excess of hygiene standards by chemical and physical characteristics. The priority preventive directions in applying computer information technology in education are: improvement of optimal visual parameters of activity, rationalization of ergonomic parameters, minimizing of adverse effects of chemical and physical conditions, rationalization of work and rest activity.

  8. Risk management in methodologies of information technology and communications projects

    Directory of Open Access Journals (Sweden)

    Jonathan Carrillo

    2013-12-01

    Full Text Available (Received: 2013/10/02 - Accepted: 2013/12/13At present there are methodologies that have several alternatives and methods to manage projects of Information and Communication Technologies. However, these do not cover a solution for the technology events that can occur in the industry, government, education, among others. In the technology market there are several models to identify and analyze risks according to relevant aspects of their area of specialty e.g. projects, in software development, communications, information security and business alignment. For this reason, this research conducted an evaluation of risk management activities of the methodologies used mostly to know which of them includes more correspondence with basic elements of IT using a rating scale.

  9. Ethical perspectives on emerging assistive technologies: insights from focus groups with stakeholders in long-term care facilities.

    Science.gov (United States)

    Dorsten, Aimee-Marie; Sifford, K Susan; Bharucha, Ashok; Mecca, Laurel Person; Wactlar, Howard

    2009-03-01

    ASSISTIVE TECHNOLOGIES ARE RELATIVELY novel tools for research and daily care in long-term care (LTC) facilities that are faced with the burgeoning of the older adult population and dwindling staffing resources. The degree to which stakeholders in LTC facilities are receptive to the use of these technologies is poorly understood. Eighteen semi-structured focus groups and one interview were conducted with relevant groups of stakeholders at seven LTC facilities in southwestern Pennsylvania. Common themes identified across all focus groups centered on concerns for privacy, autonomy, cost, and safety associated with implementation of novel technologies. The relative importance of each theme varied by stakeholder group as well as the perceived severity of cognitive and/or physical disability. Our findings suggest that ethical issues are critical to acceptance of novel technologies by their end users, and that stakeholder groups are interdependent and require shared communication about the acceptance of these emerging technologies.

  10. A Laser Technology Test Facility for Laser Inertial Fusion Energy (LIFE)

    International Nuclear Information System (INIS)

    Bayramian, A.J.; Campbell, R.W.; Ebbers, C.A.; Freitas, B.L.; Latkowski, J.; Molander, W.A.; Sutton, S.B.; Telford, S.; Caird, J.A.

    2010-01-01

    A LIFE laser driver needs to be designed and operated which meets the rigorous requirements of the NIF laser system while operating at high average power, and operate for a lifetime of >30 years. Ignition on NIF will serve to demonstrate laser driver functionality, operation of the Mercury laser system at LLNL demonstrates the ability of a diode-pumped solid-state laser to run at high average power, but the operational lifetime >30 yrs remains to be proven. A Laser Technology test Facility (LTF) has been designed to specifically address this issue. The LTF is a 100-Hz diode-pumped solid-state laser system intended for accelerated testing of the diodes, gain media, optics, frequency converters and final optics, providing system statistics for billion shot class tests. These statistics will be utilized for material and technology development as well as economic and reliability models for LIFE laser drivers.

  11. Risk management considerations for seismic upgrading of an older facility for short-term residue stabilization

    International Nuclear Information System (INIS)

    Additon, S.L.; Peregoy, W.L.; Foppe, T.L.

    1999-01-01

    Building 707 and its addition, Building 707A, were selected, after the production mission of Rocky Flats was terminated a few years ago, to stabilize many of the plutonium residues remaining at the site by 2002. The facility had undergone substantial safety improvements to its safety systems and conduct of operations for resumption of plutonium operations in the early 1990s and appeared ideally suited for this new mission to support accelerated Site closure. During development of a new authorization basis, a seismic evaluation was performed. This evaluation addressed an unanalyzed expansion joint and suspect connection details for the precast concrete tilt-up construction and concluded that the seismic capacity of the facility is less than half of that determined by previous analysis. Further, potential seismic interaction was identified between a collapsing Building 707 and the seismically upgraded Building 707A, possibly causing the partial collapse of the latter. Both the operating contractor and the Department of Energy sought a sound technical basis for deciding how to proceed. This paper addresses the risks of the as-is facility and possible benefits of upgrades to support a decision on whether to upgrade the seismic capacity of Building 707, accept the risk of the as-is facility for its short remaining mission, or relocate critical stabilization missions. The paper also addresses the Department of Energy's policy on natural phenomena

  12. Suicide Risk in Nursing Homes and Assisted Living Facilities: 2003–2011

    Science.gov (United States)

    Lohman, Matthew; Leslie, Marc; Powell, Virginia

    2015-01-01

    Objectives. We investigated the epidemiology of suicide among adults aged 50 years and older in nursing homes and assisted living facilities and whether anticipating transitioning into long-term care (LTC) is a risk factor for suicide. Methods. Data come from the Virginia Violent Death Reporting System (2003–2011). We matched locations of suicides (n = 3453) against publicly available resource registries of nursing homes (n = 285) and assisted living facilities (n = 548). We examined individual and organizational correlates of suicide by logistic regression. We identified decedents anticipating entry into LTC through qualitative text analysis. Results. Incidence of suicide was 14.16 per 100 000 in nursing homes and 15.66 in the community. Better performance on Nursing Home Compare quality metrics was associated with higher odds of suicide in nursing homes (odds ratio [OR] = 1.95; 95% confidence interval [CI] = 1.21, 3.14). Larger facility size was associated with higher suicide risk in assisted living facilities (OR = 1.01; 95% CI = 1.00, 1.01). Text narratives identified 38 decedents anticipating transitioning into LTC and 16 whose loved one recently transitioned or resided in LTC. Conclusions. LTC may be an important point of engagement in suicide prevention. PMID:25973805

  13. Suicide Risk in Nursing Homes and Assisted Living Facilities: 2003-2011.

    Science.gov (United States)

    Mezuk, Briana; Lohman, Matthew; Leslie, Marc; Powell, Virginia

    2015-07-01

    We investigated the epidemiology of suicide among adults aged 50 years and older in nursing homes and assisted living facilities and whether anticipating transitioning into long-term care (LTC) is a risk factor for suicide. Data come from the Virginia Violent Death Reporting System (2003-2011). We matched locations of suicides (n = 3453) against publicly available resource registries of nursing homes (n = 285) and assisted living facilities (n = 548). We examined individual and organizational correlates of suicide by logistic regression. We identified decedents anticipating entry into LTC through qualitative text analysis. Incidence of suicide was 14.16 per 100 000 in nursing homes and 15.66 in the community. Better performance on Nursing Home Compare quality metrics was associated with higher odds of suicide in nursing homes (odds ratio [OR] = 1.95; 95% confidence interval [CI] = 1.21, 3.14). Larger facility size was associated with higher suicide risk in assisted living facilities (OR = 1.01; 95% CI = 1.00, 1.01). Text narratives identified 38 decedents anticipating transitioning into LTC and 16 whose loved one recently transitioned or resided in LTC. LTC may be an important point of engagement in suicide prevention.

  14. Current state of the construction of an integrated test facility for hydrogen risk

    Energy Technology Data Exchange (ETDEWEB)

    Na, Young Su; Hong, Seong-Ho; Hong, Seong-Wan [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    Experimental research on hydrogen as a combustible gas is important for an assessment of the integrity of a containment building under a severe accident. The Korea Atomic Energy Research Institute (KAERI) is preparing a large-scaled test facility, called SPARC (SPray-Aerosol-Recombiner-Combustion), to estimate the hydrogen behavior such as the distribution, combustion and mitigation. This paper introduces the experimental research activity on hydrogen risk, which was presented at International Congress on Advances in Nuclear Power Plants (ICAPP) this year. The KAERI is preparing a test facility, called SPARC (SPray-Aerosol-Recombiner-Combustion test facility), for an assessment of the hydrogen risk. In the SPARC, hydrogen behavior such as mixing with steam and air, distribution, and combustion in the containment atmosphere will be observed. The SPARC consists of a pressure vessel with a 9.5 m height and 3.4 m in diameter and the operating system to control the thermal hydraulic conditions up to 1.5 MPa at 453 K in a vessel. The temperature, pressure, and gas concentration at various locations will be measured to estimate the atmospheric behavior in a vessel. To install the SPARC, an experimental building, called LIFE (Laboratory for Innovative mitigation of threats from Fission products and Explosion), was constructed at the KAERI site. LIFE has an area of 480 m''2 and height of 18.6 m, and it was designed by considering the experimental safety and specification of a large-sized test facility.

  15. Environmental Audit at Santa Barbara Operations, Special Technologies Laboratory, Remote Sensing Laboratory, North Las Vegas Facilities

    International Nuclear Information System (INIS)

    1991-03-01

    This report documents the results of the Environmental Audit of selected facilities under the jurisdiction of the DOE Nevada Operations Office (NV) that are operated by EG and G Energy Measurements, Incorporated (EG and G/EM). The facilities included in this Audit are those of Santa Barbara Operation (SBO) at Goleta, California; the Special Technologies Laboratory (STL) at Santa Barbara, California; and Las Vegas Area Operations (LVAO) including the Remote Sensing Laboratory (RSL) at Nellis Air Force Base in Nevada, and the North Las Vegas Facilities (NLVF) at North Las Vegas, Nevada. The Environmental Audit was conducted by the US Department of Energy's (DOE) Office of Environmental Audit, commencing on January 28, 1991 and ending on February 15, 1991. The scope of the Audit was comprehensive, addressing environmental activities in the technical areas of air, surface water/drinking water, groundwater, waste management, toxic and chemical materials, quality assurance, radiation, inactive waste sites, and environmental management. Also assessed was compliance with applicable Federal, state, and local regulations and requirements; internal operating requirements; DOE Orders; and best management practices. 8 tabs

  16. Race, region and risk: An examination of minority proximity to noxious facilities

    Energy Technology Data Exchange (ETDEWEB)

    Nieves, A.L. [Wheaton Coll., IL (United States)]|[Argonne National Lab., IL (United States); Nieves, L.A. [Argonne National Lab., IL (United States)

    1996-04-01

    The past decade has given rise to terms like environmental racism, eco-racism, and environmental inequities to characterize a disproportional distribution of environmental disamenities among minority communities. Much of the literature supports the contention that racial and ethnic minorities and low-income groups bear a disproportionate burden of risk from hazardous activities and substances in the environment. This study expands the scope of prior studies by employing county-level data for the entire nation and including a broad range of facility types associated with environmental disamenities. In addition, it addresses the issue of the distribution of noxious facilities among white and non-white populations in an attempt to determine the relative exposure to risk among different racial and ethnic groups. In addition, the authors also explore the relative importance of nonurban versus urban residence.

  17. Risk-informing safety reviews for non-reactor nuclear facilities: an example application

    International Nuclear Information System (INIS)

    Mubayi, V.; Yue, M.; Bari, R.A.; Azarm, M.A.; Mukaddam, W.; Good, G.; Gonzalez, F.

    2013-01-01

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction can be useful to help to risk-inform a safety review process and assess compliance with regulatory requirements. (authors)

  18. Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

    International Nuclear Information System (INIS)

    Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

    2011-01-01

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

  19. Accident Management ampersand Risk-Based Compliance With 40 CFR 68 for Chemical Process Facilities

    International Nuclear Information System (INIS)

    O'Kula, K.R.; Taylor, R.P. Jr.; Ashbaugh, S.G.

    1995-01-01

    A risk-based logic model is suggested as an appropriate basis for better predicting accident progression and ensuing source terms to the environment from process upset conditions in complex chemical process facilities. Under emergency conditions, decision-makers may use the Accident Progression Event Tree approach to identify the best countermeasure for minimizing deleterious consequences to receptor groups before the atmospheric release has initiated. It is concluded that the chemical process industry may use this methodology as a supplemental information provider to better comply with the Environmental Protection Agency's proposed 40 CFR 68 Risk Management Program rule. An illustration using a benzene-nitric acid potential interaction demonstrates the value of the logic process. The identification of worst-case releases and planning for emergency response are improved through these methods, at minimum. It also provides a systematic basis for prioritizing facility modifications to correct vulnerabilities

  20. Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

    2011-03-13

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

  1. Risk perceptions and technological hazards: a contextual view

    International Nuclear Information System (INIS)

    Walker, G.; Simmons, P.; Irwin, A.; Wynne, B.

    1998-01-01

    Full text of publication follows: the study of public perceptions of risk has given rise to a number of different (and sometimes conflicting) perspectives. Although the differences between these approaches are not trivial, recent reviews have suggested that there may be some points of convergence. In particular, recent work within the different traditions has emphasised the importance of factors such as trust and power for understanding public perceptions of risk. These factors take us beyond the characteristics of the risks themselves, which were the focus of influential work in the psychometric tradition and into a consideration of the social and cultural context within which potentially hazardous technologies are encountered and evaluated. In this paper we examine the way in which the lay public understand and respond to a particular class of technological risks - those associated with site-based major accident hazards. On the basis of empirical research, we argue that an appreciation of the different contexts within which citizens encounter such risks is crucial to understanding the dynamics of public concerns. We illustrate our argument by examining the different ways in which contextual factors influence perceptions. The discussion draws upon a recently completed study of public perceptions of the risks at seven major hazard sites in the UK, which was funded the by UK Health and Safety Executive. (authors)

  2. Information technology systems in public sector health facilities in developing countries: the case of South Africa

    Directory of Open Access Journals (Sweden)

    Cline Gregory B

    2013-01-01

    Full Text Available Abstract Background The public healthcare sector in developing countries faces many challenges including weak healthcare systems and under-resourced facilities that deliver poor outcomes relative to total healthcare expenditure. Global references demonstrate that information technology has the ability to assist in this regard through the automation of processes, thus reducing the inefficiencies of manually driven processes and lowering transaction costs. This study examines the impact of hospital information systems implementation on service delivery, user adoption and organisational culture within two hospital settings in South Africa. Methods Ninety-four interviews with doctors, nurses and hospital administrators were conducted in two public sector tertiary healthcare facilities (in two provinces to record end-user perceptions. Structured questionnaires were used to conduct the interviews with both qualitative and quantitative information. Results Noteworthy differences were observed among the three sample groups of doctors, nurses and administrators as well as between our two hospital groups. The impact of automation in terms of cost and strategic value in public sector hospitals is shown to have yielded positive outcomes with regard to patient experience, hospital staff workflow enhancements, and overall morale in the workplace. Conclusion The research provides insight into the reasons for investing in system automation, the associated outcomes, and organisational factors that impact the successful adoption of IT systems. In addition, it finds that sustainable success in these initiatives is as much a function of the technology as it is of the change management function that must accompany the system implementation.

  3. Information and Communication Technologies and Supply Chain in Facilities Management in Denmark

    DEFF Research Database (Denmark)

    Scupola, Ada; Anker Jensen, Per

    This report presents the results of a study of factors impacting Information and Communication Technology (ICT) adoption in the supply chain of Facilities Management (FM) in Denmark. The research questions addressed in this study are: What are the key factors that influence adoption and assimilat......This report presents the results of a study of factors impacting Information and Communication Technology (ICT) adoption in the supply chain of Facilities Management (FM) in Denmark. The research questions addressed in this study are: What are the key factors that influence adoption...... important organizational factors are better FM management decisions, better long term and short term planning and forecasting of FM resources, better overview and control over the budget and the activities that need to be done as well as bbetter service provided to the customers.  Among the organizational...... there are improve and control relationships with FM service provider, opportunity to offer single point of contact also in complicated bundled services, government regulation, and critical mass of users. Among the external barriers there are lack of collaboration among software providers, clients and users in order...

  4. Application of Bayesian network methodology to the probabilistic risk assessment of nuclear waste disposal facility

    International Nuclear Information System (INIS)

    Lee, Chang Ju

    2006-02-01

    The scenario in a risk analysis can be defined as the propagating feature of specific initiating event which can go to a wide range of undesirable consequences. If one takes various scenarios into consideration, the risk analysis becomes more complex than do without them. A lot of risk analyses have been performed to actually estimate a risk profile under both uncertain future states of hazard sources and undesirable scenarios. Unfortunately, in case of considering some stochastic passive systems such as a radioactive waste disposal facility, since the behaviour of future scenarios is hardly predicted without special reasoning process, we cannot estimate their risk only with a traditional risk analysis methodology. Moreover, it is believed that the sources of uncertainty at future states can be reduced pertinently by setting up dependency relationships interrelating geological, hydrological, and ecological aspects of the site with all the scenarios. It is then required current methodology of uncertainty analysis of the waste disposal facility be revisited under this belief. In order to consider the effects predicting from an evolution of environmental conditions of waste disposal facilities, this study proposes a quantitative assessment framework integrating the inference process of Bayesian network to the traditional probabilistic risk analysis. In this study an approximate probabilistic inference program for the specific Bayesian network developed and verified using a bounded-variance likelihood weighting algorithm. Ultimately, specific models, including a Monte-Carlo model for uncertainty propagation of relevant parameters, were developed with a comparison of variable-specific effects due to the occurrence of diverse altered evolution scenarios (AESs). After providing supporting information to get a variety of quantitative expectations about the dependency relationship between domain variables and AESs, this study could connect the results of probabilistic

  5. Status of NIF mirror technologies for completion of the NIF facility

    International Nuclear Information System (INIS)

    Stolz, C.J.

    2008-01-01

    The 1600 mirrors required for the National Ignition Facility (NIF) are now coated with the last optics currently being installed. The combined surface area of the NIF mirrors is almost 450 square meters, roughly 3.4 times greater than the surface area of the two Keck primary mirrors. Additionally, the power handling specification of NIF mirrors is 19 orders of magnitude greater than that of the Keck mirrors. The NIF laser will be at least 40x greater energy than the previous LLNL fusion laser called NOVA. To manufacture these mirrors, a number of new technologies (electrolytic in-situ dressing, ion figuring, source stabilization) were used that were not available for previous fusion laser optics. Post deposition technologies designed to increase laser resistance (off-line laser conditioning, solarization, air knives) have also been utilized. This paper summarizes the differences in technologies used to manufacture NIF mirrors from those used for previous fusion lasers and examines potential future technologies that would enable higher fluence operations and extend lifetimes

  6. The impact of health information technology adoption by outpatient facilities on pregnancy outcomes.

    Science.gov (United States)

    Deily, Mary E; Hu, Tianyan; Terrizzi, Sabrina; Chou, Shin-Yi; Meyerhoefer, Chad D

    2013-02-01

    Examine whether health information technology (HIT) at nonhospital facilities (NHFs) improves health outcomes and decreases resource use at hospitals within the same heath care network, and whether the impact of HIT varies as providers gain experience using the technologies. Administrative claims data on 491,832 births in Pennsylvania during 1998-2004 from the Pennsylvania Health Care Cost Containment Council and HIT applications data from the Dorenfest Institute. Fixed-effects regression analysis of the impact of HIT at NHFs on adverse birth outcomes and resource use. Greater use of clinical HIT applications by NHFs is associated with reduced incidence of obstetric trauma and preventable complications, as well as longer lengths of stay. In addition, the beneficial effects of HIT increase the longer that technologies have been in use. However, we find no consistent evidence on whether or how nonclinical HIT in NHFs affects either resource use or health outcomes. Clinical HIT applications at NHFs may reduce the likelihood of adverse birth outcomes, particularly after physicians and staff gain experience using the technologies. © Health Research and Educational Trust.

  7. THE DEVELOPMENT OF COAL-BASED TECHNOLOGIES FOR DEPARTMENT OF DEFENSE FACILITIES

    Energy Technology Data Exchange (ETDEWEB)

    Bruce G. Miller; Sharon Falcone Miller; Sarma V. Pisupati; Chunshan Song; Ronald S. Wasco; Ronald T. Wincek; Xiaochun Xu; Alan W. Scaroni; Richard Hogg; Subhash Chander; M. Thaddeus Ityokumbul; Mark S. Klima; Peter T. Luckie; Adam Rose; Richard L. Gordon; Jeffrey Lazo; A. Michael Schaal

    2004-01-30

    The third phase of a three-phase project investigating the development of coal-based technologies for US Department of Defense (DOD) facilities was completed. The objectives of the project were to: decrease DOD's dependence on foreign oil and increase its use of coal; promote public and private sector deployment of technologies for utilizing coal-based fuels in oil-designed combustion equipment; and provide a continuing environment for research and development of coal-based fuel technologies for small-scale applications at a time when market conditions in the US are not favorable for the introduction of coal-fired equipment in the commercial and industrial capacity ranges. The Phase III activities were focused on evaluating deeply-cleaned coals as fuels for industrial boilers and investigating emissions control strategies for providing ultra-low emissions when firing coal-based fuels. This was addressed by performing coal beneficiation and preparation studies, and bench- to demonstration-scale emissions reduction studies. In addition, economic studies were conducted focused on determining cost and market penetration, selection of incentives, and regional economic impacts of coal-based technologies.

  8. Risk assessment associated to possible concrete degradation of a near surface disposal facility

    Directory of Open Access Journals (Sweden)

    Wacquier W.

    2013-07-01

    Full Text Available This article outlines a risk analysis of possible concrete degradation performed in the framework of the preparation of the Safety Report of ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste and Enriched Fissile Materials, for the construction and operation of a near surface disposal facility of category A waste – short-lived low and intermediate level waste – in Dessel. The main degradation mechanism considered is the carbonation of different concrete components over different periods (from the building phase up to 2000 years, which induces corrosion of the rebars. A dedicated methodology mixing risk analysis and numerical modeling of concrete carbonation has been developed to assess the critical risks of the disposal facility at different periods. According to the results obtained, risk mapping was used to assess the impact of carbonation of concrete on the different components at the different stages. The most important risk is related to an extreme situation with complete removal of the earth cover and side embankment.

  9. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Ansley, Shannon Leigh

    2002-02-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.

  10. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility; TOPICAL

    International Nuclear Information System (INIS)

    Ansley, Shannon L.

    2002-01-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist

  11. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility

    International Nuclear Information System (INIS)

    Ansley, Shannon L.

    2002-01-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist

  12. Use of highly pressurized liquid nitrogen technology for concrete scabbling application at SICN nuclear facility - 59282

    International Nuclear Information System (INIS)

    Moggia, Fabrice; Vaudey, Claire-Emilie; Damerval, Frederique; Varet, Thierry; Toulemonde, Valerie; Richard, Frederic; Anderson, Gary

    2012-01-01

    The decommissioning process is a quite long and complicated stage who may take few years or decades to be achieved. Generally, this process involves the implementation of a large number of technologies dedicated to cutting and decontamination operations. Based on this finding, the Clean- Up Business Unit of AREVA with Air Liquide decided to start the development of a new technology based on the use of liquid nitrogen (-140 deg. C / 3500 bar). The NitroJet R process is a quite interesting and promising technology. It can be used, as we described in this document, for concrete scabbling operations but also for decontamination and cutting applications. The Clean-Up Business Unit, with its partner Air Liquide, realized a complete study of this technology including several tests and optimizations to be able to handle it in a nuclear environment. Thus, we did: - increase of the reliability of the machine, - nuclearization of the system (including the development of efficient shroud system and efficient HP pipes insulation); - development of a dedicated bearer for automatic configuration; - optimization of parameters for D and D applications. As we already mentioned, NitroJet R technology showed promising perspectives as: - economic: increase of rate processing, decrease in site monitoring costs, - environmental: use of an inert gas, no secondary waste generation, non use of chemical, dry process, - social: less strenuous work, decrease of operator dosimetry compatible with ALARA principle The future for the NitroJet R technology will be its implementation in a real high level activity environment. This process will be used in spring 2012 in AREVA nuclear reprocessing facility of La Hague (France) to accomplish concrete scabbling applications. This test will be the last of a long development period before industrial exploitation. (authors)

  13. Pilot study risk assessment for selected problems at three US Department of Energy Facilities

    International Nuclear Information System (INIS)

    Hamilton, L.D.; Holtzman, S.; Meinhold, A.F.; Morris, S.C.; Pardi, R.; Rowe, M.D.; Sun, C.; Anspaugh, L.R.; Bogen, K.T.; Daniels, J.I.

    1994-01-01

    Objective and realistic human health risk assessments were performed for environmental problems at the Savannah River Site (SRS), the Fernald Environmental Management Project (FEMP), and the Nevada Test Site (NTS). At the SRS, cancer mortality risks were analyzed for projected public exposure to 3 H and 137 Cs released into the Savannah River. For annual human exposures to SRS tritium in Savannah River water, calculated incremental individual lifetime risks in two human receptor populations were small (8x10 -7 ; upper 95 percentile point of the distribution). The 95th percentile point of the distribution for incremental individual lifetime risks from one year's exposure to 137 Cs is less than 10 -8 . No deaths are expected in either populations as a result of exposures to tritium or cesium released to the Savannah River. Routine releases of radon and radon progeny from the K-65 silos at FEMP resulted in individual lifetime risks greater than 1x10 -4 only for onsite workers and fenceline residents. Assessment of risks from exposure to uranium in ground water released by the FEMP predicted no toxic effects for human receptors. All estimated cancer risks were small. The largest predicted individual lifetime risk was for a well close to the facility. For various above-ground shot sites at the NTS, highest predicted lifetime cancer risks are for a resident farmer. At 50,000 and 100,000 y in the future, the predicted cancer risks are all below 10 -6 . In the assessment of exposure to radionuclides in ground water at the NTS, for an individual onsite near the site boundary, the geometric mean of the maximum potential excess lifetime risk of cancer mortality for an individual is 7x10 -3 . For an individual using water offsite, the geometric mean of the maximum potential excess lifetime risk of cancer mortality is 7x10 -7 . 40 refs., 6 figs., 2 tabs

  14. Technology, risk and participation: The attitude of society towards insecurity

    International Nuclear Information System (INIS)

    Wynne, B.

    1983-01-01

    The way society deals with risks in connection with society's judgement and decision on technological developments is discussed. If technology is a social phenomenon one must attribute more importance to unknown changes of social values resulting from these decisions and to unforeseen physical effects. One should therefore shift from fact analysis as a basis of decisions to a critical analysis of the creditworthyness, responsibility and degree to which the views of the decision-making institutions and elites are understood by society. (DG) [de

  15. Additional risk of end-of-the-pipe geoengineering technologies

    Science.gov (United States)

    Bohle, Martin

    2014-05-01

    qualitatively from the known successes. They do not tackle the initial cause, namely the carbon-dioxide inputs that are too high. This is their additional specific risk. 'The acceptability of geoengineering will be determined as much by social, legal and political issues as by scientific and technical factors', conclude Adam Corner and Nick Pidgeon (2010) when reviewing social and ethical implications of geoengineering the climate. It is to debate in that context that most geoengineering technologies are 'end of the pipe technologies', what involves an additional specific risk. Should these technologies be part of the toolbox to tackle anthropogenic climate change? Adam Corner and Nick Pidgeon 2010, Geoengineering the climate: The social and ethical implications, Environment Vol. 52.

  16. Remote mixed oxide fabrication facility development. Volume 2. State-of-the-art review of remote maintenance system technology

    International Nuclear Information System (INIS)

    Horgos, R.M.; Masch, M.L.

    1979-06-01

    This report provides a state-of-the-art review of remote systems technology, which includes manipulators, process connectors, vision systems and specialized process systems. A proposed mixed oxide fuel fabrication facility was reviewed and evaluated for identification of major remote maintenance and repair tasks. The technological areas were evaluated on the basis of their suitability or applicability for remote maintenance and repair of a proposed fully remote operating mixed oxide fuel fabrication facility. A technological base exists from which the design criteria for a reliable, remote operating facility can be established. Commercially available systems and components, along with those remote technologies now in development, will require modifications to adapt them to specific plant designs and requirements

  17. Use of precautionary principle in risk assessment of radioactive and nuclear facilities: benefits, costs and difficulties of implementing

    International Nuclear Information System (INIS)

    Reis, Helio G. dos; Jordao, Elizabete; Vasconcelos, Vanderley de

    2007-01-01

    The Precautionary Principle is a consequence of the understanding of both the limits of the science to predict risks, and the duty of government to protect the public and environment. An international declaration on the Principle, signed by most of world's nations, was made in 1992, during the United Nation Conference on Environment and Development. The key element of the origin and application of the Principle is the matter of acting in face of uncertainties about risks. The use of nuclear energy and ionizing radiation often involves complex facilities that pose special risks to public and environment. In order to comply with legal requirements during licensing process a risk assessment of such facilities shall be conducted. Risk assessment is often used for identifying and analyzing risks from project and complex systems. It is useful for facilitating risk management activities through the identification of dominant contributors to risk so that resources can be effectively allocated. However, risk assessment alone does not provide all of the information needed to determine an appropriate precaution level and the actions to be taken. Limitations of risk assessment are related to difficulties to solve problems, inclusion of public priorities and limited consideration of uncertainties. This work intends to discuss the current application of Precautionary Principle in risk assessment of radioactive and nuclear facilities, and propose an approach to consider it in Quantitative Risk Assessment. They are also analyzed where the Principle has been used, formally or implicitly, inside safety and risk assessment of such facilities. (author)

  18. Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory's hazardous waste management facility

    International Nuclear Information System (INIS)

    Dionne, B.J.; Morris, S. III; Baum, J.W.

    1998-03-01

    The Department of Energy's (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory's Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an open-quotes As Low as Reasonably Achievableclose quotes (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique

  19. A State-of-the-Art Report on Technologies of a Safety Assessment and a Radioactivity Exposure Assessment for the Decommissioning Process of Nuclear Facilities

    International Nuclear Information System (INIS)

    Jeong, Kwan Seong; Kang, Young Ae; Lee, Dong Gyu; Lee, Kune Woo; Jung, Chong Hun

    2007-09-01

    This report is to provide the reference contents of research and development for technologies of radioactivity exposure and safety assessment for development of the decommissioning technology for nuclear facilities. This report consists of as follows: - Analyzing and discussing on state-of-the-art technologies of a radioactivity exposure assessment of a decommissioning for nuclear facilities - Analyzing and discussing on state-of-the-art technologies of a safety assessment of a decommissioning for nuclear facilities

  20. A State-of-the-Art Report on Technologies of a Safety Assessment and a Radioactivity Exposure Assessment for the Decommissioning Process of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwan Seong; Kang, Young Ae; Lee, Dong Gyu; Lee, Kune Woo; Jung, Chong Hun

    2007-09-15

    This report is to provide the reference contents of research and development for technologies of radioactivity exposure and safety assessment for development of the decommissioning technology for nuclear facilities. This report consists of as follows: - Analyzing and discussing on state-of-the-art technologies of a radioactivity exposure assessment of a decommissioning for nuclear facilities - Analyzing and discussing on state-of-the-art technologies of a safety assessment of a decommissioning for nuclear facilities.

  1. Guidelines for Risk-Based Changeover of Biopharma Multi-Product Facilities.

    Science.gov (United States)

    Lynch, Rob; Barabani, David; Bellorado, Kathy; Canisius, Peter; Heathcote, Doug; Johnson, Alan; Wyman, Ned; Parry, Derek Willison

    2018-01-01

    In multi-product biopharma facilities, the protection from product contamination due to the manufacture of multiple products simultaneously is paramount to assure product quality. To that end, the use of traditional changeover methods (elastomer change-out, full sampling, etc.) have been widely used within the industry and have been accepted by regulatory agencies. However, with the endorsement of Quality Risk Management (1), the use of risk-based approaches may be applied to assess and continuously improve established changeover processes. All processes, including changeover, can be improved with investment (money/resources), parallel activities, equipment design improvements, and standardization. However, processes can also be improved by eliminating waste. For product changeover, waste is any activity not needed for the new process or that does not provide added assurance of the quality of the subsequent product. The application of a risk-based approach to changeover aligns with the principles of Quality Risk Management. Through the use of risk assessments, the appropriate changeover controls can be identified and controlled to assure product quality is maintained. Likewise, the use of risk assessments and risk-based approaches may be used to improve operational efficiency, reduce waste, and permit concurrent manufacturing of products. © PDA, Inc. 2018.

  2. Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory

    International Nuclear Information System (INIS)

    Lucas, D.E.; Ikenberry, T.A.

    1994-03-01

    Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91 (DOE 1991). The DOE nuclear safety policy states that the general public be protected-such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL. A safety analyst uses the frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy

  3. Spanish Minister of Science and Technology visits the LHC magnet test facility

    CERN Multimedia

    Patrice Loïez

    2002-01-01

    H.E. Mr Josep Piqué i Camps, Minister of Science and Technology, Spain, toured the test facility for LHC magnets in building SM18 during his visit to CERN in November. In this series of photos Felix Rodriguez Mateo explains the operation of the test facilty to the ministerial party. Photo 01: (left to right) Felix Rodriguez Mateo; the Minister; Francisco Giménez-Reyna, Spanish delegate to the CERN Finance Committee; M. Aguilar Benitez, Spanish delegate to the CERN Council; G. Babé and G. Léon. Photo 02: (left to right) Felix Rodriguez Mateos; César Dopazo, Director-General of CIEMAT (Spanish Research Centre for Energy, Environment and Technology); the Minister; G. Babé; M. Aguilar Benitez; and G. Léon. Photo 03: Francisco Giménez-Reyna; Felix Rodriguez Mateos; César Dopazo; the Minister; Juan Antonio Rubio, leader of the Education and Technology Transfer division at CERN; G. Babé behind M. Aguilar Benitez. Photo 04: Francisco Giménez-Reyna, partially hidden behind Felix Rodriguez Mateos; César Dop...

  4. Spanish Minister of Science and Technology visits the LHC magnet test facility

    CERN Multimedia

    Patrice Loïez

    2002-01-01

    H.E. Mr Josep Piqué i Camps, Minister for Science and Technology, Spain, toured the test facility for LHC magnets in building SM18 during his visit to CERN in November. Photos 01, 02: (left to right) M. Cerrada, CERN; Francisco Giménez-Reyna, Spanish delegate to the CERN Finance Committee; G. Léon; Juan Antonio Rubio, leader of the Education and Technology Transfer division at CERN; M. Aguilar-Benitez, Spanish delegate to CERN Council; (behind) H.E. Mr Joaquin Pérez-Villanueva y Tovar, Ambassador and Permanent Representative of Spain to the United Nations in Geneva; the Minister; Manuel Delfino, leader of the Information Technology division at CERN; bodyguard; Matteo Cavalli-Sforza, ATLAS national contact physicist for Spain; Felix Rodriguez Mateos, CERN; G. Babé. Visible in the left background is one of the test benches where magnets are prepared for installation in String 2: the full-scale model of an LHC cell of the regular part of the arc. The extremity of String 2, which measures 120 m and runs the ...

  5. Integrated risk management in South Africa: between technological features and organisational reality

    CSIR Research Space (South Africa)

    Simonis, I

    2009-01-01

    Full Text Available cost interoperable information and communication technology (ICT) solutions to effectively mitigate disaster risk by addressing all phases of disaster risk management from risk assessment to recovery; paving the way to improved risk governance...

  6. Dose and risk assessment of norm Contaminated waste released from trench disposal facility

    International Nuclear Information System (INIS)

    Abdel Geleel, M.; Ramadan, A.B.; Tawfik, A.A.

    2005-01-01

    Oil and gas extraction and processing operations accumulate naturally occurring radioactive material (NORM) at concentrations above normal in by-product waste streams. The petroleum industry adopted methods for managing of NORM that are more restrictive than past practices and are likely to provide greater isolation of the radioactivity. Trench was used as a disposal facility for NORM contaminated wastes at one site of the petroleum industry in Egypt. The aim of this work is to calculate the risk and dose assessment received from trench disposal facility directly and after closure (1000 year). RESRAD computer code was used. The results indicated that the total effective dose (TED) received after direct closure of trench disposal facility was 7.7E-4 mSv/y while after 1000 years, it will he 3.4E-4. The health cancer risk after direct closure was 3.3E-8 while after 1000 years post closure it was 6E-8. Results of this assessment will help examine policy issues concerning different options and regulation of NORM contaminated waste generated by petroleum industry

  7. Use of risk assessment methods for security design and analysis of nuclear and radioactive facilities

    International Nuclear Information System (INIS)

    Vasconcelos, Vanderley de; Andrade, Marcos C.; Jordao, Elizabete

    2011-01-01

    The objective of this work is to evaluate the applicability of risk assessment methods for analyzing the physical protection of nuclear and radioactive facilities. One of the important processes for physical protection in nuclear and radioactive facilities is the identifying of areas containing nuclear materials, structures, systems or components to be protected from sabotage, which could directly or indirectly lead to unacceptable radiological consequences. A survey of the international guidelines and recommendations about vital area identification, design basis threat (DBT), and the security of nuclear and radioactive facilities was carried out. The traditional methods used for quantitative risk assessment, like FMEA (Failure Mode and Effect Analysis), Event and Decision Trees, Fault and Success Trees, Vulnerability Assessment, Monte Carlo Simulation, Probabilistic Safety Assessment, Scenario Analysis, and Game Theory, among others, are highlighted. The applicability of such techniques to security issues, their pros and cons, the general resources needed to implement them, as data or support software, are analyzed. Finally, an approach to security design and analysis, beginning with a qualitative and preliminary examination to determine the range of possible scenarios, outcomes, and the systems to be included in the analyses, and proceeding to a progressively use of more quantitative techniques is presented. (author)

  8. Risks perception and the public acceptance of nuclear technology

    International Nuclear Information System (INIS)

    Ferreira, Walter Mendes; Gavazza, Sergio; Estrada, Julio J.S.

    2000-01-01

    This work establishes a methodology to evaluate the public acceptance of nuclear technology taking into consideration several risk concepts. Basic concepts of the nuclear science were transmitted, in form of lectures and courses, to the 13,439 Goiania residents, after the closing of the decontamination works, caused by the violation of the source of 137 Cs, of a teletherapy machine, in 1987. The results of the indicators shown that public's individuals perceive radiation risks and develop behaviors according to a constructive outline. The public does not know technical terms, being quite influenced by media, from where gets information of interest. The public orders the risks, relating them to accidents according to subjective criteria and models them as unknown, new and not observed at short period, establishing destruction, environmental catastrophe and diseases images. (author)

  9. Role of information and communication technology in promoting oral health at residential aged care facilities.

    Science.gov (United States)

    Adebayo, Bola; Durey, Angela; Slack-Smith, Linda M

    2017-07-01

    Information and communication technology (ICT) can provide knowledge and clinical support to those working in residential aged care facilities (RACFs). This paper aims to: (1) review literature on ICT targeted at residents, staff and external providers in RACFs including general practitioners, dental and allied health professionals on improving residents' oral health; (2) identify barriers and enablers to using ICT in promoting oral health at RACFs; and (3) investigate evidence of effectiveness of these approaches in promoting oral health. Findings from this narrative literature review indicate that ICT is not widely used in RACFs, with barriers to usage identified as limited training for staff, difficulties accessing the Internet, limited computer literacy particularly in older staff, cost and competing work demands. Residents also faced barriers including impaired cognitive and psychosocial functioning, limited computer literacy and Internet use. Findings suggest that more education and training in ICT to upskill staff and residents is needed to effectively promote oral health through this medium.

  10. Experimental investigations of the accelerator-driven transmutation technologies at the subcritical facility ''Yalina''

    International Nuclear Information System (INIS)

    Chigrinov, S.E.; Kiyavitskaya, H.I.; Serafimovich, I.G.; Rakhno, I.L.; Rutkovskaia, Ch.K.; Fokov, Y.; Khilmanovich, A.M.; Marstinkevich, B.A.; Bournos, V.V.; Korneev, S.V.; Mazanik, S.E.; Kulikovskaya, A.V.; Korbut, T.P.; Voropaj, N.K.; Zhouk, I.V.; Kievec, M.K.

    2002-01-01

    The investigations on accelerator-driven transmutation technologies (ADTT) focus on the reduction of the amount of long-lived wastes and the physics of a subcritical system driven with an external neutron source. This paper presents the experimental facility 'Yalina' which was designed and created at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus in the framework of the ISTC project no. B-070 to study the peculiarities of ADTT in thermal spectrum. A detailed description of the assembly, neutron generator and a preliminary analysis of some calculated and experimental data (multiplication factor, neutron flux density distribution in the assembly, transmutation rates of some long-lived fission products and minor actinides) are presented. (authors)

  11. A Distributed Simulation Facility to Support Human Factors Research in Advanced Air Transportation Technology

    Science.gov (United States)

    Amonlirdviman, Keith; Farley, Todd C.; Hansman, R. John, Jr.; Ladik, John F.; Sherer, Dana Z.

    1998-01-01

    A distributed real-time simulation of the civil air traffic environment developed to support human factors research in advanced air transportation technology is presented. The distributed environment is based on a custom simulation architecture designed for simplicity and flexibility in human experiments. Standard Internet protocols are used to create the distributed environment, linking all advanced cockpit simulator, all Air Traffic Control simulator, and a pseudo-aircraft control and simulation management station. The pseudo-aircraft control station also functions as a scenario design tool for coordinating human factors experiments. This station incorporates a pseudo-pilot interface designed to reduce workload for human operators piloting multiple aircraft simultaneously in real time. The application of this distributed simulation facility to support a study of the effect of shared information (via air-ground datalink) on pilot/controller shared situation awareness and re-route negotiation is also presented.

  12. National Ignition Facility quality assurance plan for laser materials and optical technology

    Energy Technology Data Exchange (ETDEWEB)

    Wolfe, C.R.

    1996-05-01

    Quality achievement is the responsibility of the line organizations of the National Ignition Facility (NIF) Project. This subtier Quality Assurance Plan (QAP) applies to activities of the Laser Materials & Optical Technology (LM&OT) organization and its subcontractors. It responds to the NIF Quality Assurance Program Plan (QAPP, L-15958-2, NIF-95-499) and Department of Energy (DOE) Order 5700.6C. This Plan is organized according to 10 Quality Assurance (QA) criteria and subelements of a management system as outlined in the NIF QAPP. This Plan describes how those QA requirements are met. This Plan is authorized by the Associate Project Leader for the LM&OT organization, who has assigned responsibility to the Optics QA engineer to maintain this plan, with the assistance of the NIF QA organization. This Plan governs quality-affecting activities associated with: design; procurement; fabrication; testing and acceptance; handling and storage; and installation of NIF Project optical components into mounts and subassemblies.

  13. Identifying concepts for studying implementation of information technology in facilities management

    DEFF Research Database (Denmark)

    Ebbesen, Poul; Bonke, Sten

    2014-01-01

    . Background: Experiences from the FM sector indicate that IT systems meant to support FM operations and workflows often do not generate the expected added value neither to the FM department itself nor to the basic organization supported by the FM department. Approach (Theory/Methodology): Based on findings......Purpose: To contribute to identifying a conceptual framework for describing and understanding the processes involved when implementing and using Information Technology (IT) in Facilities Management (FM). This paper discusses how basic concepts from different theories can be applied in parallel when...... from exciting research on IT implementation a range of more generic theoretical concepts applicable to the typical setting or situation of IT implementation in FM has been found. These theoretical concepts all clarify and describe different aspects of the implementation process and they may all...

  14. Development of corrective measures technology for shallow land burial facilities at arid sites

    International Nuclear Information System (INIS)

    Nyhan, J.W.; Abeele, W.V.; Perkins, B.A.; Lane, L.J.

    1984-01-01

    The field research program involving corrective measure technologies for arid shallow land burial (SLB) sites is described. Soil erosion and infiltration of water into a simulated trench cap with various surface treatments was measured and compared with similar data from agricultural systems across the United States. Field testing of biointrustion barriers at closed-out waste disposal sites at Los Alamos and in the experimental clusters are reported. The final results of an experiment designed to measure the extent of contaminant transport to the surface of a SLB facility, and the influence of plants on this relationship, are presented. An experiment designed to determine the effects of subsidence on the performance of a cobble-gravel biobarrier system is described and current field data are presented. 11 references, 11 figures, 5 tables

  15. Beam Position Monitor and Energy Analysis at the Fermilab Accelerator Science and Technology Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, David Juarez [Univ. of Guanajuato (Mexico)

    2015-08-01

    Fermilab Accelerator Science and Technology Facility has produced its first beam with an energy of 20 MeV. This energy is obtained by the acceleration at the Electron Gun and the Capture Cavity 2 (CC2). When fully completed, the accelerator will consist of a photoinjector, one International Liner Collider (ILC)-type cryomodule, multiple accelerator R&D beamlines, and a downstream beamline to inject 300 MeV electrons into the Integrable Optics Test Accelerator (IOTA). We calculated the total energy of the beam and the corresponding energy to the Electron Gun and CC2. Subsequently, a Beam Position Monitors (BPM) error analysis was done, to calculate the device actual resolution.

  16. Environmental assessment report: Nuclear Test Technology Complex. [Construction and operation of proposed facility

    Energy Technology Data Exchange (ETDEWEB)

    Tonnessen, K.; Tewes, H.A.

    1982-08-01

    The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report.

  17. Distribution and behavior of tritium in the Coolant-Salt Technology Facility

    International Nuclear Information System (INIS)

    Mays, G.T.; Smith, A.N.; Engel, J.R.

    1977-04-01

    A 1000-MW(e) Molten-Salt Breeder Reactor (MSBR) is expected to produce 2420 Ci/day of tritium. As much as 60 percent of the tritium produced may be transported to the reactor steam system (assuming no retention by the secondary coolant salt), where it would be released to the environment. Such a release rate would be unacceptable. Experiments were conducted in an engineering-scale facility--the Coolant-Salt Technology Facility (CSTF)--to examine the potential of sodium fluoroborate, the proposed coolant salt for an MSBR, for sequestering tritium. The salt was believed to contain chemical species capable of trapping tritium. A series of 5 experiments--3 transient and 2 steady-state experiments--was conducted from July of 1975 through June of 1976 where tritium was added to the CSTF. The CSTF circulated sodium fluoroborate at temperatures and pressures typical of MSBR operating conditions. Results from the experiments indicated that over 90 percent of tritium added at steady-state conditions was trapped by sodium fluoroborate and appeared in the off-gas system in a chemically combined (water-soluble) form and that a total of approximately 98 percent of the tritium added at steady-state conditions was removed through the off-gas system overall

  18. Advances in technology for the construction of deep-underground facilities

    Energy Technology Data Exchange (ETDEWEB)

    1987-12-31

    The workshop was organized in order to address technological issues important to decisions regarding the feasibility of strategic options. The objectives of the workshop were to establish the current technological capabilities for deep-underground construction, to project those capabilities through the compressed schedule proposed for construction, and to identify promising directions for timely allocation of existing research and development resources. The earth has been used as a means of protection and safekeeping for many centuries. Recently, the thickness of the earth cover required for this purpose has been extended to the 2,000- to 3,000-ft range in structures contemplated for nuclear-waste disposal, energy storage, and strategic systems. For defensive missile basing, it is now perceived that the magnitude of the threat has increased through better delivery systems, larger payloads, and variable tactics of attack. Thus, depths of 3,000 to 8,000 ft are being considered seriously for such facilities. Moreover, it appears desirable that the facilities be operational (if not totally complete) for defensive purposes within a five-year construction schedule. Deep excavations such as mines are similar in many respects to nearsurface tunnels and caverns for transit, rail, sewer, water, hydroelectric, and highway projects. But the differences that do exist are significant. Major distinctions between shallow and deep construction derive from the stress fields and behavior of earth materials around the openings. Different methodologies are required to accommodate other variations resulting from increased depth, such as elevated temperatures, reduced capability for site exploration, and limited access during project execution. This report addresses these and other questions devoted to geotechnical characterization, design, construction, and excavation equipment.

  19. Transfer of adapted water supply technologies through a demonstration and teaching facility

    Science.gov (United States)

    Nestmann, F.; Oberle, P.; Ikhwan, M.; Stoffel, D.; Blaß, H. J.; Töws, D.; Schmidt, S.

    2016-09-01

    Water scarcity can be defined as a lack of sufficient water resources or as the limited or even missing access to a safe water supply. Latter can be classified as `economic water scarcity' which among others can commonly be met in tropical and subtropical karst regions of emerging and developing countries. Karst aquifers, mostly consisting of limestone and carbonate rock, show high infiltration rates which leads to a lack of above ground storage possibilities. Thus, the water will drain rapidly into the underground and evolve vast river networks. Considering the lack of appropriate infrastructure and limited human capacities in the affected areas, these underground water resources cannot be exploited adequately. Against this, background innovative and adapted technologies are required to utilize hard-to-access water resources in a sustainable way. In this context, the German-Indonesian joint R&D project "Integrated Water Resources Management (IWRM) Indonesia" dealt with the development of highly adaptable water technologies and management strategies. Under the aegis of the Karlsruhe Institute of Technology (KIT) and funded by the German Ministry of Education and Research (BMBF), these innovative technical concepts were exemplarily implemented to remedy this deficiency in the model region Gunung Sewu, a karst area situated on the southern coast of Java Island, Indonesia. The experiences gained through the interdisciplinary joint R&D activities clearly showed that even in the case of availability of appropriate technologies, a comprising transfer of knowhow and the buildup of capabilities (Capacity Development) is inevitable to sustainably implement and disseminate new methods. In this context, an adapted water supply facility was developed by KIT which hereafter shall serve for demonstration, teaching, and research purposes. The plant's functionality, its teaching and research concept, as well as the design process, which was accomplished in collaboration with the

  20. Integrating innovative technology into remedial action at a US Department of Energy facility

    International Nuclear Information System (INIS)

    Diggs, I.W.

    1992-01-01

    The US Atomic Energy Commission (AEC), predecessor to the US Department Energy (DOE), established a production complex in the early 1950's for processing uranium and its compounds from natural uranium ore concentrates for the purpose of producing high purity uranium metal for various uses in defense reactor and nuclear weapons programs. This complex, previously known as the Feed Materials Production Center (FMPC), is now known as the Fernald Environmental Management Project (FEMP). In 1989, production was stopped at the feed materials facility due to a decision by the DOE. In December of 1989, the site was placed on the US EPA's National Priorities List (NPL) of sites requiring environmental cleanup. As a result, in April of 1990 the DOE and the US EPA signed a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Consent Agreement which augmented the FFCA. The DOE recently decided that production at the facility would not be resumed, and therefore, the main scope of work would change to remediation and closure of the site. In response to the FFCA and consistent with the modifications agreed to in the amended Consent Agreement, a Remedial Investigation/Feasibility Study (RI/FS) is in progress pursuant to CERCLA, as amended by the Superfund Amendments and Reauthorization Act (SARA). A RI/FS is a comprehensive environmental investigation systematically conducted according to US EPA regulations and guidelines used to identify and select an action plan for the cleanup of CERCLA sites. The RI phase incorporates a broad-based study to evaluate as completely as possible existing environmental and public health risks associated with past or existing facility operations. The FS phase develops and evaluates corrective action alternatives to mitigate identified environmental concerns

  1. Tubal Factor Infertility and Perinatal Risk After Assisted Reproductive Technology

    Science.gov (United States)

    Kawwass, Jennifer F.; Crawford, Sara; Kissin, Dmitry M.; Session, Donna R.; Boulet, Sheree; Jamieson, Denise J.

    2014-01-01

    OBJECTIVE To assess trends of tubal factor infertility and to evaluate risk of miscarriage and delivery of preterm or low birth weight (LBW) neonates among women with tubal factor infertility using assisted reproductive technology (ART). METHODS We assessed trends of tubal factor infertility among all fresh and frozen, donor, and nondonor ART cycles performed annually in the United States between 2000 and 2010 (N=1,418,774) using the National ART Surveillance System. The data set was then limited to fresh, nondonor in vitro fertilization cycles resulting in pregnancy to compare perinatal outcomes for cycles associated with tubal compared with male factor infertility. We performed bivariate and multivariable analyses controlling for maternal characteristics and calculated adjusted risk ratios (RRs) and 95% confidence intervals (CI). RESULTS The percentage of ART cycles associated with tubal factor infertility diagnoses decreased from 2000 to 2010 (26.02–14.81%). Compared with male factor infertility, tubal factor portended an increased risk of miscarriage (14.0% compared with 12.7%, adjusted RR 1.08, 95% CI 1.04–1.12); risk was increased for both early and late miscarriage. Singleton neonates born to women with tubal factor infertility had an increased risk of pre-term birth (15.8% compared with 11.6%, adjusted RR 1.27, 95% CI 1.20–1.34) and LBW (10.9% compared with 8.5%, adjusted RR 1.28, 95% CI 1.20–1.36). Significant increases in risk persisted for early and late preterm delivery and very low and moderately LBW delivery. A significantly elevated risk was also detected for twin, but not triplet, pregnancies. CONCLUSION Tubal factor infertility, which is decreasing in prevalence in the United States, is associated with an increased risk of miscarriage, preterm birth, and LBW delivery as compared with couples with male factor infertility using ART. PMID:23812461

  2. Risk-based investment trade-off related to building facility management

    Energy Technology Data Exchange (ETDEWEB)

    Taillandier, F. [Departement TIDS, Centre Scientifique et Technique du Batiment, 06904 Sophia Antipolis (France); Laboratoire Optimisation de la conception et Ingenierie de l' environnement, Polytech' Savoie, Universite de Savoie, 73376 Le Bourget du lac (France)], E-mail: franck.taillandier@univ-savoie.fr; Sauce, G. [Laboratoire Optimisation de la conception et Ingenierie de l' environnement, Polytech' Savoie, Universite de Savoie, 73376 Le Bourget du lac (France); Bonetto, R. [Departement TIDS, Centre Scientifique et Technique du Batiment, 06904 Sophia Antipolis (France)

    2009-04-15

    Due to his or her profession, any building facility manager has to face many decision-making situations. One of the most important to be mentioned is the arbitration of a multi-year maintenance plan for buildings. Deciding between proposed maintenance actions, according to several constraints, so as to aim at satisfying corporate strategy is a complex choice. Risk approaches can be particularly effective because of their ability to handle complexity and uncertainties. The problem is then to be able to propose a method considering risks, adapted to the specific context of building facility management. Our method, regarded as a traditional approach, includes needed resources (i.e. costs) according to constraints (i.e. budget), but it also considers several risk domains (safety, technical preservation, client satisfaction, etc.), through the consequences (gain and loss). It proposes an ergonomic arbitration system based on filters following two complementary approaches: a selection of the fundamental actions and then an optimization of the plan (in a global view). The aim, for decision-makers, is to build their own solution by testing multiple angles of vision in simulation logic. This article presents the principles of the method, illustrated by an example of a real case conducted for a leading French company.

  3. Risk-based investment trade-off related to building facility management

    International Nuclear Information System (INIS)

    Taillandier, F.; Sauce, G.; Bonetto, R.

    2009-01-01

    Due to his or her profession, any building facility manager has to face many decision-making situations. One of the most important to be mentioned is the arbitration of a multi-year maintenance plan for buildings. Deciding between proposed maintenance actions, according to several constraints, so as to aim at satisfying corporate strategy is a complex choice. Risk approaches can be particularly effective because of their ability to handle complexity and uncertainties. The problem is then to be able to propose a method considering risks, adapted to the specific context of building facility management. Our method, regarded as a traditional approach, includes needed resources (i.e. costs) according to constraints (i.e. budget), but it also considers several risk domains (safety, technical preservation, client satisfaction, etc.), through the consequences (gain and loss). It proposes an ergonomic arbitration system based on filters following two complementary approaches: a selection of the fundamental actions and then an optimization of the plan (in a global view). The aim, for decision-makers, is to build their own solution by testing multiple angles of vision in simulation logic. This article presents the principles of the method, illustrated by an example of a real case conducted for a leading French company

  4. R and D strategy on remote response technology for emergency situations of nuclear facilities in KAERI

    International Nuclear Information System (INIS)

    Jeong, Kyung Min; Cho, Jae Wan; Choi, Young Soo; Eom, Heung Seup; Seo, Yong Chil; Shin, Hoch Ul; Lee, Sung Uk; Kim, Chang Hoi; Jeong, Seung Ho; Kim, Seung Ho

    2012-01-01

    Generally speaking, robotic technologies are anticipated to be very useful for hazardous works in nuclear facilities because robotic systems are relatively immune to radiation exposure. But the application of robotic systems for such environments has not been increasing during past 20 years. Applying highly reliable and conservative 'defense in depth' concepts in the design and construction of NPPs, there is very little probability of accidents occurring or radioactive materials being released into the environments. As a precaution, however NPPs are prepared with emergency response procedures and routinely conduct exercises for post accident circumstances based on these procedures. The last year's accident at the Fukushima Daiichi nuclear power plant promotes the needs for remote response technologies based on mobile robotic system to recognize the internal status and mitigate the unanticipated events of nuclear power plants in emergency situations. For initial observation of reactor buildings two robots named 'PackBot' were used because the internal conditions were unknown so as to allow human workers for entrance into the reactor building. But there were severe limitations for the robots to perform the given tasks from various obstacles and poor visibility inside though they provided crucial information such as views of internal structures, dose level and temperature that supported the decision for human worker's entrance. The application of robots for emergency response tasks for post accidents in nuclear facilities is not a new concept. Robots were sent to recover the damaged reactor at Chernobyl where human workers could have received a lifetime dose of radiation in minutes. Based on NRC's TMI 2 Cleanup Program, several robots were built in the 1980s to help gather information and remove debris from a reactor at the Three Mile Island nuclear power plant that partially melted down in 1979. A robot was used for several years equipped with various tools allowing

  5. R and D strategy on remote response technology for emergency situations of nuclear facilities in KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyung Min; Cho, Jae Wan; Choi, Young Soo; Eom, Heung Seup; Seo, Yong Chil; Shin, Hoch Ul; Lee, Sung Uk; Kim, Chang Hoi; Jeong, Seung Ho; Kim, Seung Ho [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    Generally speaking, robotic technologies are anticipated to be very useful for hazardous works in nuclear facilities because robotic systems are relatively immune to radiation exposure. But the application of robotic systems for such environments has not been increasing during past 20 years. Applying highly reliable and conservative 'defense in depth' concepts in the design and construction of NPPs, there is very little probability of accidents occurring or radioactive materials being released into the environments. As a precaution, however NPPs are prepared with emergency response procedures and routinely conduct exercises for post accident circumstances based on these procedures. The last year's accident at the Fukushima Daiichi nuclear power plant promotes the needs for remote response technologies based on mobile robotic system to recognize the internal status and mitigate the unanticipated events of nuclear power plants in emergency situations. For initial observation of reactor buildings two robots named 'PackBot' were used because the internal conditions were unknown so as to allow human workers for entrance into the reactor building. But there were severe limitations for the robots to perform the given tasks from various obstacles and poor visibility inside though they provided crucial information such as views of internal structures, dose level and temperature that supported the decision for human worker's entrance. The application of robots for emergency response tasks for post accidents in nuclear facilities is not a new concept. Robots were sent to recover the damaged reactor at Chernobyl where human workers could have received a lifetime dose of radiation in minutes. Based on NRC's TMI 2 Cleanup Program, several robots were built in the 1980s to help gather information and remove debris from a reactor at the Three Mile Island nuclear power plant that partially melted down in 1979. A robot was used for several years

  6. Development of 3D Visualization Technology for Medium-and Large-sized Radioactive Metal Wastes from Decommissioning Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, A Rim; Park, Chan Hee; Lee, Jung Min; Kim, Rinah; Moon, Joo Hyun [Dongguk Univ., Gyongju (Korea, Republic of)

    2013-10-15

    The most important point of decommissioning nuclear facilities and nuclear power plants is to spend less money and do this process safely. In order to perform a better decommissioning nuclear facilities and nuclear power plants, a data base of radioactive waste from decontamination and decommissioning of nuclear facilities should be constructed. This data base is described herein, from the radioactive nuclide to the shape of component of nuclear facilities, and representative results of the status and analysis are presented. With the increase in number of nuclear facilities at the end of their useful life, the demand of decommissioning technologies will continue to grow for years to come. This analysis of medium-and large-sized radioactive metal wastes and 3D visualization technology of the radioactive metal wastes using the 3D-SCAN are planned to be used for constructing data bases. The data bases are expected to be used on development of the basic technologies for decommissioning nuclear facilities 4 session.

  7. Public 'in'tolerance of technological hazards and risk policy

    International Nuclear Information System (INIS)

    Simmons, P.; Walker, G.; Irwin, A.; Wynne, B.

    1998-01-01

    Full text of publication follows: it has been recognised that the notion that there is an 'acceptable' level of risk to the public from technological hazards is in many cases inappropriate. UK government policy on major industrial hazards is informed by the principle of 'tolerability' of risk (TOR). In the paper we examine this principle and how it relates to the views of people who live day-to-day with such hazards. The analysis of public views is based on the results of a Q-method study carried out in the course of recent research funded by the UK Health and Safety Executive. The Q-method study distinguishes between different bases of public toleration - and lack of toleration - of risk. The study found lack a toleration to be based on a single cluster of factors, whereas the bases for public toleration of risk were far more differentiated. The results are outlined in the paper. In the concluding section of the paper we examine the implications of these results for policy, in particular for the application of the TOR principle when setting risk criteria. (authors)

  8. The Impact of the Term Auction Facility on the Liquidity Risk Premium and Unsecured Interbank Spreads

    OpenAIRE

    Syrstad, Olav

    2014-01-01

    This paper investigates the effectiveness of the Federal Reserve's Term Auction Facility (TAF) in alleviating the liquidity shortage in USD and reducing the spread between the 3-month Libor rate and the expected policy rate. I construct a proxy for the 3-month liquidity risk premium based on data from the FX forward market which enables me to (i) decompose the Libor spread into a liquidity premium and a credit premium, and (ii) test the effectiveness of the TAF in reducing the liquidity premi...

  9. Risk management at the stage of design of high-rise construction facilities

    Science.gov (United States)

    Politi, Violetta

    2018-03-01

    This paper describes the assessment of the probabilistic risk of an accident formed in the process of designing a technically complex facility. It considers values of conditional probabilities of the compliance of load-bearing structures with safety requirements, provides an approximate list of significant errors of the designer and analyzes the relationship between the degree of compliance and the level of danger of errors. It describes and proposes for implementation the regulated procedures related to the assessment of the safety level of constructive solutions and the reliability of the construction process participants.

  10. Workshop on CEBAF [Continuous Electron Beam Accelerator Facility] spectrometer magnet design and technology: Proceedings

    International Nuclear Information System (INIS)

    1986-09-01

    The planned experimental program at CEBAF includes high-resolution, large acceptance spectrometers and a large toroidal magnetic, detector. In order to take full advantage of the high quality beam characteristics, the performances required will make these devices quite unique instruments compared to existing facilities in the same energy range. Preliminary designs have shown that such performances can be reached, but key questions concerning design concepts and most appropriate and cost-effective technologies had to be answered before going further with the designs. It was the purpose of the Workshop on CEBAF Spectrometer Magnet Design and Technology, organized by the CEBAF Research and Engineering Divisions, to provide the most complete information about the state-of-the-art tools and techniques in magnet design and construction and to discuss the ones most appropriate to the CEBAF spectrometers. In addition, it is expected that this Workshop will be the staring point for further interactions and collaborations between international magnet experts and the CEBAF staff, during the whole process of designing and building the spectrometers

  11. Person-centered care and engagement via technology of residents with dementia in aged care facilities.

    Science.gov (United States)

    Goh, Anita M Y; Loi, Samantha M; Westphal, Alissa; Lautenschlager, Nicola T

    2017-12-01

    Touchscreen technology (TT) is a resource that can improve the quality of life of residents with dementia, and care staff, in residential aged care facilities (RACF) through a person-centered care approach. To enable the use of TTs to engage and benefit people with dementia in RACFs, education is needed to explore how these devices may be used, what facilitates use, and how to address barriers. We sought to provide education and explore RACF staff views and barriers on using TT to engage their residents with dementia. An educational session on using TT with residents with dementia was given to staff from three long-term RACFs in Melbourne, Australia. A cross-sectional convenience sample of 17 staff members (personal care attendants, registered nurses, enrolled nurses, allied health clinicians, and domestic staff) who attended were administered questionnaires pre- and post-sessions. As a result of the education seminar, they were significantly more confident in their ability to use TT devices with residents. TT, and education to staff about its use with residents with dementia, is a useful strategy to enhance RACF staff knowledge and confidence, thereby enhancing the use of technology in RACFs in order to improve care standards in people with dementia.

  12. Risk of Cancer in Children Conceived by Assisted Reproductive Technology.

    Science.gov (United States)

    Reigstad, Marte Myhre; Larsen, Inger Kristin; Myklebust, Tor Åge; Robsahm, Trude Eid; Oldereid, Nan Birgitte; Brinton, Louise A; Storeng, Ritsa

    2016-03-01

    An increasing number of children are born after assisted reproductive technology (ART), and monitoring their long-term health effects is of interest. This study compares cancer risk in children conceived by ART to that in children conceived without. The Medical Birth Registry of Norway contains individual information on all children born in Norway (including information of ART conceptions). All children born between 1984 and 2011 constituted the study cohort, and cancer data were obtained from the Cancer Registry of Norway. Follow-up started at date of birth and ended on the date of the first cancer diagnosis, death, emigration, or December 31, 2011. A Cox proportional hazards model was used to calculate hazard ratios (HR) and 95% confidence intervals (CI) of overall cancer risk between children conceived by ART and those not. Cancer risk was also assessed separately for all childhood cancer types. The study cohort comprised 1 628 658 children, of which 25 782 were conceived by ART. Of the total 4554 cancers, 51 occurred in ART-conceived children. Risk of overall cancer was not significantly elevated (HR 1.21; 95% CI 0.90-1.63). However, increased risk of leukemia was observed for children conceived by ART compared with those who were not (HR 1.67; 95% CI 1.02-2.73). Elevated risk of Hodgkin's lymphoma was also found for ART-conceived children (HR 3.63; 95% CI 1.12-11.72), although this was based on small numbers. This population-based cohort study found elevated risks of leukemia and Hodgkin's lymphoma in children conceived by ART. Copyright © 2016 by the American Academy of Pediatrics.

  13. Methodology Development for Assessment of Spaceport Technology Returns and Risks

    Science.gov (United States)

    Joglekar, Prafulla; Zapata, Edgar

    2001-01-01

    As part of Kennedy Space Center's (KSC's) challenge to open the space frontier, new spaceport technologies must be developed, matured and successfully transitioned to operational systems. R&D investment decisions can be considered from multiple perspectives. Near mid and far term technology horizons must be understood. Because a multitude of technology investment opportunities are available, we must identify choices that promise the greatest likelihood of significant lifecycle At the same time, the costs and risks of any choice must be well understood and balanced against its potential returns The problem is not one of simply rank- ordering projects in terms of their desirability. KSC wants to determine a portfolio of projects that simultaneously satisfies multiple goals, such as getting the biggest bang for the buck, supporting projects that may be too risky for private funding, staying within annual budget cycles without foregoing the requirements of a long term technology vision, and ensuring the development of a diversity of technologies that, support the variety of operational functions involved in space transportation. This work aims to assist in the development of in methods and techniques that support strategic technology investment decisions and ease the process of determining an optimal portfolio of spaceport R&D investments. Available literature on risks and returns to R&D is reviewed and most useful pieces are brought to the attention of the Spaceport Technology Development Office (STDO). KSC's current project management procedures are reviewed. It is found that the "one size fits all" nature of KSC's existing procedures and project selection criteria is not conducive to prudent decision-making. Directions for improving KSC's - procedures and criteria are outlined. With help of a contractor, STDO is currently developing a tool, named Change Management Analysis Tool (CMAT)/ Portfolio Analysis Tool (PAT), to assist KSC's R&D portfolio determination. A

  14. Smart facility location planning for Smart Cities: using GIS technology and facility provision standards for pro-active planning of social facilities to support smart growth

    CSIR Research Space (South Africa)

    Green, Chéri

    2016-08-01

    Full Text Available step toward “smart” planning processes to support smart cities of the future. A case study application in Cape Town is used to illustrate the application of the methodology of spatially matching supply and demand for facilities using GIS tools...

  15. Risk disparities in the globalisation of assisted reproductive technology: the case of Asia.

    Science.gov (United States)

    Ha, Jung-Ok

    2013-01-01

    This paper analyses the disparities in risks associated with biomedical technology focusing on the results of assisted reproductive technology (ART). ART among biomedical technologies transferred to Asia is a representative case that reveals in its clinical use and related scientific research the global politics of technology. This study notes the global politics at work in the recognition of and reaction to such risks. While many Asian countries aggressively pursue technological development, weak legislative and administrative regulations have created various problems and controversial cases. This study asserts that risks associated with technology are characterised as social facts not natural ones or mere 'side effects', since technological development and risk are closely intertwined.

  16. Prospective Teachers’ Tendencies to Utilize From the Facilities of Contemporary Educational Technology

    Directory of Open Access Journals (Sweden)

    Gizem SAYGILI

    2016-07-01

    Full Text Available In terms of effectiveness and efficiency, it is important to determine the views of prospective teachers related to taking advantage of the facilities of contemporary educational technology. This study which aims to identify prospective teachers’ attitudes towards computer-assisted learning was conducted with 140 prospective teachers (86 female, 54 male who have been attending pedagogical formation education at Süleyman Demirel University in the 2013 academic year. In this study, in eight different fields of prospective teachers' attitudes towards computer assisted education were examined with different variables such as gender, major and graduation year. As a data collection tool, the "Computer Assisted Education Attitude Scale" was used in order to determine the tendencies of prospective teachers towards the use of computer-assisted learning in different fields such as physical sciences, social sciences, health sciences, fine arts, theology, mathematics and Turkish language. In the statistical analysis, frequency analysis, descriptive statistics, nonparametric statistical technics were used. As a result of the analysis it was identified that teachers participating our study exhibited substandard attitudes towards computer-assisted education. In computer-assisted education, female prospective teachers had higher attitude level than men prospective teachers. In addition, attitude scores of participants of mathematics, health sciences, fine arts and science was higher than the participants of the Turkish language, foreign languages, social sciences and theology departments. There were statistically significant difference between attitude scores of participants of different disciplines. Results of the research findings are expected to contribute to the widespread use of instructional technology, and are expected to lead to applications in other fields.Keywords: Teaching Profession, Education, Technology, Computer-Assisted Education, Attitude

  17. Seismic risk analysis for General Electric Plutonium Facility, Pleasanton, California. Final report, part II

    International Nuclear Information System (INIS)

    1980-01-01

    This report is the second of a two part study addressing the seismic risk or hazard of the special nuclear materials (SNM) facility of the General Electric Vallecitos Nuclear Center at Pleasanton, California. The Part I companion to this report, dated July 31, 1978, presented the seismic hazard at the site that resulted from exposure to earthquakes on the Calaveras, Hayward, San Andreas and, additionally, from smaller unassociated earthquakes that could not be attributed to these specific faults. However, while this study was in progress, certain additional geologic information became available that could be interpreted in terms of the existance of a nearby fault. Although substantial geologic investigations were subsequently deployed, the existance of this postulated fault, called the Verona Fault, remained very controversial. The purpose of the Part II study was to assume the existance of such a capable fault and, under this assumption, to examine the loads that the fault could impose on the SNM facility. This report first reviews the geologic setting with a focus on specifying sufficient geologic parameters to characterize the postulated fault. The report next presents the methodology used to calculate the vibratory ground motion hazard. Because of the complexity of the fault geometry, a slightly different methodology is used here compared to the Part I report. This section ends with the results of the calculation applied to the SNM facility. Finally, the report presents the methodology and results of the rupture hazard calculation

  18. Financial risks of post-closure custodial care for the Barnwell radioactive waste disposal facility - 16155

    International Nuclear Information System (INIS)

    Baird, Robert D.; Newberry, William F.

    2009-01-01

    This paper reports evaluations of the adequacy of the Barnwell Extended Care Fund in light of identified risks, with the conclusion that the fund is sufficient to cover the costs and uncertainties associated with planned post-closure care of the Barnwell, South Carolina low-level radioactive waste disposal facility. It reviews background information pertinent to the facility's post-closure monitoring and maintenance and describes financial responsibility for post-closure activities. It identifies and briefly characterizes the activities planned to be conducted following facility closure and presents the midrange estimate of planned post-closure costs. The paper identifies and quantifies sources of uncertainty in activities and costs planned for post-closure care and presents 50-, 80-, and 95-percent confidence levels of planned costs. The fund is currently sufficient to cover some but not all of the costs that might be incurred as a result of unplanned events. The paper identifies, characterizes, and quantifies unplanned events, possible consequences, and probabilities of occurrence. The paper presents costs that might be incurred in responding to the unplanned initiating events and identifies levels of confidence that the fund is adequate to cover such costs. (authors)

  19. Ten Years Experience In Geo-Databases For Linear Facilities Risk Assessment (Lfra)

    Science.gov (United States)

    Oboni, F.

    2003-04-01

    Keywords: geo-environmental, database, ISO14000, management, decision-making, risk, pipelines, roads, railroads, loss control, SAR, hazard identification ABSTRACT: During the past decades, characterized by the development of the Risk Management (RM) culture, a variety of different RM models have been proposed by governmental agencies in various parts of the world. The most structured models appear to have originated in the field of environmental RM. These models are briefly reviewed in the first section of the paper focusing the attention on the difference between Hazard Management and Risk Management and the need to use databases in order to allow retrieval of specific information and effective updating. The core of the paper reviews a number of different RM approaches, based on extensions of geo-databases, specifically developed for linear facilities (LF) in transportation corridors since the early 90s in Switzerland, Italy, Canada, the US and South America. The applications are compared in terms of methodology, capabilities and resources necessary to their implementation. The paper then focuses the attention on the level of detail that applications and related data have to attain. Common pitfalls related to decision making based on hazards rather than on risks are discussed. The paper focuses the last sections on the description of the next generation of linear facility RA application, including examples of results and discussion of future methodological research. It is shown that geo-databases should be linked to loss control and accident reports in order to maximize their benefits. The links between RA and ISO 14000 (environmental management code) are explicitly considered.

  20. Need to use probabilistic risk approach in performance assessment of waste disposal facilities

    International Nuclear Information System (INIS)

    Bonano, E.J.; Gallegos, D.P.

    1991-01-01

    Regulations governing the disposal of radioactive, hazardous, and/or mixed wastes will likely require, either directly or indirectly, that the performance of disposal facilities be assessed quantitatively. Such analyses, commonly called ''performance assessments,'' rely on the use of predictive models to arrive at a quantitative estimate of the potential impact of disposal on the environment and the safety and health of the public. It has been recognized that a suite of uncertainties affect the results of a performance assessment. These uncertainties are conventionally categorized as (1) uncertainty in the future state of the disposal system (facility and surrounding medium), (2) uncertainty in models (including conceptual models, mathematical models, and computer codes), and (3) uncertainty in data and parameters. Decisions regarding the suitability of a waste disposal facility must be made in light of these uncertainties. Hence, an approach is needed that would allow the explicit consideration of these uncertainties so that their impact on the estimated consequences of disposal can be evaluated. While most regulations for waste disposal do not prescribe the consideration of uncertainties, it is proposed that, even in such cases, a meaningful decision regarding the suitability of a waste disposal facility cannot be made without considering the impact of the attendant uncertainties. A probabilistic risk assessment (PRA) approach provides the formalism for considering the uncertainties and the technical basis that the decision makers can use in discharging their duties. A PRA methodology developed and demonstrated for the disposal of high-level radioactive waste provides a general framework for assessing the disposal of all types of wastes (radioactive, hazardous, and mixed). 15 refs., 1 fig., 1 tab

  1. Probalistisk short-term risk modeling for back-end fuel cycle and waste management facilities

    International Nuclear Information System (INIS)

    Kjellbert, N.A.

    1980-03-01

    This study of probabilistic short-term risk modeling of back-end fuel cycle and waste management facilities represents the continuation of work started in 1977. The purpose of the report is to present a more detailed survey of models and analysis techniques that mey be applicable. The definition of the risk concept and the nature of the facilities and events which are to be analyzed are described. The most important criteria are that the model or method shall be quantitative, logically/scientifically based, and be able to handle systems of some complexity. Several formalized analysis methods are described, most of them emanating from reliability theory. No single model will fulfill all criteria simultaneously, to the degree desired. Nevertheless, fault tree analysis seems to be an efficient tool in many applications, although it must probably be used together with other models in most cases. Other methodologies described can also be useful, such as failure modes and effects analysis, renewal theory and Markov chains, reliability block diagrams, event trees and cause/consequence diagrams, the GO methodology, Monte Carlo simulation, and, often necessary, various consequence modeling techniques. (author)

  2. Nominal radio ecological benchmarks for the ecological risk assessment of radioactive waste management facilities

    Energy Technology Data Exchange (ETDEWEB)

    Garisto, N.C. [SENES Consultants Ltd., Richmond Hill, Ontario (Canada)]. E-mail: ngaristo@senes.ca

    2006-07-01

    Ecological risk assessments are used to assess potential ecological impacts from contaminated sites, such as radioactive waste management and disposal facilities. These assessments determine the overall significance of the impact of such facilities on non-human biota. Specific indicator species are selected as representative non-human biota at the study sites for the purposes of these risk assessments. Potential environmental impacts are generally assessed in terms of 'screening indices'. In simple terms, a screening index is the ratio of an estimated exposure level of the indicator species (or environmental concentration) divided by a level or concentration deemed unlikely to have a significant ecological effect. These latter levels or concentrations are referred to as 'estimated no effect value' or ENEVs. Nominal ENEV values for chronic radiation effects based on our current interpretation of literature data are presented in this paper. They are: 5 mGy/d for fish and amphibians; 2.4 mGy/d for aquatic plants; 2 mGy/d for reptiles; 5 mGy/d for benthic and terrestrial invertebrates; 1 mGy/d for slow-growing terrestrial animals that reproduce late in life; 10 mGy/d for short-lived prolific terrestrial animals; 2.4 mGy/d for terrestrial plants; 5 mGy/d for birds. The paper identifies major areas of uncertainty regarding the selection of these nominal ENEVs for practical applications. (author)

  3. Nominal radio ecological benchmarks for the ecological risk assessment of radioactive waste management facilities

    International Nuclear Information System (INIS)

    Garisto, N.C.

    2006-01-01

    Ecological risk assessments are used to assess potential ecological impacts from contaminated sites, such as radioactive waste management and disposal facilities. These assessments determine the overall significance of the impact of such facilities on non-human biota. Specific indicator species are selected as representative non-human biota at the study sites for the purposes of these risk assessments. Potential environmental impacts are generally assessed in terms of 'screening indices'. In simple terms, a screening index is the ratio of an estimated exposure level of the indicator species (or environmental concentration) divided by a level or concentration deemed unlikely to have a significant ecological effect. These latter levels or concentrations are referred to as 'estimated no effect value' or ENEVs. Nominal ENEV values for chronic radiation effects based on our current interpretation of literature data are presented in this paper. They are: 5 mGy/d for fish and amphibians; 2.4 mGy/d for aquatic plants; 2 mGy/d for reptiles; 5 mGy/d for benthic and terrestrial invertebrates; 1 mGy/d for slow-growing terrestrial animals that reproduce late in life; 10 mGy/d for short-lived prolific terrestrial animals; 2.4 mGy/d for terrestrial plants; 5 mGy/d for birds. The paper identifies major areas of uncertainty regarding the selection of these nominal ENEVs for practical applications. (author)

  4. Validation of Fall Risk Assessment Specific to the Inpatient Rehabilitation Facility Setting.

    Science.gov (United States)

    Thomas, Dan; Pavic, Andrea; Bisaccia, Erin; Grotts, Jonathan

    2016-09-01

    To evaluate and compare the Morse Fall Scale (MFS) and the Casa Colina Fall Risk Assessment Scale (CCFRA) for identification of patients at risk for falling in an acute inpatient rehabilitation facility. The primary objective of this study was to perform a retrospective validation study of the CCFRAS, specifically for use in the inpatient rehabilitation facility (IRF) setting. Retrospective validation study. The study was approved under expedited review by the local Institutional Review Board. Data were collected on all patients admitted to Cottage Rehabiliation Hospital (CRH), a 38-bed acute inpatient rehabilitation hospital, from March 2012 to August 2013. Patients were excluded from the study if they had a length of stay less than 3 days or age less than 18. The area under the receiver operating characteristic curve (AUC) and the diagnostic odds ratio were used to examine the differences between the MFS and CCFRAS. AUC between fall scales was compared using the DeLong Test. There were 931 patients included in the study with 62 (6.7%) patient falls. The average age of the population was 68.8 with 503 males (51.2%). The AUC was 0.595 and 0.713 for the MFS and CCFRAS, respectively (0.006). The diagnostic odds ratio of the MFS was 2.0 and 3.6 for the CCFRAS using the recommended cutoffs of 45 for the MFS and 80 for the CCFRAS. The CCFRAS appears to be a better tool in detecting fallers vs. nonfallers specific to the IRF setting. The assessment and identification of patients at high risk for falling is important to implement specific precautions and care for these patients to reduce their risk of falling. The CCFRAS is more clinically relevant in identifying patients at high risk for falling in the IRF setting compared to other fall risk assessments. Implementation of this scale may lead to a reduction in fall rate and injuries from falls as it more appropriately identifies patients at high risk for falling. © 2015 Association of Rehabilitation Nurses.

  5. ICT security- aspects important for nuclear facilities; Information and Communication Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Thunem, Atoosa P-J.

    2005-09-15

    Rapid application growth of complex Information and Communication Technologies (ICT) in every society and state infrastructure as well as industry has revealed vulnerabilities that eventually have given rise to serious security breaches. These vulnerabilities together with the course of the breaches from cause to consequence are gradually about to convince the field experts that ensuring the security of ICT-driven systems is no longer possible by only relying on the fundaments of computer science, IT, or telecommunications. Appropriating knowledge from other disciplines is not only beneficial, but indeed very necessary. At the same time, it is a common observation today that ICT-driven systems are used everywhere, from the nuclear, aviation, commerce and healthcare domains to camera-equipped web-enabled cellular phones. The increasing interdisciplinary and inter-sectoral aspects of ICT security worldwide have been providing updated and useful information to the nuclear domain, as one of the emerging users of ICT-driven systems. Nevertheless, such aspects have also contributed to new and complicated challenges, as ICT security for the nuclear domain is in a much more delicate manner than for any other domains related to the concept of safety, at least from the public standpoint. This report addresses some important aspects of ICT security that need to be considered at nuclear facilities. It deals with ICT security and the relationship between security and safety from a rather different perspective than usually observed and applied. The report especially highlights the influence on the security of ICT-driven systems by all other dependability factors, and on that basis suggests a framework for ICT security profiling, where several security profiles are assumed to be valid and used in parallel for each ICT-driven system, sub-system or unit at nuclear facilities. The report also covers a related research topic of the Halden Project with focus on cyber threats and

  6. Current developments of fuel fabrication technologies at the plutonium fuel production facility, PFPF

    International Nuclear Information System (INIS)

    Asakura, K.; Aono, S.; Yamaguchi, T.; Deguchi, M.

    2000-01-01

    The Japan Nuclear Cycle Development Institute, JNC, designed, constructed and has operated the Plutonium Fuel Production Facility, PFPF, at the JNC Tokai Works to supply MOX fuels to the proto-type Fast Breeder Reactor, FBR, 'MONJU' and the experimental FBR 'JOYO' with 5 tonMOX/year of fabrication capability. Reduction of personal radiation exposure to a large amount of plutonium is one of the most important subjects in the development of MOX fabrication facility on a large scale. As the solution of this issue, the PFPF has introduced automated and/or remote controlled equipment in conjunction with computer controlled operation scheme. The PFPF started its operation in 1988 with JOYO reload fuel fabrication and has demonstrated MOX fuel fabrication on a large scale through JOYO and MONJU fuel fabrication for this decade. Through these operations, it has become obvious that several numbers of equipment initially installed in the PFPF need improvements in their performance and maintenance for commercial utilization of plutonium in the future. Furthermore, fuel fabrication of low density MOX pellets adopted in the MONJU fuel required a complete inspection because of difficulties in pellet fabrication compared with high density pellet for JOYO. This paper describes new pressing equipment with a powder recovery system, and pellet finishing and inspection equipment which has multiple functions, such as grinding measurements of outer diameter and density, and inspection of appearance to improve efficiency in the pellet finishing and inspection steps. Another development of technology concerning an annular pellet and an innovative process for MOX fuel fabrication are also described in this paper. (author)

  7. The Annual Neutron School: Program and Facility for Nuclear Science and Technology

    International Nuclear Information System (INIS)

    Dingle, C.A.M.; Bautista, U.M.; Jecong, J.F.M.; Hila, F.C.; Astronomo, A.A.; Olivares, R.U.; Guillermo, N.R.D.; Ramo, M.E.S.K.V.; Saligan, P.P.

    2015-01-01

    The core realization of the mandate of the Philippine Nuclear Research Institute (PNRI) is the establishment and utilization of major nuclear facilities in lieu of the decommissioned research reactor. To address the need for manpower in the future, the applied physics research section (APRS) of the PNRI has initiated capacity building in the use and operation of small neutron sources which attempts to re-establish, develop and sustain expertise in nuclear science and technology. These activities have provided the theoretical and experimental training of young professionals and scientist of the institute which, consequently, resulted in the conceptualization of the Annual Neutron School (ANS).The ANS provides training and teaching environments for the young generation who will operate, utilize and regulate future nuclear facilities. More importantly, it demonstrates and presents the acquired knowledge and research outputs by the staff via “train a trainer” concept to an audience of junior undergraduate students. The successful implementation of the ANS has been participated by selected universities within Metro Manila and was able to train a number of students since its establishment in 2013. The program offers training, education, and R & D in the basic nuclear instrumentation and techniques which includes (1) characterization of different neutron sources – AmBe, PuBe and Cf-252; (2) development of Neutron Activation Analysis (NAA) technique using a portable neutron source for non-destructive elemental analysis; (3) utilization of MCNP (Monte Carlo N-Particle) code for verification of experimental data on neutron characterization, radiation dosimetry, detector design, calibration and efficiency and TRIGA fuel assembly configuration for sub-critical experiments. (author)

  8. The risk of nuclear power in Germany compared with the risk other electricity generating technologies

    International Nuclear Information System (INIS)

    Preiss, P.; Wissel, S.; Fahl, U.; Friedrich, R.; Voss, A.

    2013-01-01

    The report shows that no electricity generation technology is without risk and without environmental impact. Taking into account the quantifiable risks of loss expenses in case of accidents the study shows that the health hazards and economical risk are by trend about equal for nuclear power and renewable energy sources. The study is based on the statement that the severe accident in Fukushima-Daiichi cannot be ascribed to so-called remaining risk since the NPP was not designed for tsunamis of the size that occurred in 2011 although this size was of high probability and that the calculated very low probabilities for severe accidents in German nuclear power plants correspond to the reality.

  9. Analysis of Debris Trajectories at the Scaled Wind Farm Technology (SWiFT) Facility

    Energy Technology Data Exchange (ETDEWEB)

    White, Jonathan R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Burnett, Damon J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-01-01

    Sandia National Laboratories operates the Scaled Wind Farm Technology Facility (SWiFT) on behalf of the Department of Energy Wind and Water Power Technologies Office. An analysis was performed to evaluate the hazards associated with debris thrown from one of SWiFT’s operating wind turbines, assuming a catastrophic failure. A Monte Carlo analysis was conducted to assess the complex variable space associated with debris throw hazards that included wind speed, wind direction, azimuth and pitch angles of the blade, and percentage of the blade that was separated. In addition, a set of high fidelity explicit dynamic finite element simulations were performed to determine the threshold impact energy envelope for the turbine control building located on-site. Assuming that all of the layered, independent, passive and active engineered safety systems and administrative procedures failed (a 100% failure rate of the safety systems), the likelihood of the control building being struck was calculated to be less than 5/10,000 and ballistic simulations showed that the control building would not provide passive protection for the majority of impact scenarios. Although options exist to improve the ballistic resistance of the control building, the recommendation is not to pursue them because there is a low probability of strike and there is an equal likelihood personnel could be located at similar distances in other areas of the SWiFT facility which are not passively protected, while the turbines are operating. A fenced exclusion area has been created around the turbines which restricts access to the boundary of the 1/100 strike probability. The overall recommendation is to neither relocate nor improve passive protection of the control building as the turbine safety systems have been improved to have no less than two independent, redundant, high quality engineered safety systems. Considering this, in combination with a control building strike probability of less than 5/10,000, the

  10. US DOE surplus facilities management program (SFMP). International technology exchange activities

    International Nuclear Information System (INIS)

    Broderick, J.

    1986-01-01

    The Surplus Facilities Management Program is one of five remedial action programs established by the US Department of Energy (DOE) to eliminate potential hazards to the public and environment from radioactive contamination. These programs provide remedial actions at various facilities and sites previously used by the US Government in national atomic energy programs. Included are uranium ore milling sites, nuclear materials production plants, and research and development facilities. The DOE's five remedial action programs are: the Grand Junction Remedial Action Project; the Formerly Utilized Sites Remedial Action Project; the West Valley Demonstration Project; and the Surplus Facilities Management Program. The Surplus Facilities Management Program (SWMP) was established by DOE in 1978. There are presently over 300 shutdown facilities in the SFMP located at sites across the United States and in Puerto Rico. In some cases, remedial action involves decontaminating and releasing a facility for some other use. In other instances, facilities are completely demolished and removed from the site

  11. Report to Congress on innovative safety and security technology solutions for alternative transportation facilities

    Science.gov (United States)

    2017-05-01

    This research collected information on the frequency and impact of safety and security incidents (threats) at selected facilities and identified priority incidents at each facility. A customized all hazards approach was used to determine the ha...

  12. Regulatory uncertainty and the associated business risk for emerging technologies

    International Nuclear Information System (INIS)

    Hoerr, Robert A.

    2011-01-01

    An oversight system specifically concerned with nanomaterials should be flexible enough to take into account the unique aspects of individual novel materials and the settings in which they might be used, while recognizing that heretofore unrecognized safety issues may require future modifications. This article considers a question not explicitly considered by the project team: what is the risk that uncertainty over how regulatory oversight will be applied to nanomaterials will delay or block the development of this emerging technology, thereby depriving human health of potential and substantial benefits? An ambiguous regulatory environment could delay the availability of valuable new technology and therapeutics for human health by reducing access to investment capital. Venture capitalists list regulatory uncertainty as a major reason not to invest at all in certain areas. Uncertainty is far more difficult to evaluate than risk, which lends itself to quantitative models and can be factored into projections of return on possible investments. Loss of time has a large impact on investment return. An examination of regulatory case histories suggests that an increase in regulatory resting requirement, where the path is well-defined, is far less costly than a delay of a year or more in achieving product approval and market launch.

  13. Computer technologies for industrial risk prevention and emergency management

    International Nuclear Information System (INIS)

    Balduccelli, C.; Bologna, S.; Di Costanzo, G.; Vicoli, G.

    1996-07-01

    This document provides an overview about problems related to the engineering of computer based systems for industrial risk prevention and emergency management. Such systems are rather complex and subject to precise reliability and safety requirements. With the evolution of informatic technologies, such systems are becoming to be the means for building protective barriers for reduction of risk associated with plant operations. For giving more generality to this document, and for not concentrating on only a specific plant, the emergency management systems will be dealt with more details than ones for accident prevention. The document is organized in six chapters. Chapter one is an introduction to the problem and to its state of art, with particular emphasis to the aspects of safety requirements definition. Chapter two is an introduction to the problems related to the emergency management and to the training of operators in charge of this task. Chapter three deals in details the topic of the Training Support Systems, in particular about MUSTER (multi-user system for training and evaluation of environmental emergency response) system. Chapter four deals in details the topic of decision support systems, in particular about ISEM (information technology support for emergency management) system. Chapter five illustrates an application of support to the operators of Civil Protection Department for the management of emergencies in the fields of industrial chemical. Chapter six is about a synthesis of the state of art and the future possibilities, identifying some research and development activities more promising for the future

  14. Regulatory uncertainty and the associated business risk for emerging technologies

    Science.gov (United States)

    Hoerr, Robert A.

    2011-04-01

    An oversight system specifically concerned with nanomaterials should be flexible enough to take into account the unique aspects of individual novel materials and the settings in which they might be used, while recognizing that heretofore unrecognized safety issues may require future modifications. This article considers a question not explicitly considered by the project team: what is the risk that uncertainty over how regulatory oversight will be applied to nanomaterials will delay or block the development of this emerging technology, thereby depriving human health of potential and substantial benefits? An ambiguous regulatory environment could delay the availability of valuable new technology and therapeutics for human health by reducing access to investment capital. Venture capitalists list regulatory uncertainty as a major reason not to invest at all in certain areas. Uncertainty is far more difficult to evaluate than risk, which lends itself to quantitative models and can be factored into projections of return on possible investments. Loss of time has a large impact on investment return. An examination of regulatory case histories suggests that an increase in regulatory resting requirement, where the path is well-defined, is far less costly than a delay of a year or more in achieving product approval and market launch.

  15. Influences of Inadequate Instructional Materials and Facilities in Teaching and Learning of Electrical/Electronics Technology Education Courses

    Science.gov (United States)

    Ogbu, James E.

    2015-01-01

    This study investigated the influences of inadequate instructional materials and facilities in the teaching and learning of electrical/electronics (E/E) technology education courses. The study was guided by two research questions and two null hypotheses which were tested at 0.05 level of significance. The design employed was descriptive survey…

  16. Study on the state-of-the-arts technologies and policy trends for the decommissioning of nuclear installations and facilities

    International Nuclear Information System (INIS)

    Jeong, G. J.; Park, J. H.; Jeong, U. S. and others

    2005-12-01

    D and D project of the nuclear facilities is now the one of the biggest projects among the nuclear ones in the world. The nuclear facilities have their unique characteristics so making preparations about technical research in advance is very important in economic side and worker's protection side. Especially, because workers have a high possibility to contact radioactive material directly, an automation technology and shielding technology for worker's protection as well as a system development which can perform D and D work efficiently are necessary for D and D project. The waste reduction technology development, D and D equipment development, container development, and the study related the establishment of the level of the release regulation for radioactive waste are also important. The purpose of this research is to grasp of the national and internal D and D status for the nuclear facilities and to estimate them so we expect to prevent the possibility of a tremendous economical loss as the initiative of the nuclear D and D market is lost due to not understand the situation about the status of the related technologies. And we also expect to practical use the accumulated experience to decommissioning facilities in North

  17. Sandia Wake Imaging System Field Test Report: 2015 Deployment at the Scaled Wind Farm Technology (SWiFT) Facility.

    Energy Technology Data Exchange (ETDEWEB)

    Naughton, Brian Thomas [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Herges, Thomas [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-10-01

    This report presents the objectives, configuration, procedures, reporting , roles , and responsibilities and subsequent results for the field demonstration of the Sandia Wake Imaging System (SWIS) at the Sandia Scaled Wind Farm Technology (SWiFT) facility near Lubbock, Texas in June and July 2015.

  18. Benefits and Barriers of Information and Communication Technologies Adoption in Facilities Management Services Supply Chain

    DEFF Research Database (Denmark)

    Scupola, Ada

      This paper presents the results of a study of factors impacting information and communication technology (ICT) adoption in the supply chain of facilities management services. The research questions addressed in this study are: What are the key factors that influence adoption and assimilation of...

  19. A reliability-risk modelling of nuclear rad-waste facilities

    International Nuclear Information System (INIS)

    Lehmann, P.H.; El-Bassioni, A.A.

    1975-01-01

    Rad-waste disposal systems of nuclear power sites are designed and operated to collect, delay, contain, and concentrate radioactive wastes from reactor plant processes such that on-site and off-site exposures to radiation are well below permissible limits. To assist the designer in achieving minimum release/exposure goals, a computerized reliability-risk model has been developed to simulate the rad-waste system. The objectives of the model are to furnish a practical tool for quantifying the effects of changes in system configuration, operation, and equipment, and for the identification of weak segments in the system design. Primarily, the model comprises a marriage of system analysis, reliability analysis, and release-risk assessment. Provisions have been included in the model to permit the optimization of the system design subject to constraints on cost and rad-releases. The system analysis phase involves the preparation of a physical and functional description of the rad-waste facility accompanied by the formation of a system tree diagram. The reliability analysis phase embodies the formulation of appropriate reliability models and the collection of model parameters. Release-risk assessment constitutes the analytical basis whereupon further system and reliability analyses may be warranted. Release-risk represents the potential for release of radioactivity and is defined as the product of an element's unreliability at time, t, and the radioactivity available for release in time interval, Δt. A computer code (RARISK) has been written to simulate the tree diagram of the rad-waste system. Reliability and release-risk results have been generated for cases which examined the process flow paths of typical rad-waste systems, the effects of repair and standby, the variations of equipment failure and repair rates, and changes in system configurations. The essential feature of this model is that a complex system like the rad-waste facility can be easily decomposed into its

  20. Tsunami risk assessment for facility group over a wide area using inundation assessment method considering energy conservation law

    International Nuclear Information System (INIS)

    Fukutani, Yo; Imamura, Fumihiko; Tokunaga, Takeshi; Sato, Ichiro

    2015-01-01

    We propose a quantitative evaluation method of overall tsunami risk that the entire facility group over a wide area holds. We considerably reduced the calculation cost for tsunami inundation depth by adopting the evaluation method using energy conservation law as compared with the evaluation method using non-linear long wave equation. For financial institutions such as banks and insurance companies with contractors over a wide area and business companies with multiple their assets and facilities in various places, the proposed evaluation method in this study could be a useful approach to implement their risk-based management decisions for tsunami risk. (author)

  1. Seismic risk analysis for the Babcock and Wilcox facility, Leechburg, Pennsylvania

    International Nuclear Information System (INIS)

    1977-01-01

    The results of a detailed seismic risk analysis of the Babcock and Wilcox Plutonium Fuel Fabrication facility at Leechburg, Pennsylvania are presented. This report focuses on earthquakes; the other natural hazards, being addressed in separate reports, are severe weather (strong winds and tornados) and floods. The calculational method used is based on Cornell's work (1968); it has been previously applied to safety evaluations of major projects. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases. Because of the aseismicity of the region around the site, an analysis different from the conventional closest approach in a tectonic province was adapted. Earthquakes as far from the site as 1,000 km were included, as were the possibility of earthquakes at the site. In addition, various uncertainties in the input were explicitly considered in the analysis. The results of the risk analysis, which include a Bayesian estimate of the uncertainties, are presented, expressed as return period accelerations. The best estimate curve indicates that the Babcock and Wilcox facility will experience 0.05 g every 220 years and 0.10 g every 1400 years. The bounding curves roughly represent the one standard deviation confidence limits about the best estimate, reflecting the uncertainty in certain of the input. Detailed examination of the results show that the accelerations are very insensitive to the details of the source region geometries or the historical earthquake statistics in each region and that each of the source regions contributes almost equally to the cumulative risk at the site. If required for structural analysis, acceleration response spectra for the site can be constructed by scaling the mean response spectrum for alluvium in WASH 1255 by these peak accelerations

  2. Experimental research subject and renovation of chemical processing facility (CPF) for advanced fast reactor fuel reprocessing technology development

    International Nuclear Information System (INIS)

    Koyama, Tomozo; Shinozaki, Tadahiro; Nomura, Kazunori; Koma, Yoshikazu; Miyachi, Shigehiko; Ichige, Yoshiaki; Kobayashi, Tsuguyuki; Nemoto, Shin-ichi

    2002-01-01

    In order to enhance economical efficiency, environmental impact and nuclear nonproliferation resistance, the Advanced Reprocessing Technology, such as simplification and optimization of process, and applicability evaluation of the innovative technology that was not adopted up to now, has been developed for the reprocessing of the irradiated fuel taken out from a fast reactor. Renovation of the hot cell interior equipments, establishment and updating of glove boxes, installation of various analytical equipments, etc. in the Chemical Processing Facility (CPF) was done to utilize the CPF more positivity which is the center of the experimental field, where actual fuel can be used, for research and development towards establishment of the Advanced Reprocessing Technology development. The hot trials using the irradiated fuel pins of the experimental fast reactor 'JOYO' for studies on improved aqueous reprocessing technology, MA separation technology, dry process technology, etc. are scheduled to be carried out with these new equipments. (author)

  3. Accident Precursor Analysis and Management: Reducing Technological Risk Through Diligence

    Science.gov (United States)

    Phimister, James R. (Editor); Bier, Vicki M. (Editor); Kunreuther, Howard C. (Editor)

    2004-01-01

    Almost every year there is at least one technological disaster that highlights the challenge of managing technological risk. On February 1, 2003, the space shuttle Columbia and her crew were lost during reentry into the atmosphere. In the summer of 2003, there was a blackout that left millions of people in the northeast United States without electricity. Forensic analyses, congressional hearings, investigations by scientific boards and panels, and journalistic and academic research have yielded a wealth of information about the events that led up to each disaster, and questions have arisen. Why were the events that led to the accident not recognized as harbingers? Why were risk-reducing steps not taken? This line of questioning is based on the assumption that signals before an accident can and should be recognized. To examine the validity of this assumption, the National Academy of Engineering (NAE) undertook the Accident Precursors Project in February 2003. The project was overseen by a committee of experts from the safety and risk-sciences communities. Rather than examining a single accident or incident, the committee decided to investigate how different organizations anticipate and assess the likelihood of accidents from accident precursors. The project culminated in a workshop held in Washington, D.C., in July 2003. This report includes the papers presented at the workshop, as well as findings and recommendations based on the workshop results and committee discussions. The papers describe precursor strategies in aviation, the chemical industry, health care, nuclear power and security operations. In addition to current practices, they also address some areas for future research.

  4. 6 CFR 27.205 - Determination that a chemical facility “presents a high level of security risk.”

    Science.gov (United States)

    2010-01-01

    ... 6 Domestic Security 1 2010-01-01 2010-01-01 false Determination that a chemical facility âpresents... SECURITY, OFFICE OF THE SECRETARY CHEMICAL FACILITY ANTI-TERRORISM STANDARDS Chemical Facility Security Program § 27.205 Determination that a chemical facility “presents a high level of security risk.” (a...

  5. Fusion technology development: role of fusion facility upgrades and fission test reactors

    International Nuclear Information System (INIS)

    Hsu, P.Y.; Deis, G.A.; Longhurst, G.R.; Miller, L.G.; Schmunk, R.E.

    1983-01-01

    The near term national fusion program is unlikely to follow the aggressive logic of the Fusion Engineering Act of 1980. Faced with level budgets, a large, new fusion facility with an engineering thrust is unlikely in the near future. Within the fusion community the idea of upgrading the existing machines (TFTR, MFTF-B) is being considered to partially mitigate the lack of a design data base to ready the nation to launch an aggressive, mission-oriented fusion program with the goal of power production. This paper examines the cost/benefit issues of using fusion upgrades to develop the technology data base which will be required to support the design and construction of the next generation of fusion machines. The extent of usefulness of the nation's fission test reactors will be examined vis-a-vis the mission of the fusion upgrades. The authors show that while fission neutrons will provide a useful test environment in terms of bulk heating and tritium breeding on a submodule scale, they can play only a supporting role in designing the integrated whole modules and systems to be used in a nuclear fusion machine

  6. National Ignition Facility quality assurance plan for laser materials and optical technology

    International Nuclear Information System (INIS)

    Wolfe, C.R.

    1996-05-01

    Quality achievement is the responsibility of the line organizations of the National Ignition Facility (NIF) Project. This subtier Quality Assurance Plan (QAP) applies to activities of the Laser Materials ampersand Optical Technology (LM ampersand OT) organization and its subcontractors. It responds to the NIF Quality Assurance Program Plan (QAPP, L-15958-2, NIF-95-499) and Department of Energy (DOE) Order 5700.6C. This Plan is organized according to 10 Quality Assurance (QA) criteria and subelements of a management system as outlined in the NIF QAPP. This Plan describes how those QA requirements are met. This Plan is authorized by the Associate Project Leader for the LM ampersand OT organization, who has assigned responsibility to the Optics QA engineer to maintain this plan, with the assistance of the NIF QA organization. This Plan governs quality-affecting activities associated with: design; procurement; fabrication; testing and acceptance; handling and storage; and installation of NIF Project optical components into mounts and subassemblies

  7. NFC like wireless technology for monitoring purposes in scientific/industrial facilities

    International Nuclear Information System (INIS)

    Badillo, I.; Eguiraun, M.; Jugo, J.

    2012-01-01

    Wireless technologies are becoming more and more used in large industrial and scientific facilities like particle accelerators for facilitating the monitoring and indeed sensing in these kind of large environments. Cabled equipment means little flexibility in placement and is very expensive in both money and effort whenever reorganization or new installation is needed. So, when cabling is not really needed for performance reasons wireless monitoring and control is a good option, due to the speed of implementation. There are several wireless flavors to choose, as Bluetooth, Zigbee, WiFi, etc. depending on the requirements of each specific application. In this work a wireless monitoring system for EPICS (Experimental and Industrial Control System) is presented. The desired control system variables are acquired over the network and published in a mobile device, allowing the operator to check process variables everywhere the signal spreads. In this approach, a Python based server will be continuously getting EPICS Process Variables via Channel Access protocol and sending them through a WiFi standard 802.11 network using ICE middle-ware. ICE is a tool-kit oriented to build distributed applications. Finally, the mobile device will read the data and show it to the operator. The security of the communication can be improved by means of a weak wireless signal, following the same idea as in Near Field Communication (NFC), but for more large distances. With this approach, local monitoring and control applications, as for example a vacuum control system for several pumps, are currently implemented. (authors)

  8. Fusion technology development: role of fusion facility upgrades and fission test reactors

    International Nuclear Information System (INIS)

    Hsu, P.Y.; Deis, G.A.; Miller, L.G.; Longhurst, G.R.; Schmunk, R.E.

    1983-01-01

    The near term national fusion program is unlikely to follow the aggressive logic of the Fusion Engineering Act of 1980. Faced with level budgets, a large, new fusion facility with an engineering thrust is unlikely in the near future. Within the fusion community the idea of upgrading the existing machines (TFTR, MFTF-B) is being considered to partially mitigate the lack of a design data base to ready the nation to launch an aggressive, mission-oriented fusion program with the goal of power production. This paper examines the cost/benefit issues of using fusion upgrades to develop the technology data base which will be required to support the design and construction of the next generation of fusion machines. The extent of usefulness of the nation's fission test reactors will be examined vis-a-vis the mission of the fusion upgrades. We will show that while fission neutrons will provide a useful test environment in terms of bulk heating and tritium breeding on a submodule scale, they can play only a supporting role in designing the integrated whole modules and systems to be used in a nuclear fusion machine

  9. Seismic risk evaluation within the technology neutral framework

    International Nuclear Information System (INIS)

    Johnson, B.C.; Apostolakis, G.E.

    2012-01-01

    Highlights: ► We examine seismic risk within the Technology Neutral Framework (TNF). ► We find that the risk goals in the TNF to be stringent compared with current goals. ► We note that the current fleet reactors would not meet the TNF goals. ► We recommend that an initiating frequency cutoff of 10 −5 per year be use in evaluating seismic risk. - Abstract: The NRC Office of Nuclear Regulatory Research has proposed a risk-informed and performance-based licensing process that is referred to as the technology neutral framework (TNF). In the TNF, licensing basis events (LBEs), determined using probabilistic risk assessment methods, take the place of design basis accidents. These LBEs are constructed by grouping together accident sequences with similar phenomenology. All event sequences with a mean frequency greater than 10 −7 per reactor year are to be considered as part of the licensing basis. Imposing such a limit would require that earthquakes with a mean return period of ten million years be considered as part of the licensing basis. It is difficult to get seismic hazards (i.e., ground accelerations) from expert seismologists at such low frequencies. This is because it is difficult or impossible to confidently say what the seismic hazard might be at these extremely low frequencies. A linear extrapolation in log-log space of hazard curves at the Clinton site down to 10 −7 per year leads to a peak ground acceleration of about 4.5 g. A Weibull distribution is also used to fit the curve leading to a peak ground acceleration of about 2.6 g. These extrapolations demonstrate the extreme nature of rare earthquakes. Even when seismic isolation is implemented, the TNF goal is not met. The problem appears to be that there is no limit on initiating event frequency in the TNF. Demonstrating that a design meets the goals of the TNF would be nearly impossible. A frequency limit for earthquakes could be imposed at a frequency of about 10 −5 per year to focus on

  10. Application of accident progression event tree technology to the Savannah River Site Defense Waste Processing Facility SAR analysis

    International Nuclear Information System (INIS)

    Brandyberry, M.D.; Baker, W.H.; Wittman, R.S.; Amos, C.N.

    1993-01-01

    The Accident Analysis in the Safety Analysis Report (SAR) for the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) has recently undergone an upgrade. Non-reactor SARs at SRS (and other Department of Energy (DOE) sites) use probabilistic techniques to assess the frequency of accidents at their facilities. This paper describes the application of an extension of the Accident Progression Event Tree (APET) approach to accidents at the SRS DWPF. The APET technique allows an integrated model of the facility risk to be developed, where previous probabilistic accident analyses have been limited to the quantification of the frequency and consequences of individual accident scenarios treated independently. Use of an APET allows a more structured approach, incorporating both the treatment of initiators that are common to more than one accident, and of accident progression at the facility

  11. Evaluation of environmental-control technologies for commercial nuclear fuel-conversion (UF6) facilities

    International Nuclear Information System (INIS)

    Perkins, B.L.

    1982-10-01

    At present in the United States, there are two commercial conversion facilities. These facilities process uranium concentrate into UF 6 for shipment to the enrichment facilities. One conversion facility uses a dry hydrofluor process, whereas the other facility uses a process known as the wet solvent extraction-fluorination process. Because of the different processes used in the two plants, waste characteristics, quantities, and treatment practices differ at each facility. Wastes and effluent streams contain impurities found in the concentrate (such as uranium daughters, vanadium, molybdenum, selenium, arsenic, and ammonia) and process chemicals used in the circuit (including fluorine, nitrogen, and hydrogen), as well as small quantities of uranium. Studies of suitable disposal options for the solid wastes and sludges generated at the facilities and the long-term effects of emissions to the ambient environment are needed. 30 figures, 34 tables

  12. Control de configuraciones peligrosas en instalaciones con riesgo asociado // Hazardous configurations control in risk related facilities

    Directory of Open Access Journals (Sweden)

    Antonio Torres - Valle

    2010-05-01

    Full Text Available ResumenEl control de configuraciones peligrosas en instalaciones con riesgo asociado es una aplicación delos Análisis Probabilistas de Seguridad (APS previos de las mismas. Una opción de mayor alcancees el uso de monitores de riesgo los que permiten la detección en tiempo real de talesconfiguraciones. Dada la complejidad de los APS y de los monitores de riesgo, esta tarea requiere depersonal experto. El documento presenta un método cualitativo de control de configuracionespeligrosas basado en matrices de dependencias. El algoritmo, informatizado en el códigoCONFIGURACION, puede ser aplicado sin necesidad de APS previos ni uso de monitores de riesgo.La sencillez del método justifica su extensión a instalaciones donde tales herramientas no se handesarrollado, permitiendo así la detección de las configuraciones peligrosas durante su explotación yelevando la seguridad de las plantas. Un sistema similar al descrito se utiliza como ayuda en laoperación de la central nuclear de Embalse. El artículo muestra el uso del método utilizando comobase un sistema de seguridad simplificado.Palabras claves: control de configuración, Análisis Probabilista de Seguridad (APS, matriz de___________________________________________________________________________AbstractThe hazardous configurations control in risk related facilities is an application of the previousProbabilistic Safety Analysis (PSA. A more complete option is the risk monitoring for the on-linedetection of these configurations. The expert personnel are required for this task take into account thecomplexity of the PSA and risk monitor. The paper presents a method of configuration control, basedon dependence matrixes. The algorithm is included in a computer code called CONFIGURACION, todetermine these situations in a qualitative way, without previous PSA results or using a Risk Monitor.The simplicity of the method warrants its application to facilities where these tools have not

  13. Impacts of the use of institutional controls on risk assessments at Department of Energy facilities

    International Nuclear Information System (INIS)

    White, R.K.; Swindle, D.W. Jr.; Redfearn, A.; King, A.D.; Shaw, R.A.

    1992-01-01

    The United States Environmental Protection Agency (EPA), in the National Oil and Hazardous Waste Pollution Contingency Plan (NCP), has determined that institutional controls cannot be applied when determining baseline human health risks from exposure to contaminants present at a hazardous waste site. Environmental restoration activities at DOE-OR/ER sites are primarily driven by the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Therefore, the report focuses on the approaches and assumptions relating to institutional controls under CERCLA. In order to demonstrate the implications of the use of institutional controls at DOE facilities, this report summarizes the approaches and results of the recent baseline risk assessment for Solid Waste Storage Area 6 at Oak Ridge National Laboratory. The report concludes with possible options on the use of institutional controls at DOE-OR/ER sites. This report summarizes some of the major issues related to the use of institutional controls at hazardous waste sites under the auspices of DOE-OR/ER. In particular, the report addresses the impacts that assumptions regarding institutional controls have on the results and interpretation of the risk assessment, [in both the Remedial Investigation (RI) and the FS] and provides a case study from an actual DOE site

  14. Financial Risk Factor Analysis for Facility Gas Leakages of H2 and NG

    Directory of Open Access Journals (Sweden)

    In-Bok Lee

    2016-09-01

    Full Text Available Fuel cells may be the key to a more environmentally-friendly future because they emit low carbon dioxide per unit of energy supplied. However, little work has investigated the potential financial risks pertaining to fuel cell systems. Often used in the analysis of the safety of systems involving flammable or hazardous materials, risk factor analysis has recently been used to analyze the potential financial losses that may occur from industrial hazards. Therefore, this work undertakes a financial risk factor analysis to determine the costs of leakages of hydrogen and natural gas, which are used in fuel cell systems. Total leakage was calculated from an analysis of several leakage rates and modes. The impact of applying appropriate detection and prevention systems was also investigated. The findings were then used to analyze the consequences for various sections of the system and to calculate the overall cost based on facility outage or damage, and the cost of taking safety precautions. This provides a basis for comparison among proposed potential reactionary measures.

  15. 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)

  16. 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)

  17. Risk assessment methodology for extreme wind and missile effects on critical facilities

    International Nuclear Information System (INIS)

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

    1985-01-01

    The TORMIS methodology has been applied to a number of probabilistic risk assessments of critical facilities in the continental United States. These analyses have centered on the estimation of tornado missile impact and damage risks to individual targets as well as to groups of targets at specific plants. A number of advancements and generalizations in the approach have recently been made. These include: (1) generalization of windfield options to include straight winds (WINMIS) and hurricanes (HURMIS); (2) generalization of the scoring to enable analysis of Boolean system expressions for damage probabilities on compound series and parallel safety trains; (3) generalization of the failure criteria to include wind pressure as well as missile impact; (4) generalization of the plant modeling capability to enable more detailed treatment of targets partially or fully enclosed by vulnerable cladding and to allow tracking of missiles inside such enclosures; and (5) incorporation of windspeed criteria for structural failure and subsequent production of potential missiles. This paper will present some of the basic theory and key results of recent TORMIS, WINMIS, and HURMIS applications. The influence of uncertainties in the estimation process and the data needed for plant-specific risk assessments will also be discussed

  18. Innovative and adaptive technologies in decommissioning of nuclear facilities. Final report of a coordinated research project 2004-2008

    International Nuclear Information System (INIS)

    2008-10-01

    There are dozens of old reactors and other nuclear facilities worldwide that are either being actively dismantled or are candidates for decommissioning in the near term. A significant proportion of these facilities are situated in Member States or institutions that do not have adequate expertise and technologies for planning and implementing state of the art decommissioning projects. The technology selection process is critical in that regard. The main objective of the IAEA technical activities on decommissioning is to promote the exchange of lessons learned in order to improve the technologies, thereby contributing to successful planning and implementation of decommissioning. This should be achieved through a better understanding of the decision making process in technology comparison and selection and relevant issues affecting the entire decommissioning process. The specific objectives of the Coordinated Research Project (CRP) on Innovative and Adaptive Technologies in Decommissioning of Nuclear Facilities include the following general aspects: (a) To establish methodologies and data needs for developing concepts and approaches relevant to technology comparison and selection in decommissioning; (b) To improve and expand the database on applications and performance of various types of decommissioning technologies; (c) To address specific issues for individual decommissioning technologies and generate data relevant to their comparison and selection. It is also expected that this project, and in particular the papers collected in this TECDOC, will draw Member States' attention to the practicality and achievability of timely planning and implementation of decommissioning, especially for many smaller projects. Concluding reports that summarized the work undertaken under the aegis of the CRP were presented at the third and final research coordination meeting held in Rez, Czech Republic, 3-7 December 2007, and collected in this technical publication. Operating

  19. Cutting and decontamination technologies for nuclear facility dismantling; Technologien zur Zerlegung und zur Dekontamination von kerntechnischen Anlagen

    Energy Technology Data Exchange (ETDEWEB)

    Huebner, Felix; Grone, Georg von; Schultmann, Frank

    2017-03-15

    The German Government's decision to phase-out nuclear power will lead to a substantial increase of the number of nuclear decommissioning and dismantling projects. The decommissioning of nuclear facilities must meet the requirements of the radiation protection ordinance. This study deals with the decontamination and dismantling technologies available to meet radiation protection requirements. The aim of this study is to determine the state of the art in the field of decommissioning and dismantling technologies. Furthermore, future trends in the development and application of such technologies should be identified. A detailed study of current literature provides an overview of established decommissioning technologies. Moreover, experts were consulted in order to facilitate a practical assessment. The experts' statements indicate that (apart from the chemical decontamination of the primary circuit) the use of mechanical methods is generally preferred. Abrasive methods are rated as particularly efficient. According to the experts, the development of new decontamination technologies may allow a more efficient decontamination. However, the success of a new technology will be subject to its application costs. Mechanical technologies are preferred for the dismantling of nuclear facilities. The band saw has been identified as a standard tool in nuclear dismantling. The survey has concluded that there is no need for new dismantling technologies. The potential lies in the optimization of existing processes and techniques. With regard to remotely operated systems, experts' opinions vary on whether the use of these systems will increase in future. Most areas inside a nuclear facility have low radiation levels that allow the use of human labour for the dismantling. However, there is a need for an improvement in the allocation and management of decommissioning projects.

  20. Probabilistic risk assessment for back-end facilities: Improving the treatment of fire and explosion scenarios

    International Nuclear Information System (INIS)

    Sunman, C.R.J.; Campbell, R.J.; Wakem, M.J.

    1996-01-01

    The nuclear reprocessing facilities at Sellafield are a key component of the International business of BNFL. The operations carried out at the site extend from the receipt and storage of irradiated fuel, chemical reprocessing, plutonium and uranium finishing, through mixed oxide fuel production. Additionally there are a wide range of supporting processes including solid waste encapsulation, vitrification, liquid waste evaporation and treatment. Decommissioning of the site's older facilities is also proceeding. The comprehensive range of these activities requires that the safety assessment team keeps up to date with developments in the field, as well as conducting and sponsoring appropriate research into methodologies and modelling in order to deliver a cost effective, timely service. This paper will review the role of Probabilistic Risk Assessment (PRA) in safety cases for operations at Sellafield and go on to describe some areas of PRA methodology development in the UK and in which BNFL is a contributor. Finally the paper will summarise some specific areas of methodology development associated with improving the modelling of fire and explosion hazards which are specific to BNFL. (author)