WorldWideScience

Sample records for reactor-safety study radiological

  1. Critical review of the reactor-safety study radiological health effects model. Final report

    International Nuclear Information System (INIS)

    Cooper, D.W.; Evans, J.S.; Jacob, N.; Kase, K.R.; Maletskos, C.J.; Robertson, J.B.; Smith, D.G.

    1983-03-01

    This review of the radiological health effects models originally presented in the Reactor Safety Study (RSS) and currently used by the US Nuclear Regulatory Commission (NRC) was undertaken to assist the NRC in determining whether or not to revise the models and to aid in the revision, if undertaken. The models as presented in the RSS and as implemented in the CRAC (Calculations of Reactor Accident Consequences) Code are described and critiqued. The major elements analyzed are those concerning dosimetry, early effects, and late effects. The published comments on the models are summarized, as are the important findings since the publication of the RSS

  2. Critical review of the reactor-safety study radiological health effects model. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, D.W.; Evans, J.S.; Jacob, N.; Kase, K.R.; Maletskos, C.J.; Robertson, J.B.; Smith, D.G.

    1983-03-01

    This review of the radiological health effects models originally presented in the Reactor Safety Study (RSS) and currently used by the US Nuclear Regulatory Commission (NRC) was undertaken to assist the NRC in determining whether or not to revise the models and to aid in the revision, if undertaken. The models as presented in the RSS and as implemented in the CRAC (Calculations of Reactor Accident Consequences) Code are described and critiqued. The major elements analyzed are those concerning dosimetry, early effects, and late effects. The published comments on the models are summarized, as are the important findings since the publication of the RSS.

  3. Nordic studies in reactor safety

    International Nuclear Information System (INIS)

    Pershagen, N.

    1993-01-01

    The Nordic Nuclear Safety Research Programme SIK programme in reactor safety is part of a major joint Nordic research effort in nuclear safety. The report summarizes the achievements of the SIK programme, which was carried out during 1990-1993 in collaboration between Nordic nuclear utilities, safety authorities, and research institutes. Three main projects were successfully completed dealing with: 1) development and application of a living PSA concept for monitoring the risk of core damage, and of safety indicators for early warning of possible safety problems; 2) review and intercomparison of severe accident codes, case studies of potential core melt accidents in nordic reactors, development of chemical models for the MAAP code, and outline of a system for computerized accident management support; 3) compilation of information about design and safety features of neighbouring reactors in Germany, Lithuania and Russia, and for naval reactors and nuclear submarines. The report reviews the state-of-the-art in each subject matter as an introduction to the individual project summaries. The main findings of each project are highlighted. The report also contains an overview of reactor safety research in the Nordic countries and a summary of fundamental reactor safety principles. (au) (69 refs.)

  4. Fusion reactor safety studies, FY 1977

    International Nuclear Information System (INIS)

    Darby, J.B. Jr.

    1978-04-01

    This report reviews the technical progress in the fusion reactor safety studies performed during FY 1977 in the Fusion Power Program at the Argonne National Laboratory. The subjects reported on include safety considerations of the vacuum vessel and first-wall design for the ANL/EPR, the thermal responses of a tokamak reactor first wall, the vacuum wall electrical resistive requirements in relationship to magnet safety, and a major effort is reported on considerations and experiments on air detritiation

  5. The German reactor safety study

    International Nuclear Information System (INIS)

    Birkhofer, A.

    1980-01-01

    The most important results of the German risk study of a nuclear power plant equipped with a pressurized water reactor were published in August 1979. The main volume of the study with the approach used and the results elaborated has been available for reference since late 1979. Eight technical volumes contain detailed descriptions and documentations of the investigations carried out. The reference facility used as a basis for the technical plant studies was unit B of the Biblis Nuclear Power Station, a KWU PWR of 3750 MW thermal power. This contribution provides more detailed explanations of the methods and the results of the risk study illustrated by examples. The description refers to accident categories and categories of radioactivity releases, probabilities of specific sequences of accident events, and the damage associated with core meltdown accidents as a function of various types of failure. For purposes of evaluation and application of the results the limits in the basic assumptions of the study are referred to. (orig./HP) [de

  6. Acceptable risk in reactor safety studies

    International Nuclear Information System (INIS)

    Benjamin, J.R.; Shinozuka, M.; Shah, H.C.

    1975-01-01

    Acceptable risk is defined in terms of its five basic parameters: the hazard or problem; the probability of occurrence; the consequence; the possible alternative actions; and the value system of the community or the society. The problem of consistency in design at a site and between differing sites is discussed and solutions are suggested. Techniques for consistent deterministic and probabilistic setting limits and design standards are illustrated using data from AEC Reactor Safety Study, WASH-1400. The influence of level of consequence is discussed and a general methodology for decision analysis in resource allocation problem is briefly introduced and illustrated. The concept of acceptable risk is put in a quantitative format that can be used by engineers and planners. Bayesian statistical methods are introduced to develop the methodologies

  7. Overview of the reactor safety study consequence model

    International Nuclear Information System (INIS)

    Wall, I.B.; Yaniv, S.S.; Blond, R.M.; McGrath, P.E.; Church, H.W.; Wayland, J.R.

    1977-01-01

    The Reactor Safety Study (WASH-1400) is a comprehensive assessment of the potential risk to the public from accidents in light water power reactors. The engineering analysis of the plants is described in detail in the Reactor Safety Study: it provides an estimate of the probability versus magnitude of the release of radioactive material. The consequence model, which is the subject of this paper, describes the progression of the postulated accident after the release of the radioactive material from the containment. A brief discussion of the manner in which the consequence calculations are performed is presented. The emphasis in the description is on the models and data that differ significantly from those previously used for these types of assessments. The results of the risk calculations for 100 light water power reactors are summarized

  8. Reactor safety study applied to the Forsmark 3 Power Plant

    International Nuclear Information System (INIS)

    Ericsson, G.; Tiren, L.I.

    1978-01-01

    A reactor safety study of the Forsmark 3 BWR power plant has been carried out for the purpose of calculating core melt probabilities using WASH-1400 methods. A sensitivity analysis shows that the calculated core melt probability is changed by approximately a factor of 10 depending on assumptions made with respect to the probability of human error. The importance of the availability of off-site power and the influence of common cause failure is also discussed. (author)

  9. French studies and research program in pressurized water reactor safety

    International Nuclear Information System (INIS)

    Duco, J.

    1986-06-01

    The aim of researches developed now in France on water reactor safety is to obtain means and knowledge allowing to control accidental situations, including severe situations beyond design basis accidents. The main studies and researches concerning water reactors and described in this report are the following ones: core cooling accident and prevention of severe accidents, fuel behavior in accidental situation, behavior of the containment building, fission product transfer and releases in case of accident, problems related to equipment aging, and, methodology of risk analysis and ''human factor'' studies. Most of these studies follow an analytic approach of phenomena [fr

  10. Consequence model of the German reactor safety study

    International Nuclear Information System (INIS)

    Bayer, A.; Aldrich, D.; Burkart, K.; Horsch, F.; Hubschmann, W.; Schueckler, M.; Vogt, S.

    1979-01-01

    The consequency model developed for phase A of the German Reactor Safety Study (RSS) is similar in many respects to its counterpart in WASH-1400. As in that previous study, the model describes the atmosphere dispersion and transport of radioactive material released from the containment during a postulated reactor accident, and predicts its interaction with and influence on man. Differences do exist between the two models however, for the following reasons: (1) to more adequately reflect central European conditions, (2) to include improved submodels, and (3) to apply additional data and knowledge that have become available since publication of WASH-1400. The consequence model as used in phase A of the German RSS is described, highlighting differences between it and the U.S. model

  11. Reactor safety

    International Nuclear Information System (INIS)

    Butz, H.P.; Heuser, F.W.; May, H.

    1985-01-01

    The paper comprises an introduction into nuclear physics bases, the safety concept generally speaking, safety devices of pwr type reactors, accident analysis, external influences, probabilistic safety assessment and risk studies. It further describes operational experience, licensing procedures under the Atomic Energy Law, research in reactor safety and the nuclear fuel cycle. (DG) [de

  12. Sensitivity analysis of the reactor safety study. Final report

    International Nuclear Information System (INIS)

    Parkinson, W.J.; Rasmussen, N.C.; Hinkle, W.D.

    1979-01-01

    The Reactor Safety Study (RSS) or Wash 1400 developed a methodology estimating the public risk from light water nuclear reactors. In order to give further insights into this study, a sensitivity analysis has been performed to determine the significant contributors to risk for both the PWR and BWR. The sensitivity to variation of the point values of the failure probabilities reported in the RSS was determined for the safety systems identified therein, as well as for many of the generic classes from which individual failures contributed to system failures. Increasing as well as decreasing point values were considered. An analysis of the sensitivity to increasing uncertainty in system failure probabilities was also performed. The sensitivity parameters chosen were release category probabilities, core melt probability, and the risk parameters of early fatalities, latent cancers and total property damage. The latter three are adequate for describing all public risks identified in the RSS. The results indicate reductions of public risk by less than a factor of two for factor reductions in system or generic failure probabilities as high as one hundred. There also appears to be more benefit in monitoring the most sensitive systems to verify adherence to RSS failure rates than to backfitting present reactors. The sensitivity analysis results do indicate, however, possible benefits in reducing human error rates

  13. Study of fast reactor safety test facilities. Preliminary report

    International Nuclear Information System (INIS)

    Bell, G.I.; Boudreau, J.E.; McLaughlin, T.; Palmer, R.G.; Starkovich, V.; Stein, W.E.; Stevenson, M.G.; Yarnell, Y.L.

    1975-05-01

    Included are sections dealing with the following topics: (1) perspective and philosophy of fast reactor safety analysis; (2) status of accident analysis and experimental needs; (3) experiment and facility definitions; (4) existing in-pile facilities; (5) new facility options; and (6) data acquisition methods

  14. Reactor safety study. An assessment of accident risks in U.S. commercial nuclear power plants. Appendix XI. Analysis of comments on the draft WASH-1400 report

    International Nuclear Information System (INIS)

    1975-10-01

    Information is presented concerning comments on reactor safety by governmental agencies and civilian organizations; reactor safety study methodology; consequence model; probability of accident sequences; and various accident conditions

  15. Study on personnel qualification for non-destructive tests in the field of reactor safety

    International Nuclear Information System (INIS)

    Trusch, K.; Wuestenberg, H.

    1977-01-01

    The training system for non-destructive testing is described, and the available and necessary personnel is analyzed; the personnel required for reactor safety problems is treated separately. On this basis, the subjects discussed in the study - available personnel, personnel requirements, training, training requirements, and suggestions for realisation - are treated in a general manner to begin with and afterwards with a view to specific problems of reactor safety. The methods employed are adapted to this situation. To obtain the necessary empirical data, questionnaires were set up and distributed, and experts in selected business companies and institutions were interviewed who work in the field of reactor safety or do same training in non-destructive testing. (orig.) [de

  16. Review of light--water reactor safety studies. Volume 3 of health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California

    International Nuclear Information System (INIS)

    Nero, A.V.; Farnaam, M.R.K.

    1977-01-01

    This report summarizes and compares important studies of light-water nuclear reactor safety, emphasizing the Nuclear Regulatory Commission's Reactor Safety Study, work on risk assessment funded by the Electric Power Research Institute, and the Report of the American Physical Society study group on light-water reactor safety. These reports treat risk assessment for nuclear power plants and provide an introduction to the basic issues in reactor safety and the needs of the reactor safety research program. Earlier studies are treated more briefly. The report includes comments on the Reactor Safety Study. The manner in which these studies may be used and alterations which would increase their utility are discussed

  17. Meteorological aspects of the reactor safety study requiring further study

    International Nuclear Information System (INIS)

    Slinn, W.G.N.

    1981-01-01

    Simple and approximate methods are used in a search for meteorological features that dominate estimates of reactor-accident consequences, and that require more accurate descriptions if consequence estimates are to be more realistic. By considering variations in the source term, it is seen that accidents involving containment-vessel failure dominate both the mean and variance of the distribution of consequences, although this conclusion is subject to uncertainties about plume rise. Research is recommended on the behavior of horizontal, sonic jets, with heat transfer to the ground, and especially during stable atmospheric conditions. Diffusion with fumigation and lofting require further study; use of K-theory and National Weather Service data should be vigorously pursued. Conditional upon an accident occurring, precipitation scavenging appears to dominate the variance of the consequences

  18. Multi-channel grouping techniques for conducting reactor safety studies

    International Nuclear Information System (INIS)

    Waltar, A.E.; Wilburn, N.P.

    1975-01-01

    In conducting safety studies for postulated unprotected accidents in an LMFBR system, it is common practice to employ multi-channel coupled neutronics, thermal hydraulics computer programs such as SAS3A or MELT-III. The multichannel feature of such code systems is important if the natural fuel failure incoherencies and the resulting sodium void/fuel motion reactivity feedbacks--which have strong spatial variations--are to be properly modeled. Because of the large amounts of computer time associated with many channel runs, however, there is a strong incentive to conduct parametric studies with as few channels as possible. The paper presented is focused on methods successfully employed to accomplish this end for a study of the hypothetical unprotected transient overpower accident conducted for the FFTF

  19. Pilot Study on Harmonisation of Reactor Safety in WENRA Countries

    International Nuclear Information System (INIS)

    2003-03-01

    Most of the objectives, set for the Pilot Study, were met. It can be concluded that the methodology was adequate for its purpose. National requirements on selected safety issues have been systematically compared and the major gaps and differences have been identified. Convenient overviews have been provided of differences and similarities between the countries. Furthermore, the conclusions are based on a safety justification and are detailed enough to provide input to a further more detailed analysis on the national level. It was not possible, however, to provide fully verified conclusions about the implementation of the reference levels in the different countries. This has to do with the following constraints on the study: In line with the Terms of Reference, the comparison of formal requirements did not address the more detailed use of criteria and methods to verify compliance. The same requirement could be enforced differently in different regulatory systems, and hence lead to different implementation. The Pilot Study also assessed the implementation, but it was not possible to do this in sufficient detail to identify such differences. The implementation was assessed on the basis of current knowledge of the respective regulatory body, but it was not possible to provide the panels with evidence of the implementation. For these reasons, conclusions about implemented safety provisions in the different countries should be drawn with precaution. The introduction of the panel assessments greatly improved the quality and consistency of the comparison assessments. Uncertainties in the assessments are mainly connected with lack of time to make a detailed analysis in some cases. The reliability of the assessments seems to be sufficient for the objectives of the Pilot Study. The introduction of the IAEA safety standards in the study proved to be helpful and provided confidence in the scope and strictness of the reference levels. This Pilot Study has contributed to

  20. French study and research program on water cooled reactor safety

    International Nuclear Information System (INIS)

    Zammite, R.

    1985-05-01

    Electricite de France and the CEA (Commissariat a l'Energie Atomique), joined to obtain, in several fields, the knowledge and qualified calculation tools, they need to develop new means to face the potential consequences of accidents. The bringing on of an important number of PWR units in France in the eightys involves a focusing on these studies. The main fields concerned are the following ones: core cooling accidents and severe accident prevention; fuel behavior in case of accident; containment behavior in accidental situation; emission, transfer and release of fission products in case of accident; probabilistic risk analysis, human factor and earthquakes [fr

  1. Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Appendix XI. Analysis of comments on the draft WASH-1400 report. [PWR and BWR

    Energy Technology Data Exchange (ETDEWEB)

    1975-10-01

    Information is presented concerning comments on reactor safety by governmental agencies and civilian organizations; reactor safety study methodology; consequence model; probability of accident sequences; and various accident conditions.

  2. Reactor safety study. An assessment of accident risks in U.S. commercial nuclear power plants. Executive summary: main report

    International Nuclear Information System (INIS)

    1975-10-01

    Information is presented concerning the objectives and organization of the reactor safety study; the basic concepts of risk; the nature of nuclear power plant accidents; risk assessment methodology; reactor accident risk; and comparison of nuclear risks to other societal risks

  3. Reactor safety

    International Nuclear Information System (INIS)

    Meneley, D.A.

    The people of Ontario have begun to receive the benefits of a low cost, assured supply of electrical energy from CANDU nuclear stations. This indigenous energy source also has excellent safety characteristics. Safety has been one of the central themes of the CANDU development program from its very beginning. A great deal of work has been done to establish that public risks are small. However, safety design criteria are now undergoing extensive review, with a real prospect of more stringent requirements being applied in the future. Considering the newness of the technology it is not surprising that a consensus does not yet exist; this makes it imperative to discuss the issues. It is time to examine the policies and practice of reactor safety management in Canada to decide whether or not further restrictions are justified in the light of current knowledge

  4. Effects of wind shear on the consequence model of the reactor safety study

    International Nuclear Information System (INIS)

    Sprung, J.L.; Church, H.W.

    1977-01-01

    The effects of explicit incorporation of wind shear into the consequence model of the Reactor Safety study have been investigated. The integral of exposure (X/Q) over area is unchanged by directional shear and decreased by speed shear. Consequence model predictions of early fatalities are always decreased by wind shear. Where early fatalities are decreased, survivors are subject to latent effects and, therefore, latent effects increase. However, aggregate early fatalities and latent effects always are decreased. Because the magnitude of these changes is within the present uncertainties of the consequence model, explicit incorporation of wind shear in the consequence model is not now warranted

  5. Yellin's review of the Nuclear Regulatory Commission's Reactor Safety Study: comment

    International Nuclear Information System (INIS)

    Wilson, R.

    1976-01-01

    Joel Yellin (Bell J. Economics, Vol. 7, No. 1 (Spr. 1976)) reviewed the Reactor Safety Study (WASH-1400, or Rasmussen Report) published by the Nuclear Regulatory Commission and makes several criticisms. Wilson finds that some of these criticisms are much overstated, while others, although valid, are mainly criticisms of presentation. To be useful for public policy, reactor risks--and indeed all nuclear risks--must be compared with other risks society faces. Wilson feels that the Rasmussen Report is weak in these comparisons, primarily because there exist few estimates of risk in other places, but that the comparisons he does make indeed confirm that the risk is smaller than Yellin suggests. 20 references

  6. Investigations of the adequacy of the meteorological transport model developed for the reactor safety study

    International Nuclear Information System (INIS)

    Spring, J.L.; Brown, W.D.; Church, H.W.; McGrath, P.E.; Ritchie, L.T.; Russo, A.J.; Steck, G.P.; Wayland, J.R.; Blond, R.M.; Wall, I.B.

    1978-01-01

    A computer model (CRAC) was developed for the Reactor Safety Study (WASH-1400) [1] to estimate the consequences of postulated accidents at U.S. commercial nuclear power plants. One hundred reactors at 68 sites were included in the study. The 68 sites were divided into 6 classes according to their geographic location and meteorology. For each site class, a composite population distribution was constructed from the true population distributions at each of the sites comprising that class, and a reference site was chosen for which a full year of meteorological data (wind speed, atmospheric stability, occurrence of rain) was obtained. Given data about a postulated accident (probability, amounts of the released radionuclides, etc.) and the reference reactor site (meteorology, composite population, land usage), CRAC was used to calculate the atmospheric dispersion and ground deposition of the released radionuclides (Gaussian plume submodel) and the health effects (dosimetric and dose response submodels) and costs (land interdiction and decontamination submodel) resulting from their release. The Gaussian plume model used in CRAC either did not treat or treated simplistically a number of meteorological phenomena. Simplified models were used to treat plume rise, inversion layers, and rainstorms, while wind shear, wind direction, and correlations between wind fields and population distributions were not treated at all. Some of the effects of all of these phenomena on predictions of accident consequences as calculated using CRAC have been or are being investigated. The results of these studies are summarized

  7. Sensitivity of risk parameters to human errors in reactor safety study for a PWR

    International Nuclear Information System (INIS)

    Samanta, P.K.; Hall, R.E.; Swoboda, A.L.

    1981-01-01

    Sensitivities of the risk parameters, emergency safety system unavailabilities, accident sequence probabilities, release category probabilities and core melt probability were investigated for changes in the human error rates within the general methodological framework of the Reactor Safety Study (RSS) for a Pressurized Water Reactor (PWR). Impact of individual human errors were assessed both in terms of their structural importance to core melt and reliability importance on core melt probability. The Human Error Sensitivity Assessment of a PWR (HESAP) computer code was written for the purpose of this study. The code employed point estimate approach and ignored the smoothing technique applied in RSS. It computed the point estimates for the system unavailabilities from the median values of the component failure rates and proceeded in terms of point values to obtain the point estimates for the accident sequence probabilities, core melt probability, and release category probabilities. The sensitivity measure used was the ratio of the top event probability before and after the perturbation of the constituent events. Core melt probability per reactor year showed significant increase with the increase in the human error rates, but did not show similar decrease with the decrease in the human error rates due to the dominance of the hardware failures. When the Minimum Human Error Rate (M.H.E.R.) used is increased to 10 -3 , the base case human error rates start sensitivity to human errors. This effort now allows the evaluation of new error rate data along with proposed changes in the man machine interface

  8. The DRAGON aerosol research facility to study aerosol behaviour for reactor safety applications

    International Nuclear Information System (INIS)

    Suckow, Detlef; Guentay, Salih

    2008-01-01

    During a severe accident in a nuclear power plant fission products are expected to be released in form of aerosol particles and droplets. To study the behaviour of safety relevant reactor components under aerosol loads and prototypical severe accident conditions the multi-purpose aerosol generation facility DRAGON is used since 1994 for several projects. DRAGON can generate aerosol particles by the evaporation-condensation technique using a plasma torch system, fluidized bed and atomization of particles suspended in a liquid. Soluble, hygroscopic aerosol (i.e. CsOH) and insoluble aerosol particles (i.e. SnO 2 , TiO 2 ) or mixtures of them can be used. DRAGON uses state-of-the-art thermal-hydraulic, data acquisition and aerosol measurement techniques and is mainly composed of a mixing chamber, the plasma torch system, a steam generator, nitrogen gas and compressed air delivery systems, several aerosol delivery piping, gas heaters and several auxiliary systems to provide vacuum, coolant and off-gas treatment. The facility can be operated at system pressure of 5 bars, temperatures of 300 deg. C, flow rates of non-condensable gas of 900 kg/h and steam of 270 kg/h, respectively. A test section under investigation is attached to DRAGON. The paper summarizes and demonstrates with the help of two project examples the capabilities of DRAGON for reactor safety studies. (authors)

  9. The Use Of High Speed Photography In Reactor Safety Studies At The Atomic Energy Establishment, Winfrith

    Science.gov (United States)

    Maddison, R. J.

    1985-02-01

    The investigation of certain areas of nuclear reactor safety involves the study of high speed phenomena with timescales ranging from microseconds to a few hundreds of milliseconds. Examples which have been extensively studied at Winfrith are firstly, the thermal interaction of molten fuel and reactor coolant which can generate high pressures on the 100 msec timescale, and which involves phenomena such as vapour film collapse which takes place on the microsecond timescale. Secondly, there is the response of reactor structures to such pressures, and finally there is the response of structural materials such as metals and concrete to the impulsive loading arising from the impact of heavy, high velocity missiles. A wide range of experimental techniques is used in these studies, many of which have been developed specially for this type of work which ranges from small laboratory scale to large field scale experiments. There are two important features which characterise many of these experiments:- i) a long period of meticulous preparation of very heavily instrumented, short duration experiments and; ii) the destructive nature of the experiments. Various forms of High Speed photography are included in the inventory of experimental techniques. These include the use of single and double exposure, short duration, spark photography; the use of an Image Convertor Camera (IMACON 790); and a number of rotating prism cine cameras. High Speed Photography is used both in a primary experimental role in the studies, and in a supportive role for other instrumentation. Because of the sometimes violent nature of these experiments, cameras are often heavily protected and operated remotely; lighting systems are sometimes destroyed. This has led to the development of unconventional techniques for camera operation and subject lighting. This paper will describe some of the experiments and the way in which High Speed Photography has been applied as an essential experimental tool. It will be

  10. Reactor safety study. An assessment of accident risks in U.S. commercial nuclear power plants. Appendix I. Accident definition and use of event trees

    International Nuclear Information System (INIS)

    1975-10-01

    Information is presented concerning accident definition and use of event trees, event tree methodology, potential accidents covered by the reactor safety study, analysis of potential accidents involving the reactor core, and analysis of potential accidents not involving the core

  11. Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Executive summary: main report. [PWR and BWR

    Energy Technology Data Exchange (ETDEWEB)

    1975-10-01

    Information is presented concerning the objectives and organization of the reactor safety study; the basic concepts of risk; the nature of nuclear power plant accidents; risk assessment methodology; reactor accident risk; and comparison of nuclear risks to other societal risks.

  12. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    Arien, B.

    2000-01-01

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of two main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents. Main achievements in 1999 are reported

  13. Fusion reactor safety

    International Nuclear Information System (INIS)

    1987-12-01

    Nuclear fusion could soon become a viable energy source. Work in plasma physics, fusion technology and fusion safety is progressing rapidly in a number of Member States and international collaboration continues on work aiming at the demonstration of fusion power generation. Safety of fusion reactors and technological and radiological aspects of waste management are important aspects in the development and design of fusion machines. In order to provide an international forum to review and discuss the status and the progress made since 1983 in programmes related to operational safety aspects of fusion reactors, their waste management and decommissioning concepts, the IAEA had organized the Technical Committee on ''Fusion Reactor Safety'' in Culham, 3-7 November 1986. All presentations of this meeting were divided into four sessions: 1. Statements on National-International Fusion Safety Programmes (5 papers); 2. Operation and System Safety (15 papers); 3. Waste Management and Decommissioning (5 papers); 4. Environmental Impacts (6 papers). A separate abstract was prepared for each of these 31 papers. Refs, figs, tabs

  14. Problems of nuclear reactor safety. Vol. 1

    International Nuclear Information System (INIS)

    Shal'nov, A.V.

    1995-01-01

    Proceedings of the 9. Topical Meeting 'Problems of nuclear reactor safety' are presented. Papers include results of studies and developments associated with methods of calculation and complex computerized simulation for stationary and transient processes in nuclear power plants. Main problems of reactor safety are discussed as well as rector accidents on operating NPP's are analyzed

  15. Overview of the NKS/RAK-1 project 'Strategies for reactor safety' and linkages to piping reliability studies

    International Nuclear Information System (INIS)

    Andersson, Kjell

    1997-01-01

    The NKS/RAK-1 project forms part of a four-year research program (1994-97) in the Nordic countries. The general objective of NKS/RAK-1 project is to explore strategies for reactor safety: to investigate and evaluate the safety work, to increase realism and reliability of safety analysis; and to increase the safety of nuclear installations in selected areas. The project has done extensive interview work at utilities and authorities, and analysed a number of case studies. Brief highlights and overviews of the sub-projects are presented in this paper

  16. High-temperature gas-cooled reactor safety studies. Progress report for January 1, 1974--June 30, 1975

    International Nuclear Information System (INIS)

    Cole, T.E.; Sanders, J.P.; Kasten, P.R.

    1977-07-01

    Progress is reported in the following areas: systems and safety analysis; fission product technology; primary coolant technology; seismic and vibration technology; confinement components; primary system materials technology; safety instrumentation; loss of flow accident analysis using HEATUP code; use of coupled-conduction-convection model for core thermal analysis; development of multichannel conduction-convection program HEXEREI; cooling system performance after shutdown; core auxiliary cooling system performance; development of FLODIS code; air ingress into primary systems following DBDA; performance of PCRV thermal barrier cover plates; temperature limits for fuel particle coating failure; tritium distribution and release in HTGR; energy release to PCRV during DBDA; and mathematical models for HTGR reactor safety studies

  17. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    Arien, B.

    1998-01-01

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of four main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents, the development of an expert system for the aid to diagnosis; the development and application of a probabilistic reactor dynamics method. Main achievements in 1999 are reported

  18. Cost benefit analysis of reactor safety systems

    International Nuclear Information System (INIS)

    Maurer, H.A.

    1984-01-01

    Cost/benefit analysis of reactor safety systems is a possibility appropriate to deal with reactor safety. The Commission of the European Communities supported a study on the cost-benefit or cost effectiveness of safety systems installed in modern PWR nuclear power plants. The following systems and their cooperation in emergency cases were in particular investigated in this study: the containment system (double containment), the leakage exhaust and control system, the annulus release exhaust system and the containment spray system. The benefit of a safety system is defined according to its contribution to the reduction of the radiological consequences for the environment after a LOCA. The analysis is so far performed in two different steps: the emergency core cooling system is considered to function properly, failure of the emergency core cooling system is assumed (with the possible consequence of core melt-down) and the results may demonstrate the evidence that striving for cost-effectiveness can produce a safer end result than the philosophy of safety at any cost. (orig.)

  19. Reactor Safety Assessment System

    International Nuclear Information System (INIS)

    Sebo, D.E.; Bray, M.A.; King, M.A.

    1987-01-01

    The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (USNRC). RSAS is designed for use at the USNRC Operations Center in the event of a serious incident at a licensed nuclear power plant. RSAS is a situation assessment expert system which uses plant parametric data to generate conclusions for use by the NRC Reactor Safety Team. RSAS uses multiple rule bases and plant specific setpoint files to be applicable to all licensed nuclear power plants in the United States. RSAS currently covers several generic reactor categories and multiple plants within each category

  20. Reactor safety assessment system

    International Nuclear Information System (INIS)

    Sebo, D.E.; Bray, M.A.; King, M.A.

    1987-01-01

    The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (USNRC). RSA is designed for use at the USNRC Operations Center in the event of a serious incident at a licensed nuclear power plant. RSAS is a situation assessment expert system which uses plant parametric data to generate conclusions for use by the NRC Reactor Safety Team. RSAS uses multiple rule bases and plant specific setpoint files to be applicable to all licensed nuclear power plants in the United States. RSAS currently covers several generic reactor categories and multiple plants within each category

  1. Research for enhancing reactor safety

    International Nuclear Information System (INIS)

    1989-05-01

    Recent research for enhanced reactor safety covers extensive and numerous experiments and computed modelling activities designed to verify and to improve existing design requirements. The lectures presented at the meeting report GRS research results and the current status of reactor safety research in France. The GRS experts present results concerning expert systems and their perspectives in safety engineering, large-scale experiments and their significance in the development and verification of computer codes for thermohydraulic modelling of safety-related incidents, the advanced system code ATHLET for analysis of thermohydraulic processes of incidents, the analysis simulator which is a tool for fast evaluation of accident management measures, and investigations into event sequences and the required preventive emergency measures within the German Risk Study. (DG) [de

  2. Reactor safety analysis

    International Nuclear Information System (INIS)

    Arien, B.

    1998-01-01

    Risk assessments of nuclear installations require accurate safety and reliability analyses to estimate the consequences of accidental events and their probability of occurrence. The objective of the work performed in this field at the Belgian Nuclear Research Centre SCK-CEN is to develop expertise in probabilistic and deterministic reactor safety analysis. The four main activities of the research project on reactor safety analysis are: (1) the development of software for the reliable analysis of large systems; (2) the development of an expert system for the aid to diagnosis; (3) the development and the application of a probabilistic reactor-dynamics method, and (4) to participate in the international PHEBUS-FP programme for severe accidents. Progress in research during 1997 is described

  3. Reactor safety study. An assessment of accident risks in U.S. commercial nuclear power plants. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1975-10-01

    The Reactor Safety Study was sponsored by the U. S. Atomic Energy Commission to estimate the public risks that could be involved in potential accidents in commercial nuclear power plants of the type now in use. It was performed under the independent direction of Professor Norman C. Rasmussen of the Massachusetts Institute of Technology. The risks had to be estimated, rather than measured, because although there are about 50 such plants now operating, there have been no nuclear accidents to date resulting in significant releases of radioactivity in U.S. commercial nuclear power plants. The objective of the study was to make a realistic estimate of these risks and, to provide perspective, to compare them with non-nuclear risks to which our society and its individuals are already exposed. This information may be of help in determining the future reliance by society on nuclear power as a source of electricity. The results from this study suggest that the risks to the public from potential accidents in nuclear power plants are comparatively small.

  4. Reactor safety study. An assessment of accident risks in U.S. commercial nuclear power plants. Executive summary

    International Nuclear Information System (INIS)

    1975-10-01

    The Reactor Safety Study was sponsored by the U. S. Atomic Energy Commission to estimate the public risks that could be involved in potential accidents in commercial nuclear power plants of the type now in use. It was performed under the independent direction of Professor Norman C. Rasmussen of the Massachusetts Institute of Technology. The risks had to be estimated, rather than measured, because although there are about 50 such plants now operating, there have been no nuclear accidents to date resulting in significant releases of radioactivity in U.S. commercial nuclear power plants. The objective of the study was to make a realistic estimate of these risks and, to provide perspective, to compare them with non-nuclear risks to which our society and its individuals are already exposed. This information may be of help in determining the future reliance by society on nuclear power as a source of electricity. The results from this study suggest that the risks to the public from potential accidents in nuclear power plants are comparatively small

  5. Space reactor safety, 1985--1995 lessons learned

    International Nuclear Information System (INIS)

    Marshall, A.C.

    1995-01-01

    Space reactor safety activities and decisions have evolved over the last decade. Important safety decisions have been made in the SP-100, Space Exploration Initiative, NEPSTP, SNTP, and Bimodal Space Reactor programs. In addition, international guidance on space reactor safety has been instituted. Space reactor safety decisions and practices have developed in the areas of inadvertent criticality, reentry, radiological release, orbital operation, programmatic, and policy. In general, the lessons learned point out the importance of carefully reviewing previous safety practices for appropriateness to space nuclear programs in general and to the specific mission under consideration

  6. Space reactor safety, 1985--1995 lessons learned

    Energy Technology Data Exchange (ETDEWEB)

    Marshall, A.C.

    1995-12-31

    Space reactor safety activities and decisions have evolved over the last decade. Important safety decisions have been made in the SP-100, Space Exploration Initiative, NEPSTP, SNTP, and Bimodal Space Reactor programs. In addition, international guidance on space reactor safety has been instituted. Space reactor safety decisions and practices have developed in the areas of inadvertent criticality, reentry, radiological release, orbital operation, programmatic, and policy. In general, the lessons learned point out the importance of carefully reviewing previous safety practices for appropriateness to space nuclear programs in general and to the specific mission under consideration.

  7. New perspectives on reactor safety

    International Nuclear Information System (INIS)

    Avery, R.

    1986-01-01

    Over the past few years a number of changes and new perspectives have come about in our approach to reactor safety. These changes have occurred over a period of time extending from as long ago as 1975, when WASH-1400 came out representing the first major application of probabilistic risk analysis (PRA) to US reactor plants. The period of change has extended from that time to the present, and includes new areas of focus such as safety goals, source term studies, and severe accident policy statement and approaches, including the IDCOR Program. It has also included a greatly increased interest in inherent safety. These areas are discussed in this paper

  8. Light water reactor safety

    CERN Document Server

    Pershagen, B

    2013-01-01

    This book describes the principles and practices of reactor safety as applied to the design, regulation and operation of light water reactors, combining a historical approach with an up-to-date account of the safety, technology and operating experience of both pressurized water reactors and boiling water reactors. The introductory chapters set out the basic facts upon which the safety of light water reactors depend. The central section is devoted to the methods and results of safety analysis. The accidents at Three Mile Island and Chernobyl are reviewed and their implications for light wate

  9. Perspectives on reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States)

    1994-03-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  10. Perspectives on reactor safety

    International Nuclear Information System (INIS)

    Haskin, F.E.

    1994-03-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

  11. Study of In-Pile test facility for fast reactor safety research: performance requirements and design features

    Energy Technology Data Exchange (ETDEWEB)

    Nonaka, N.; Kawatta, N.; Niwa, H.; Kondo, S.; Maeda, K

    1996-12-31

    This paper describes a program and the main design features of a new in-pile safety facility SERAPH planned for future fast reactor safety research. The current status of R and D on technical developments in relation to the research objectives and performance requirements to the facility design is given.

  12. Light-water reactors. Safety problems and related studies in France

    International Nuclear Information System (INIS)

    Lelievre, J.

    1975-01-01

    The program of theoretical and experimental studies developed by the CEA on the safety of PWR reactors is presented: studies relative to the consequences of a LOCA following a rupture of the primary system, studies relative to fuel element behavior, studies on steels, reliability studies and studies of non-destructive testing methods [fr

  13. Reactor safety research in Sweden

    International Nuclear Information System (INIS)

    Pershagen, B.

    1980-02-01

    Objectives, means and results of Swedish light water reactor safety research during the 1970s are reviewed. The expenditure is about 40 Million Swkr per year excluding industry. Large efforts have been devoted to experimental studies of loss of coolant accidents. Large scale containment response tests for simulated pipe breaks were carried out at the Marviken facility. At Studsvik a method for testing fuel during fast power changes has been developed. Stress corrosion, crack growth and the effect of irradiation on the strength ductility of Zircaloy tube was studied. A method for determining the fracture toughness of pressure vessel steel was developed and it was shown that the fracture toughness was lower than earlier assumed. The release of fission products to reactor water was studied and so was the release, transport and removal of airborne radioactive matter for Swedish BWRs and PWRs. Test methods for iodine filter systems were developed. A system for continuous monitoring of radioactive noble gas stack release was developed for the Ringhals plant. Attention was drawn to the importance of the human factor for reactor safety. Probabilistic methods for risk analysis were applied to the Barsebaeck 2 and Forsmark 3 boiling water reactors. Procedures and working conditions for operator personnel were investigated. (GBn)

  14. Review of the American Physical Society light water reactor safety study

    International Nuclear Information System (INIS)

    Budnitz, R.J.

    1975-11-01

    The issue of light-water reactor (LWR) safety has been the subject of a part-time, year-long study sponsored by the American Physical Society and supported by the National Science Foundation and the former Atomic Energy Commission. The 1974-1975 study produced a Report by the Study Group to the Society. The Report's ''Summary of Conclusions and Major Recommendations'' section is presented

  15. Forced convection boiling of sodium. Study carried out in the framework of fast neutrons reactors safety

    International Nuclear Information System (INIS)

    Charlety, Paul

    1971-01-01

    Within the framework of the safety of fast neutron reactors, this research thesis reports the study of sodium boiling in order to assess safety margins, and to predict the consequences of some accidents. The author thus addresses issues related to sodium boiling by notably focussing on boiling physics. He first defines these issues and presents the adopted approach for this research, and then describes the experimental installation. He reports the experimental study which comprised different types of tests, and presents experimental results. He reports the development of a calculation model which could report phenomena which have been experimentally noticed [fr

  16. The reactor safety study of experimental multi-purpose VHTR design

    International Nuclear Information System (INIS)

    Yasuno, T.; Mitake, S.; Ezaki, M.; Suzuki, K.

    1981-01-01

    Over the past years, the design works of the Experimental Very High Temperature Reactor (VHTR) plant have been conducted at Japan Atomic Energy Research Institute. The conceptual design has been completed and the more detailed design works and the safety analysis of the experimental VHTR plant are continued. The purposes of design studies are to show the feasibility of the experimental VHTR program, to specify the characteristics and functions of the plant components, to point out the R and D items necessary for the experimental VHTR plant construction, and to analyze the feature of the plant safety. In this paper the summary of system design and safety features of the experimental reactor are indicated. Main issues are the safety philosophy for the design basis accident, the accidents assumed and the engineered safety systems adopted in the design works

  17. Evaluation of reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-04-15

    Although the operation of nuclear reactors has a remarkably good record of safety, the prevention of possible reactor accidents is one of the major factors that atomic planners have to contend with. At the same time, excessive caution may breed an attitude that hampers progress, either by resisting new development or by demanding unnecessarily elaborate and expensive precautions out of proportion to the actual hazards involved. The best course obviously is to determine the possible dangers and adopt adequate measures for their prevention, providing of course, for a reasonable margin of error in judging the hazards and the effectiveness of the measures. The greater the expert understanding and thoroughness with which this is done, the narrower need the margin be. This is the basic idea behind the evaluation of reactor safety

  18. Aspects of nuclear reactor safety

    International Nuclear Information System (INIS)

    Hardt, P. von der; Rottger, H.

    1980-01-01

    The Colloquium on 'Irradiation Tests for Reactor Safety Programmes' has been organised by JRC Petten in order to determine the present state of technology in the field. The role of research and test reactors for studies of structural material and fuel elements under transient and off-normal conditions was to be explained. The Colloquium has been attended by 110 participants from outside and inside Europe. 27 papers were presented covering the major ongoing projects in Japan, the United States, and in Europe, and elaborating in particular: - design rationale and layout of safety irradiation experiments; - design, manufacture, and performance of irradiation equipment with particular attention to generation and control of transient conditions, fast response in-pile instrumentation and its out-of-pile data retrieval; - post-irradiation evaluation; - results and analytical support

  19. SRP reactor safety evolution

    International Nuclear Information System (INIS)

    Rankin, D.B.

    1984-01-01

    The Savannah River Plant reactors have operated for over 100 reactor years without an incident of significant consequence to on or off-site personnel. The reactor safety posture incorporates a conservative, failure-tolerant design; extensive administrative controls carried out through detailed operating and emergency written procedures; and multiple engineered safety systems backed by comprehensive safety analyses, adapting through the years as operating experience, changes in reactor operational modes, equipment modernization, and experience in the nuclear power industry suggested. Independent technical reviews and audits as well as a strong organizational structure also contribute to the defense-in-depth safety posture. A complete review of safety history would discuss all of the above contributors and the interplay of roles. This report, however, is limited to evolution of the engineered safety features and some of the supporting analyses. The discussion of safety history is divided into finite periods of operating history for preservation of historical perspective and ease of understanding by the reader. Programs in progress are also included. The accident at Three Mile Island was assessed for its safety implications to SRP operation. Resulting recommendations and their current status are discussed separately at the end of the report. 16 refs., 3 figs

  20. Space nuclear reactor safety

    International Nuclear Information System (INIS)

    Damon, D.; Temme, M.; Brown, N.

    1990-01-01

    Definition of safety requirements and design features of the SP-100 space reactor power system has been guided by a mission risk analysis. The analysis quantifies risk from accidental radiological consequences for a reference mission. Results show that the radiological risk from a space reactor can be made very low. The total mission risk from radiological consequences for a shuttle-launched, earth orbit SP-100 mission is estimated to be 0.05 Person-REM (expected values) based on a 1 mREM/yr de Minimus dose. Results are given for each mission phase. The safety benefits of specific design features are evaluated through risk sensitivity analyses

  1. 1982 annual status report: reactor safety

    International Nuclear Information System (INIS)

    1982-01-01

    This report presents the projects of the Reactor Safety Program at the JRC: 1) Reliability and risk evolution; 2) LWR loss of coolant accident studies; 3) Primary system integrity; 4) LMFBR core accident initiation and transition phase; and, 5) LMFBR accident post disassembly phase

  2. The dual face of reactor safety

    International Nuclear Information System (INIS)

    Merz, L.

    1981-01-01

    Reactor safety is nowadays treated theoretically by a probabilistic approach. This means that events which may lead to accidents are considered as random events, and probability calculus is employed to predict potential damage. However, it has been found in practice that there are also failures in no way connected with chance, i.e., the so-called deterministic ones. This lends a dual face to reactor safety, a probabilistic and a deterministic one. In this contribution, the author resumes studies he had once initiated under the heading of Deterministic and Probabilistic Theses on Reactor Safety. He examines the present state of reactor safety under the aspect of deterministic and probabilistic failures and the significance of active and passive safety systems, estimating whether and to what extent earlier proposals have been incorporated in present technology. The two most prominent studies dealing with the risk of nuclear power plants, the American Rasmussen Study, WASH 1400, and the German Risk Study, were calculated by the most recent probabilistic methods. The causes of deterministic failures can be traced back to deterministic errors. There are errors in planning, in design, in fabrication, errors caused by maloperation, premature aging, sabotage and war. Since they are due to certain causes, it is possible in principle to discover and control them already by mental experiments. (orig./HP) [de

  3. Reactor safety research. The CEC contribution

    International Nuclear Information System (INIS)

    Krischer, W.

    1990-01-01

    The involvement of the EC Commission in the reactor safety research dates back almost to the implementation of the EURATOM Treaty and has thus lasted for thirty years. The need for close collaboration and for general consensus on some crucial problems of concern to the public, has made the role of international organizations and, as far as Europe is concerned, the role of the European Community particularly important. The areas in which the CEC has been active during the last five years are widespread. This is partly due to the fact that, after TMI and Chernobyl, the effort and the interest of the different countries in reactor safety was considerable. Reactor Safety Research represents the proceedings of a seminar held by the Commission at the end of its research programme 1984-88 on reactor safety. As such it gives a comprehensive overview of the recent activities and main results achieved in the CEC Joint Research Centre and in national laboratories throughout Europe on the basis of shared cost actions. In a concluding chapter the book reports on the opinions, expressed during a panel by a group of major exponents, on the needs for future research. The main topics addressed are, with particular reference to Light Water Reactors (LWRS): reliability and risk evaluation, inspection of steel components, primary circuit components end-of-life prediction, and abnormal behaviour of reactor cooling systems. As far as LMFBRs are concerned, the topics covered are: severe accident modelling, material properties and structural behaviour studies. There are 67 pages, all of which are indexed separately. Reactor Safety Research will be of particular interest to reliability and safety engineers, nuclear engineers and technicians, and mechanical and structural engineers. (author)

  4. A review of the radiological safety of the ISIS accelerator - A paper prepared for the advanced reactor safety topical meeting, Orlando, Florida (USA) June 1997

    International Nuclear Information System (INIS)

    Wright, P.

    1997-01-01

    This paper describes the current radiological safety aspects of operation of ISIS accelerator components and spallation targets. Improvements in the design of a new facility with higher power are also suggested for each main component. General comments on the regulatory and organisational aspects are made. Regulation is by European Union and British Legislation. Specific ISIS components described are the ion source, linear accelerator, synchrotron, target station, experimental beam lines and radioactive materials stores. The reliability of tantalum and uranium targets is discussed. Environmental discharges of tritium and other nuclides can become a limiting factor in accelerator operation. Methods of discharge monitoring at ISIS are explained and suggestions for improvements are outlined. Waste accumulation, associated doses and costs are described. 3 refs

  5. An approach to the verification of a fault-tolerant, computer-based reactor safety system: A case study using automated reasoning: Volume 1: Interim report

    International Nuclear Information System (INIS)

    Chisholm, G.H.; Kljaich, J.; Smith, B.T.; Wojcik, A.S.

    1987-01-01

    The purpose of this project is to explore the feasibility of automating the verification process for computer systems. The intent is to demonstrate that both the software and hardware that comprise the system meet specified availability and reliability criteria, that is, total design analysis. The approach to automation is based upon the use of Automated Reasoning Software developed at Argonne National Laboratory. This approach is herein referred to as formal analysis and is based on previous work on the formal verification of digital hardware designs. Formal analysis represents a rigorous evaluation which is appropriate for system acceptance in critical applications, such as a Reactor Safety System (RSS). This report describes a formal analysis technique in the context of a case study, that is, demonstrates the feasibility of applying formal analysis via application. The case study described is based on the Reactor Safety System (RSS) for the Experimental Breeder Reactor-II (EBR-II). This is a system where high reliability and availability are tantamount to safety. The conceptual design for this case study incorporates a Fault-Tolerant Processor (FTP) for the computer environment. An FTP is a computer which has the ability to produce correct results even in the presence of any single fault. This technology was selected as it provides a computer-based equivalent to the traditional analog based RSSs. This provides a more conservative design constraint than that imposed by the IEEE Standard, Criteria For Protection Systems For Nuclear Power Generating Stations (ANSI N42.7-1972)

  6. Nuclear reactor safety in the USA

    International Nuclear Information System (INIS)

    Vigil, J.C.

    1983-01-01

    Nuclear reactor safety in the USA has emphasized a defense-in-depth approach to protecting the public from reactor accidents. This approach was severely tested by the Three Mile Island accident and was found to be effective in safeguarding the public health and safety. However, the economic impact of the TMI accident was very large. Consequently, more attention is now being given to plant protection as well as public-health protection in reactor-safety studies. Sophisticated computer simulations at Los Alamos are making major contributions in this area. In terms of public risk, nuclear power plants compare favorably with other large-scale alternatives to electricity generation. Unfortunately, there is a large gulf between the real risks of nuclear power and the present public perception of these risks

  7. Meeting on reactor safety research

    International Nuclear Information System (INIS)

    1982-09-01

    The meeting 'Reactor Safety Research' organized for the second time by the GRS by order of the BMFT gave a review of research activities on the safety of light water reactors in the Federal Repulbic of Germany, international co-operation in this field and latest results of this research institution. The central fields of interest were subjects of man/machine-interaction, operational reliability accident sequences, and risk. (orig.) [de

  8. Nuclear reactor safety

    International Nuclear Information System (INIS)

    Buhl, A.R.

    1979-01-01

    Dr. Buhl feels that nuclear-energy issues are too complex to be understood as single topics, and can only be understood in relationship to broader issues. In fact, goals and risks associated with all energy options must be seen as interrelated with other broad issues, and it should be understood that there are presently no clearcut criteria to ensure that the best decisions are made. The technical community is responsible for helping the public to understand the basic incompatibility of hard and soft technologies and that there is no risk-free energy source. Four principles are outlined for assessing the risks of various energy technologies: (1) take a holistic view; (2) compare the risk with the unit energy output; (3) compare the risk with those of everyday activities; and (4) identify unusual risks associated with a particular option. Dr. Buhl refers to the study conducted by Dr. Inhaber of Canada who used this approach and concluded that nuclear power and natural gas have the lowest overall risk

  9. RB research reactor Safety Report

    International Nuclear Information System (INIS)

    Sotic, O.; Pesic, M.; Vranic, S.

    1979-04-01

    This RB reactor safety report is a revised and improved version of the Safety report written in 1962. It contains descriptions of: reactor building, reactor hall, control room, laboratories, reactor components, reactor control system, heavy water loop, neutron source, safety system, dosimetry system, alarm system, neutron converter, experimental channels. Safety aspects of the reactor operation include analyses of accident causes, errors during operation, measures for preventing uncontrolled activity changes, analysis of the maximum possible accident in case of different core configurations with natural uranium, slightly and highly enriched fuel; influence of possible seismic events

  10. The Dutch debate on reactor safety

    International Nuclear Information System (INIS)

    Aldenkamp, F.; Biesiot, W.; Geerts, H.M.; Nienhuys, K.; Soppe, W.

    1986-06-01

    A survey is presented of the discussion on location sites for nuclear power plants in the Netherlands and the USA. It consists of two parts (A and B). This part (A) presents a summary of the discussion in the Netherlands. The name and contents of the reports which have been published are indicated briefly. Many of the Dutch reports refer to American studies on reactor safety. In order to obtain a good survey of these a description is presented of the development of the discussion in the USA after the publication of the well-known reactor safety study WASH-1400. After this survey of five important reports, an introduction is presented dealing with the background of the authors, the purposes, the main conclusions and the most salient points of criticism formulated by others. Under discussion are the reports of the IDCOR (nuclear power industry), ANS (American Nuclear Society), APS (American Physical Society), NRC (Nuclear Regulatory Commission) and UCS (Union of Concerned Scientists). 38 refs.; 5 figs.; 5 tabs

  11. Radiological studies on Egyptian mummies

    International Nuclear Information System (INIS)

    Pahl, W.M.

    1982-01-01

    The goal of this work as part of a mummy study project is to obtain the maximum amount of information through radiological methods with the minimum destruction of the object. For this proven radiological methods were used as well as conventional radiological methods which had not yet been used with mummy research and modern radiological methods using an electronic basis relative to their importance for the study of medical archaeological materials. It is shown that the knowledge which is gained from the use of a combination of classical radiological methods and computed tomography cannot be enhanced by an autopsy of the study objects. Since because of this the objects can be kept in their original condition, a later checking of the results is guaranteed with the possibility of clearing up remaining open questions by means of further developed methods. (orig.) [de

  12. Nuclear power reactors: reactor safety and military and civil defence

    International Nuclear Information System (INIS)

    Hvinden, T.

    1976-01-01

    The formation of fission products and plutonium in reactors is briefly described, followed by a short general discussion of reactor safety. The interaction of reactor safety and radioactive release considerations with military and civil defence is thereafter discussed. Reactors and other nuclear plants are factors which must be taken into account in the defence of the district around the site, and as potential targets of both conventional and guerilla attacks and sabotage, requiring special defence. The radiological hazards arising from serious damage to a power reactor by conventional weapons are briefly discussed, and the benefits of underground siting evaluated. Finally the author discusses the significance of the IAEA safeguards work as a preventive factor. (JIW)

  13. Verification of reactor safety codes

    International Nuclear Information System (INIS)

    Murley, T.E.

    1978-01-01

    The safety evaluation of nuclear power plants requires the investigation of wide range of potential accidents that could be postulated to occur. Many of these accidents deal with phenomena that are outside the range of normal engineering experience. Because of the expense and difficulty of full scale tests covering the complete range of accident conditions, it is necessary to rely on complex computer codes to assess these accidents. The central role that computer codes play in safety analyses requires that the codes be verified, or tested, by comparing the code predictions with a wide range of experimental data chosen to span the physical phenomena expected under potential accident conditions. This paper discusses the plans of the Nuclear Regulatory Commission for verifying the reactor safety codes being developed by NRC to assess the safety of light water reactors and fast breeder reactors. (author)

  14. Research and development studies on the seismic behaviour of the PEC fast reactor (safety analysis detailed report no. 8)

    Energy Technology Data Exchange (ETDEWEB)

    Martelli, A.; Forni, M.; Masoni, P.; Maresca, G.; Castoldi, A.; Muzzi, F. [ENEA, Rome (Italy); Ansaldo Spa, Genoa [Italy; ISMES Spa, Bergamo [Italy

    1988-01-15

    This paper presents the main features and results of the numerical and experimental studies that were carried out by ENEA (Italian Commission for Alternative Energy Sources) for the seismic verification of the Italian PEC fast reactor test facility. More precisely, the paper focuses on the wide-ranging research and development programme that has been performed (and recently completed) on the reactor building, the reactor-block, the main vessel, the core and the shutdown system. The needs of these detailed studies are stressed and the feed-backs on the design, necessary safisfy the seismic safety requirements, are recalled. The general validity of the analyses in the framework of the research and development activities for nuclear reactor is also pointed out.

  15. Experimental facilities for gas-cooled reactor safety studies. Task group on Advanced Reactor Experimental Facilities (TAREF)

    International Nuclear Information System (INIS)

    2009-01-01

    In 2007, the NEA Committee on the Safety of Nuclear Installations (CSNI) completed a study on Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR) which focused on facilities suitable for current and advanced water reactor systems. In a subsequent collective opinion on the subject, the CSNI recommended to conduct a similar exercise for Generation IV reactor designs, aiming to develop a strategy for ' better preparing the CSNI to play a role in the planned extension of safety research beyond the needs set by current operating reactors'. In that context, the CSNI established the Task Group on Advanced Reactor Experimental Facilities (TAREF) in 2008 with the objective of providing an overview of facilities suitable for performing safety research relevant to gas-cooled reactors and sodium fast reactors. This report addresses gas-cooled reactors; a similar report covering sodium fast reactors is under preparation. The findings of the TAREF are expected to trigger internationally funded CSNI projects on relevant safety issues at the key facilities identified. Such CSNI-sponsored projects constitute a means for efficiently obtaining the necessary data through internationally co-ordinated research. This report provides an overview of experimental facilities that can be used to carry out nuclear safety research for gas-cooled reactors and identifies priorities for organizing international co-operative programmes at selected facilities. The information has been collected and analysed by a Task Group on Advanced Reactor Experimental Facilities (TAREF) as part of an ongoing initiative of the NEA Committee on the Safety of Nuclear Installations (CSNI) which aims to define and to implement a strategy for the efficient utilisation of facilities and resources for Generation IV reactor systems. (author)

  16. Problems of nuclear reactor safety. Vol. 1; Problemy bezopasnosti yaderno-ehnergeticheskikh ustanovok. Tom 1

    Energy Technology Data Exchange (ETDEWEB)

    Shal` nov, A V [Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)

    1996-12-31

    Proceedings of the 9. Topical Meeting `Problems of nuclear reactor safety` are presented. Papers include results of studies and developments associated with methods of calculation and complex computerized simulation for stationary and transient processes in nuclear power plants. Main problems of reactor safety are discussed as well as rector accidents on operating NPP`s are analyzed.

  17. RB research reactor safety report

    International Nuclear Information System (INIS)

    Sotic, O.; Pesic, M.; Vranic, S.

    1979-04-01

    This new version of the safety report is a revision of the safety report written in 1962 when the RB reactor started operation after reconstruction. The new safety report was needed because reactor systems and components have been improved and the administrative procedures were changed. the most important improvements and changes were concerned with the use of highly enriched fuel (80% enriched), construction of reactor converter outside the reactor vessel, improved control system by two measuring start-up channels, construction of system for heavy water leak detection, new inter phone connection between control room and other reactor rooms. This report includes description of reactor building with installations, rector vessel, reactor core, heavy water system, control system, safety system, dosimetry and alarm systems, experimental channels, neutron converter, reactor operation. Safety aspects contain analyses of accident reasons, method for preventing reactivity insertions, analyses of maximum hypothetical accidents for cores with natural uranium, 2% enriched and 80% enriched fuel elements. Influence of seismic events on the reactor safety and well as coupling between reactor and the converter are parts of this document

  18. Reactor containment and reactor safety in the United States

    International Nuclear Information System (INIS)

    Kouts, H.

    1986-01-01

    The reactor safety systems of two reactors are studied aiming at the reactor containment integrity. The first is a BWR type reactor and is called Peachbottom 2, and the second is a PWR type reactor, and is called surry. (E.G.) [pt

  19. Monitoring circuit for reactor safety systems

    Science.gov (United States)

    Keefe, Donald J.

    1976-01-01

    The ratio between the output signals of a pair of reactor safety channels is monitored. When ratio falls outside of a predetermined range, it indicates that one or more of the safety channels has malfunctioned.

  20. Monitoring circuit for reactor safety systems

    International Nuclear Information System (INIS)

    Keefe, D.J.

    1976-01-01

    The ratio between the output signals of a pair of reactor safety channels is monitored. When ratio falls outside of a predetermined range, it indicates that one or more of the safety channels has malfunctioned. 3 claims, 2 figures

  1. Reactor safety training for decision making

    International Nuclear Information System (INIS)

    Scott, C.K.

    2003-01-01

    The purpose of this paper is to describe an approach to reactor safety training for technical staff working at an operating station. The concept being developed is that, when the engineer becomes a registered professional engineer, they have sufficient reactor safety knowledge to perform independent technical work without compromising the safety of the plant. This goal would be achieved with a focused training program while working as an engineer-in-training (four years in NB). (author)

  2. IAEA programme on research reactor safety

    International Nuclear Information System (INIS)

    Alcala, F.; Di Meglio, A.F.

    1995-01-01

    This paper describes the IAEA programme on research reactor safety and includes the safety related areas of conversions to the use of low enriched uranium (LEU) fuel. The program is based on the IAEA statutory responsibilities as they apply to the requirements of over 320 research reactors operating around the world. The programme covers four major areas: (a) the development of safety documents; (b) safety missions to research reactor facilities; (c) support of research programmes on research reactor safety; (d) support of Technical Cooperation projects on research reactor safety issues. The demand for these activities by the IAEA member states has increased substantially in recent years especially in developing countries with increasing emphasis being placed on LEU conversion matters. In response to this demand, the IAEA has undertaken an extensive programme for each of the four areas above. (author)

  3. 1980 Annual status report reactor safety

    International Nuclear Information System (INIS)

    1981-01-01

    The JRC reactor safety programme involves theoretical and experimental activities to analyse accidents and their consequences for LWRs and LMFBRs. The first project deals with the improvement and the application of methodologies for risk and reliability assessment. This activity involves the identification and modelling of accident sequences and events and the analysis of fault trees. In this project, the implementation of a centralized data bank system (European Reliability Data System) is foreseen, which should provide the information needed for risk assessment studies. In project 2 a major effort on LWRs is centered on the study of the loss-of-coolant accident following large, intermediate or small breaks of the primary circuit. These accidents are simulated out of pile in the LOBI facility. In project 3 a contribution is made to solve material problems and to provide data and calculation methods for end of life predictions of reactor components. It involves a contribution to the programme for the inspection of steel components (PISC) as well as the study of fracture and creep fatigue properties of stainless steel. In the project 4 and 5 a deterministic approach is adopted to solve some problems of large hypothetical accidents in an LMFBR. The calculation tools developed concern sodium thermohydraulics in fuel element bundles, fuel coolant interaction, whole core accident analysis, containment loading and response and post accident heat removal

  4. Experts' discussion on reactor safety research

    International Nuclear Information System (INIS)

    1980-01-01

    The experts' discussion on reactor safety research deals with risk analysis, political realization, man and technics, as well as with the international state of affairs. Inspite of a controversy on individual issues and on the proportion of governmental and industrial involvment in reactor safety research, the continuation and intensification of corresponding research work is said to be necessary. Several participants demanded to consider possible 'conventional accidents' as well as a stronger financial commitment by the industry in this sector. The ratio 'man and technics' being an interface decisive for the proper functioning or failure of complex technical systems requires even more research work to be done. (GL) [de

  5. Technical mechanics in constructional reactor safety

    International Nuclear Information System (INIS)

    Matthees, W.

    1979-01-01

    Reactor safety is based on close cooperation between a number of technical and scientific disciplines; most problems of reactor technology can be solved with the aid of technical mechanics. At the 5th International Conference on Structural Mechanics in Reactor Technology (5th SMIRT), one of the biggest conferences in the field of applied technical mechanics, about 800 papers were read giving the latest state of knowledge in the field of constructional reactor safety. The main subject of the conference was the analysis of material behaviour under high loads; the information and methods of these analysis go far beyond what is required in the conventional field. (orig./UA) [de

  6. RSAS: a Reactor Safety Assessment System

    International Nuclear Information System (INIS)

    Sebo, D.E.; Dixon, B.W.; Bray, M.A.

    1985-01-01

    The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (NRC). RSAS is being developed for use at the NRC's Operations Center in the event of a serious incident at a licensed nuclear power plant. The system generates situation assessments for the NRC Reactor Safety Team based on a limited number of plant parameters, known operator actions, and plant status data. The RSAS rule base currently covers one reactor type. The extension of the rule base to other reactor types is also discussed

  7. Uncertainties and reliability theories for reactor safety

    International Nuclear Information System (INIS)

    Veneziano, D.

    1975-01-01

    What makes the safety problem of nuclear reactors particularly challenging is the demand for high levels of reliability and the limitation of statistical information. The latter is an unfortunate circumstance, which forces deductive theories of reliability to use models and parameter values with weak factual support. The uncertainty about probabilistic models and parameters which are inferred from limited statistical evidence can be quantified and incorporated rationally into inductive theories of reliability. In such theories, the starting point is the information actually available, as opposed to an estimated probabilistic model. But, while the necessity of introducing inductive uncertainty into reliability theories has been recognized by many authors, no satisfactory inductive theory is presently available. The paper presents: a classification of uncertainties and of reliability models for reactor safety; a general methodology to include these uncertainties into reliability analysis; a discussion about the relative advantages and the limitations of various reliability theories (specifically, of inductive and deductive, parametric and nonparametric, second-moment and full-distribution theories). For example, it is shown that second-moment theories, which were originally suggested to cope with the scarcity of data, and which have been proposed recently for the safety analysis of secondary containment vessels, are the least capable of incorporating statistical uncertainty. The focus is on reliability models for external threats (seismic accelerations and tornadoes). As an application example, the effect of statistical uncertainty on seismic risk is studied using parametric full-distribution models

  8. Problems of nuclear reactor safety. Vol. 2

    International Nuclear Information System (INIS)

    Goncharov, L.A.

    1995-01-01

    Theses of proceedings of the 9 Topical Meeting on problems of nuclear power plant safety are presented. Reports include results of neutron-physical experiments carried out for reactor safety justification. Concepts of advanced reactors with improved safety are considered. Results of researches on fuel cycles are given too

  9. The Chemistry of iodine in reactor safety: summary and conclusions: OECD Workshop

    International Nuclear Information System (INIS)

    1996-01-01

    About seventy experts from fourteen OECD member countries attended this Fourth OECD Workshop on the chemistry of iodine in reactor safety, as well as experts from Latvia and the Commission of the European Communities. Thirty four papers were presented, in five sessions: national and international programmes (integral and intermediate-scale experiments), experimental homogeneous phase chemistry, surface processes, thermodynamic and kinetic studies, safety applications. A final session is devoted to a general discussion on remaining research studies relevant to reactor safety

  10. Overview of fusion reactor safety

    International Nuclear Information System (INIS)

    Cohen, S.; Crocker, J.G.

    1981-01-01

    Present trends in magnetic fusion research and development indicate the promise of commercialization of one of a limited number of inexhaustible energy options early in the next century. Operation of the large-scale fusion experiments, such as the Joint European Torus (JET) and Takamak Fusion Test Reactor (TFTR) now under construction, are expected to achieve the scientific break even point. Early design concepts of power producing reactors have provided problem definition, whereas the latest concepts, such as STARFIRE, provide a desirable set of answers for commercialization. Safety and environmental concerns have been considered early in the development of magnetic fusion reactor concepts and recognition of proplem areas, coupled with a program to solve these problems, is expected to provide the basis for safe and environmentally acceptable commercial reactors. First generation reactors addressed in this paper are expected to burn deuterium and tritium fuel because of the relatively high reaction rates at lower temperatures compared to advanced fuels such as deuterium-deuterium. This paper presents an overwiew of the safety and environmental problems presently perceived, together with some of the programs and techniques planned and/or underway to solve these problems. A preliminary risk assessment of fusion technology relative to other energy technologies is made. Improvements based on material selection are discussed. Tritium and neutron activation products representing potential radiological hazards in fusion reactor are discussed, and energy sources that can lead to the release of radioactivity from fusion reactors under accident conditions are examined. The handling and disposal of radioactive waste are discussed; the status of biological effects of magnetic fields are referenced; and release mechanisms for tritium and activation products, including analytical methods, are presented. (orig./GG)

  11. The emphasis is on reactor safety research

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    For the second time the Association for Reactor Safety mbH (GRS), Koeln, organised on behalf of the BMFT the conference 'Reactor safety research'. About 400 visitors took part. The public who were interested were given a review of the activities which are being undertaken by the BMFT in the programme 'Research and safety of light-water reactors'. The series of conference papers initiated by the BMFT is to be developed into a permanent information source which will be of interest to those working on nuclear questions such as official quarters, industry and high schools, and experts who have to give judgements. The most important statements by various research groups in industry, high schools and also associations of experts, are summarised. (orig.) [de

  12. Development of the reactor safety film

    International Nuclear Information System (INIS)

    Sheheen, N.N.; Hodson, P.J.

    1981-01-01

    The first computer-generated film of LASL's Reactor Safety efforts was developed using the ANIMATE framework, a program that adds visual capabilities to MAPPER. Numerous software limitations had to be overcome within a very limited production schedule. A significant achievement was the 15,000-vector-per-frame sequence depicting a pressurized water reactor core with parts flashing while pumps circulate fluid through the system

  13. Some views on nuclear reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Tanguy, P.Y. [Electricite de France, Paris (France)

    1995-04-01

    This document is the text of a speech given by Pierre Y. Tanguy (Electricite de France) at the 22nd Water Reactor Safety Meeting held in Bethesda, MD in 1994. He describes the EDF nuclear program in broad terms and proceeds to discuss operational safety results with EDF plants. The speaker also outlines actions to enhance safety planned for the future, and he briefly mentions French cooperation with the Chinese on the Daya Bay project.

  14. Hydrogen problems in reactor safety research

    International Nuclear Information System (INIS)

    Casper, H.

    1984-01-01

    The BMFT and BMI have initiated a workshop 'Hydrogen Problems in Reactor Safety Research' that took place October 3./4., 1983. The objective of this workshop was to present the state of the art in the main areas - Hydrogen-Production - Hydrogen-Distribution - Hydrogen-Ignition - Hydrogen-Burning and Containment Behaviour - Mitigation Measures. The lectures on the different areas are compiled. The most important results of the final discussion are summarized as well. (orig.) [de

  15. COMPRESS - a computerized reactor safety system

    International Nuclear Information System (INIS)

    Vegh, E.

    1986-01-01

    The computerized reactor safety system, called COMPRESS, provides the following services: scram initiation; safety interlockings; event recording. The paper describes the architecture of the system and deals with reliability problems. A self-testing unit checks permanently the correct operation of the independent decision units. Moreover the decision units are tested by short pulses whether they can initiate a scram. The self-testing is described in detail

  16. Light-water reactor safety analysis codes

    International Nuclear Information System (INIS)

    Jackson, J.F.; Ransom, V.H.; Ybarrondo, L.J.; Liles, D.R.

    1980-01-01

    A brief review of the evolution of light-water reactor safety analysis codes is presented. Included is a summary comparison of the technical capabilities of major system codes. Three recent codes are described in more detail to serve as examples of currently used techniques. Example comparisons between calculated results using these codes and experimental data are given. Finally, a brief evaluation of current code capability and future development trends is presented

  17. Comments on nuclear reactor safety in Ontario

    International Nuclear Information System (INIS)

    1987-08-01

    The Chalk River Technicians and Technologists Union representing 500 technical employees at the Chalk River Nuclear Laboratories of AECL submit comments on nuclear reactor safety to the Ontario Nuclear Safety Review. Issues identified by the Review Commissioner are addressed from the perspective of both a labour organization and experience in the nuclear R and D field. In general, Local 1568 believes Ontario's CANDU nuclear reactors are not only safe but also essential to the continued economic prosperity of the province

  18. Reactor safety in Eastern Europe

    International Nuclear Information System (INIS)

    1995-02-01

    The papers presented to the GRS colloquium refer to the cooperative activities for reactor accident analysis and modification of the GRS computer codes for their application to reactors of the Russian design types of WWER or RBMK. Another topic is the safety of RBMK reactors in particular, and the current status of investigations and studies addressing the containment of unit 4 of the Chernobyl reactor station. All papers are indexed separately in report GRS--117. (HP)

  19. Reactor safety research in France

    International Nuclear Information System (INIS)

    Bussac, J.; Zammite, R.

    1989-01-01

    The paper deals withs PWR research only and covers programs performed in CEA or in cooperation between CEA and EDF or Framatome. Emphasis is being given to core cooling faults and associated procedures, primary circuit two-phase thermohydraulics, core damage, safeguarding of confinement, evaluation of accidental releases, and management of accident consequences. Most of the design and construction adequacy problems have already been solved in a generic manner, nevertheless new designs are now being studied and may require complementary research. (DG)

  20. Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

    International Nuclear Information System (INIS)

    1975-06-01

    The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

  1. Categorization of reactor safety issues from a risk perspective

    International Nuclear Information System (INIS)

    1985-03-01

    This report presents the results of an effort to identify and rank reactor safety and risk issues identified from past Probabilistic Risk Assessments (PRAs) and other safety analyses. Because of the varied scope of these analyses, the list of issues may be incomplete. Nevertheless, those studies comprised ordered analyses to whatever their respective depths; hence, they warranted scrutiny for whatever insights they could reveal with respect to issue importance. The top-ranked issues in terms of their contribution to the uncertainty in risk are described in some detail. All of these risk issues are compared to the generic safety issues for completeness and omissions

  2. Sodium Fast Reactor Safety and Licensing Research Plan

    International Nuclear Information System (INIS)

    Denman, Matthew; Lachance, Jeff; Sofu, Tanju; Wigeland, Roald; Flanagan, George; Bari, Robert

    2013-01-01

    Conclusions: The Sodium Fast Reactor Safety and Licensing Research Plan reports conclude a multi-year expert elicitation process. All information included in the studies are publicly available and the reports are UUR. These reports are intended to guide SFR researchers in the safety and licensing arena to important and outstanding issues Two (and a half) projects have been funded based on the recommendations in this report: • Modernization of SAS4A; • Incorporation of Contain/LMR with MELCOR; • (Data recovery at INL and PNNL)

  3. Reactor safety research in times of change

    International Nuclear Information System (INIS)

    Zipper, Reinhard

    2013-01-01

    Since the early 1970ies reactor safety research sponsored by the German Ministry of Economics an Technology and its predecessors and pursued independently from interests of industry or industrial associations as well as from current licensing issues significantly contributed to the extension of knowledge regarding risks and possible threats associated with the operation of nuclear power plants. The results of these research activities triggered several measures taken by industry and utilities to further enhance the internationally recognized high safety standards of nuclear power plants in Germany. Furthermore, by including especially universities in the distinguished research activities a large number of young scientists were given the opportunity to qualify in the field of nuclear reactor technology and safety thus contributing to the preservation of competence during the demographic change. The nuclear phase out in Germany affects also issues of reactor safety research in Germany. While Germany will progressively decrease and terminate the use of nuclear energy for public power supply other countries in Europe and in other parts of the world are continuing, expanding and even starting the use of nuclear power. As generally recognized, nuclear safety is an international issue and in the wake of the Fukushima disaster there are several initiatives to launch a system of internationally binding safety rules and guide lines. The German Competence Alliance therefore has elaborated a framework of areas were future reactor safety research will still be needed to support German efforts based on own and independent expertise to continuously develop and establish highest safety standards for the use of nuclear power supply domestic and abroad.

  4. EPRI program in water reactor safety

    International Nuclear Information System (INIS)

    Loewenstein, W.B.; Gelhaus, F.; Gopalakrishnan, A.

    1975-01-01

    The basis for EPRI's water reactor safety program is twofold. First is compilation and development of fundamental background data necessary for quantified light-water reactor (LWR) safety assurance appraisals. Second is development of realistic and experimentally bench-marked analytical procedures. The results are expected either to confirm the safety margins in current operating parameters, and to identify overly conservative controls, or, in some cases, to provide a basis for improvements to further minimize uncertainties in expected performance. Achievement of these objectives requires the synthesis of related current and projected experimental-analytical projects toward establishment of an experimentally-based analysis for the assurance of safety for LWRs

  5. Perspectives on reactor safety. Revision 1

    International Nuclear Information System (INIS)

    Haskin, F.E.; Hodge, S.A.

    1997-11-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

  6. Perspectives on reactor safety. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A. [Oak Ridge National Lab., TN (United States). Engineering Technology Div.

    1997-11-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  7. New and recently finalised activities within the NKS Programmes for Nordic cooperation on nuclear reactor safety and emergency preparedness

    DEFF Research Database (Denmark)

    Andgren, Karin; Andersson, Kasper Grann; Magnússon, Sigurður M.

    2015-01-01

    Over the years, NKS has provided funding for hundreds of research activities in fields comprising reactor safety, decommissioning, nuclear and radiological emergency preparedness, and management of radioactive waste. Advanced technologies and methods developed under the NKS framework have been used...... within the Nordic countries as well as internationally. Two programme areas are defined under the NKS platform: The NKS-R programme on nuclear reactor safety and the NKS-B programme on emergency preparedness. Three articles, giving an introduction to NKS and its two programmes, were published...

  8. The IAEA programme on research reactor safety

    International Nuclear Information System (INIS)

    Abou Yehia, H.

    2007-01-01

    According to the research reactor database of IAEA (RRDB), 250 reactors are operating worldwide, 248 have been shut down and 170 have been decommissioned. Among the 248 reactors that do not run, some will resume their activities, others will be dismantled and the rest do not face a clear future. The analysis of reported incidents shows that the ageing process is a major cause of failures, more than two thirds of operating reactors are over 30 years old. It also appears that the lack of adequate regulations or safety standards for research reactors is an important issue concerning reactor safety particularly when reactors are facing re-starting or upgrading or modifications. The IAEA has launched a 4-axis program: 1) to set basic safety regulations and standards for research reactors, 2) to provide IAEA members with an efficient help for the application of these safety regulations to their reactors, 3) to foster international exchange of information on research reactor safety, and 4) to provide IAEA members with a help concerning safety issues linked to malicious acts or sabotage on research reactors

  9. A university contribution to reactor safety

    International Nuclear Information System (INIS)

    Hall, W.B.

    1980-01-01

    The total UK university effort available for research specifically directed towards reactor safety is certainly small in comparison with that in industry. To be worth while, the work should complement that in the industry, and ways in which this can, and in some cases does, happen, will be discussed. There is, however, another reason for university involvement: the need for an informed body of opinion on matters of reactor safety outside the industry. Without this it is difficult for the public and its representatives to assure themselves that the depth and scope of safety analysis is commensurate with the seriousness of the problem, and that the best available data and techniques are being used. An independent inspectorate is an essential element in this philosophy, but in addition there is much to be said for exposing the arguments to scrutiny by the widest possible range of informed critics. Such people will be much more effective if they are themselves involved in real problems in the field. In a university, this involvement is probably best achieved through research; as mentioned above, the type of research should preferably complement that being carried out in the industry. The current situation, and the future, are discussed. (author)

  10. Radiological Worker Training: Radiological Worker 2 study guides

    International Nuclear Information System (INIS)

    1992-10-01

    Upon completion of this training course, the participant will have the knowledge to work safely in areas controlled for radiological purposes using proper radiological practices. Radiological Worker H Training, for the worker whose job assignment involves entry into Radiological Buffer Areas and all types of Radiation Contamination and Airborne Radioactivity Areas. This course is designed to prepare the worker to work safely in and around radiological areas and present methods to use to ensure individual radiation exposure is maintained As Low As Reasonably Achievable

  11. The Storage of Thermal Reactor Safety Analysis data (STRESA)

    International Nuclear Information System (INIS)

    Tanarro Colodron, J.

    2016-01-01

    Full text: Storage of Thermal Reactor Safety Analysis data (STRESA) is an online information system that contains three technical databases: 1) European Nuclear Research Facilities, open to all online visitors; 2) Nuclear Experiments, available only to registered users; 3) Results Data, being the core content of the information system, its availability depends on the role and organisation of each user. Its main purpose is to facilitate the exchange of experimental data produced by large Euratom funded scientific projects addressing severe accidents, providing at the same time a secure repository for this information. Due to its purpose and architecture, it has become an important asset for networks of excellence as SARNET or NUGENIA. The Severe Accident ResearchNetwork of Excellence (SARNET)was set up in 2004 under the aegis of the research Euratom Framework Programmes to study severe accidents in watercooled nuclear power plants. Coordinated by the IRSN, SARNET unites 43 organizations involved in research on nuclear reactor safety in 18 European countries plus the USA, Canada, South Korea and India. In 2013, SARNET became fully integrated in the Technical Area N2(TA2), named “Severe accidents” of NUGENIA association, devoted to R&D on fission technology of Generation II and III. (author

  12. Dosimetric studies in diagnostic radiology

    International Nuclear Information System (INIS)

    Mohamadain, K. E. M.

    2004-04-01

    A dosimetric study in pediatric radiology and adult patients was currently being carried out at the pediatrics units of two large hospitals in Rio de Janeiro city: IPPMG (Instituto de Pediatric e Puericultura Martagao Gesteira, University hospital of federal University of Rio de Janeiro), IFF (Instituto Fernandes Figueira, FIOCRUZ) and Hospital Geral de Bonsucesso, a large public hospital in Rio de Janeiro city (HGB) Brazil. The dosimetric study was also performed at three pediatrics units in Sudan, namely, Ahmed Gasim, Khartoum and Omdurman hospitals. For chest x-ray examination the entrance skin dose(ESD) for AP, PA and LAT projections of pediatric patients, and the scattered dose at the thyroid, ovary and gonads have been obtained with thermoluminescent dosimeters (TLD) and with use of a software package Dosecal in thr Brazilian hospitals, and with the software dosecal in the Sudanese hospitals.The aim of this work was to estimate the entrance skin dose (ESD), the effective dose (ED) and the body organ dose (BOD) for chest x-ray exposure in pediatric patients, and different exams for adults patients, and to compare the results obtained in the tow Countries Sudan and Brazil with the reference dose level. For ESD evaluation of the chest x-ray, three different TL dosimeters have been used, namely LiF: Mg, Ti (TLD 100) CaSo 4 : Dy and LiF:Mg, Cu,P (TLD 100 H). The age intervals considered were: 0-1 years, 1-5 years, 5-10 years and 10-15 years. The results obtained with all dosimeters were in good agreement with, those obtained by the dosecal software, especially for AP and PA projection. However, some discrepancies were found for the LAT projection. The results within Brazil were some what consistent while in Sudan, large difference were observed, it was also noted that the doses in Brazil hospitals were less than the reference dose levels while in Sudanese hospitals the doses were higher than the reference dose levels. For adult patients only the software dosecal

  13. Reactor safety research - results and perspectives

    International Nuclear Information System (INIS)

    Banaschik, M.

    1989-01-01

    The work performed so far is an essential contribution to the determination of the safety margins of nuclear facilities and their systems and to the further development of safety engineering. The further development of safety engineering involves a shift of emphasis in reactor safety research towards event sequences beyond the design basis. The aim of this shift in emphasis is the further development of the preventive level. This is based on the fact that the conservative design of the operating and safety systems involves and essential safety potential. The R and D work is intended to help develop accident management measures and to take the plant back into the safe state even after severe accidents. In this context, it is necessary to make full use of the safety margins of the plant and to include the operating systems for coping with accidents. As a result of the aims, the research work approaches operating and plant-specific processes. (orig./DG) [de

  14. IAEA activities on research reactor safety

    International Nuclear Information System (INIS)

    Alcala-Ruiz, F.

    1995-01-01

    Since its inception in 1957, the International Atomic Energy Agency (IAEA) has included activities in its programme to address aspects of research reactors such as safety, utilization and fuel cycle considerations. These activities were based on statutory functions and responsibilities, and on the current situation of research reactors in operation around the world; they responded to IAEA Member States' general or specific demands. At present, the IAEA activities on research reactors cover the above aspects and respond to specific and current issues, amongst which safety-related are of major concern to Member States. The present IAEA Research Reactor Safety Programme (RRSP) is a response to the current situation of about 300 research reactors in operation in 59 countries around the world. (orig.)

  15. Thermal hydraulic reactor safety analyses and experiments

    International Nuclear Information System (INIS)

    Holmstroem, H.; Eerikaeinen, L.; Kervinen, T.; Kilpi, K.; Mattila, L.; Miettinen, J.; Yrjoelae, V.

    1989-04-01

    The report introduces the results of the thermal hydraulic reactor safety research performed in the Nuclear Engineering Laboratory of the Technical Research Centre of Finland (VTT) during the years 1972-1987. Also practical applications i.e. analyses for the safety authorities and power companies are presented. The emphasis is on description of the state-of-the-art know how. The report describes VTT's most important computer codes, both those of foreign origin and those developed at VTT, and their assessment work, VTT's own experimental research, as well as international experimental projects and other forms of cooperation VTT has participated in. Appendix 8 contains a comprehensive list of the most important publications and technical reports produced. They present the content and results of the research in detail.(orig.)

  16. Nuclear reactor safety research in Idaho

    International Nuclear Information System (INIS)

    Zeile, H.J.

    1983-01-01

    Detailed information about the performance of nuclear reactor systems, and especially about the nuclear fuel, is vital in determining the consequences of a reactor accident. Fission products released from the fuel during accidents are the ultimate safety concern to the general public living in the vicinity of a nuclear reactor plant. Safety research conducted at the Idaho National Engineering Laboratory (INEL) in support of the U.S. Nuclear Regulatory Commission (NRC) has provided the NRC with detailed data relating to most of the postulated nuclear reactor accidents. Engineers and scientists at the INEL are now in the process of gathering data related to the most severe nuclear reactor accident - the core melt accident. This paper describes the focus of the nuclear reactor safety research at the INEL. The key results expected from the severe core damage safety research program are discussed

  17. Pancreatic pseudocysts. Radiological and ultrasonographic studies

    Energy Technology Data Exchange (ETDEWEB)

    Contrera, J.D.; Uemura, L.; Palma, J.K.; Souza, L.P. de; Ferraz, L.R.L.; Magalhaes, P.J.A. (Sao Paulo Univ., Ribeirao Preto (Brazil). Faculdade de Medicina)

    Radiological and ultrasonographic studies of ten patients with surgically confirmed pancreatic pseudocysts were reviewed. All of them were male, with previous story of chronic alcoholism and clinical evidences of pancreatitis. The most important radiological finding consisted of a mass opacifying the epigastrium, displacing the stomach and bowel loops. ultrasound studies showed that the lesions were predominantly cystic, rounded or oval-shaped with smooth or irregular contours and of various sizes.

  18. Proceedings of the Third Scientific Presentation on Reactor Safety Technology

    International Nuclear Information System (INIS)

    1998-01-01

    These proceedings contains the results of research and development on reactor safety technology which carried out by Reactor Safety Technology Centre, National Atomic Energy Agency, Serpong, Indonesia during 1997/1998 fiscal year. The presentation was held on 13-14 May 1998 at Serpong,Indonesia

  19. Radiology

    International Nuclear Information System (INIS)

    Bigot, J.M.; Moreau, J.F.; Nahum, H.; Bellet, M.

    1990-01-01

    The 17th International Congress of Radiology was conducted in two separate scientific sessions, one for radiodiagnosis and one for radiation oncology. Topics covered are: Radiobiology -radioprotection; imaging and data processing; contrast media; MRI; nuclear medicine; radiology and disasters; radiology of tropical diseases; cardiovascular radiology; interventional radiology; imaging of trauma; imaging of chest, gastro-intestinal tract, breast and genito-urinary tract; imaging in gynecology;imaging in oncology; bone and joint radiology; head and neck-radiology; neuro-radiology. (H.W.). refs.; fig.; tabs

  20. German Light-Water-Reactor Safety-Research Program

    International Nuclear Information System (INIS)

    Seipel, H.G.; Lummerzheim, D.; Rittig, D.

    1977-01-01

    The Light-Water-Reactor Safety-Research Program, which is part of the energy program of the Federal Republic of Germany, is presented in this article. The program, for which the Federal Minister of Research and Technology of the Federal Republic of Germany is responsible, is subdivided into the following four main problem areas, which in turn are subdivided into projects: (1) improvement of the operational safety and reliability of systems and components (projects: quality assurance, component safety); (2) analysis of the consequences of accidents (projects: emergency core cooling, containment, external impacts, pressure-vessel failure, core meltdown); (3) analysis of radiation exposure during operation, accident, and decommissioning (project: fission-product transport and radiation exposure); and (4) analysis of the risk created by the operation of nuclear power plants (project: risk and reliability). Various problems, which are included in the above-mentioned projects, are concurrently studied within the Heiss-Dampf Reaktor experiments

  1. Very high temperature measurements: Applications to nuclear reactor safety tests

    International Nuclear Information System (INIS)

    Parga, Clemente-Jose

    2013-01-01

    This PhD dissertation focuses on the improvement of very high temperature thermometry (1100 deg. C to 2480 deg. C), with special emphasis on the application to the field of nuclear reactor safety and severe accident research. Two main projects were undertaken to achieve this objective: - The development, testing and transposition of high-temperature fixed point (HTFP) metal-carbon eutectic cells, from metrology laboratory precision (±0.001 deg. C) to applied research with a reasonable degradation of uncertainties (±3-5 deg. C). - The corrosion study and metallurgical characterization of Type-C thermocouple (service temp. 2300 deg. C) prospective sheath material was undertaken to extend the survivability of TCs used for molten metallic/oxide corium thermometry (below 2000 deg. C)

  2. Probabilistic methods in the field of reactor safety in Germany

    Energy Technology Data Exchange (ETDEWEB)

    Birkhofer, A [Technische Univ. Muenchen (Germany, F.R.). Lehrstuhl fuer Reaktordynamik und Reaktorsicherheit

    1979-01-01

    The present status and future prospects in Germany of reliability, as well as risk analysis, in the field of reactor safety are examined. The development of analytical methods with respect to the available data base is reviewed with consideration of the roles of reliability codes, component data, common mode failures, human influence, structural analysis and process computers. Some examples of the application of probability assessments are discussed and the extension of reliability analysis beyond the loss-of-coolant accident is considered. In the case of risk analysis, the object is to determine not only the probability of failure of systems but also the probability and extent of possible consequences. Some risk studies under investigation in Germany and the methodology of risk analysis are discussed. Reliability and risk analysis are involved to an increasing extent in safety research and licensing procedures and their influence in other fields such as the public perception of risk is also discussed.

  3. Reactor safety-a New Approach

    International Nuclear Information System (INIS)

    Machiels, A.J.; Marston, T.U.; Taylor, J.J.

    1993-01-01

    Since 1982, the U.S. utilities have been leading to an industry-wide effort to establish a technical foundation for the design of the next generation of light water reactors (LWRs) in the United States. Since 1985, the utility initiative has been effected through a major technical program managed by the Electric Power Research Institute (EPRI): the Advanced Light Water Reactor (ALWR) Program. In addition to the U.S. utility leadership and sponsorship, the ALWR Program has also greatly benefitted from the participation and sponsorship of numerous international utility companies and from the close cooperation with the U.S. Department of Energy (DOE). One of the main goals of the ALWR Program has been to develop a comprehensive set of design requirements for the advanced LWRs. The Utility Requirement Document (URD) defines the technical basis for improved and standardized future LWR designs. The URD covers the entire plant up to the grid interface. Therefore, it is the basis for an integrated plant design, i.e., nuclear steam supply system and balance of plant. It emphasizes those areas which are most important to the objective of achieving an advanced LWR that is excellent with respect to safety, performance, constructibility, and economics. There are numerous basic design policies underlying the ALWR URD. Of particular interest is the treatment of reactor safety

  4. Commissioning of research reactors. Safety guide

    International Nuclear Information System (INIS)

    2006-01-01

    The objective of this Safety Guide is to provide recommendations on meeting the requirements for the commissioning of research reactors on the basis of international best practices. Specifically, it provides recommendations on fulfilling the requirements established in paras 6.44 and 7.42-7.50 of International Atomic Energy Agency, Safety of Research Reactors, IAEA Safety Standards Series No. NS-R-4, IAEA, Vienna (2005) and guidance and specific and consequential recommendations relating to the recommendations presented in paras 615-621 of International Atomic Energy Agency, Safety in the Utilization and Modification of Research Reactors, Safety Series No. 35-G2, IAEA, Vienna (1994) and paras 228-229 of International Atomic Energy Agency, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, Safety Series No. 35-G1, IAEA, Vienna (1994). This Safety Guide is intended for use by all organizations involved in commissioning for a research reactor, including the operating organization, the regulatory body and other organizations involved in the research reactor project

  5. Light-water-reactor safety program. Quarterly progress report, April--June 1977

    International Nuclear Information System (INIS)

    Sachs, R.G.; Kyger, J.A.

    1977-01-01

    The report summarizes work performed on the following water-reactor-safety problems: (1) loss-of-coolant accident research in heat transfer and fluid dynamics; (2) transient fuel response and fission-product release; (3) mechanical properties of zircaloy containing oxygen; and (4) steam-explosion studies

  6. SACRD: a data base for fast reactor safety computer codes, general description

    International Nuclear Information System (INIS)

    Greene, N.M.; Forsberg, V.M.; Raiford, G.B.; Arwood, J.W.; Simpson, D.B.; Flanagan, G.F.

    1979-01-01

    SACRD is a data base of material properties and other handbook data needed in computer codes used for fast reactor safety studies. Data are available in the thermodynamics, heat transfer, fluid mechanics, structural mechanics, aerosol transport, meteorology, neutronics, and dosimetry areas. Tabular, graphical and parameterized data are provided in many cases. A general description of the SACRD system is presented in the report

  7. Clinic-Radiological Study of facial paralysis

    International Nuclear Information System (INIS)

    Olier, J.; Bacaicoa, M.C.; Guridi, J.; Gil, J.L.; Elcarte, F.; Delgado, G.

    1992-01-01

    We have gathered 159 cases of facial paralysis from recent records in our hospital, including paralyses of central as well as peripheral origin, and presenting as the only symptom or as one of several major symptoms of the discomfort of each patient. Sixty-four percent of them were studied by CT scan and/or MR, confirming the existence of alterations in the pathway of nerve pair VII in 50% of the patients who underwent radiological study. Idiopathic facial paralysis was the most common type (42% of the total); while tumors and post-traumatic findings were the most constant radiological findings. From the analysis of the data, the importance of the clinical criteria for selection of the patients in the study and the protocol for radiological diagnosis employed can be deduced. (author)

  8. Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Appendices III and IV. [PWR and BWR

    Energy Technology Data Exchange (ETDEWEB)

    1975-10-01

    The items listed below summarize the detail sections which follow: a listing of definitions and a discussion of the general treatment of data within the random variable approach as utilized by the study; a tabulation of the assessed data base containing failure classifications, final assessed ranges utilized in quantification and reference source values considered in determining the ranges; a discussion of nuclear power plant experience that was used to validate the data assessment by testing its applicability as well as to check on the adequacy of the model to incorporate typical real incidents; an expanded presentation of the data assessment giving information on applicability considerations; a discussion of test and maintenance data including comparisons of models with experience data; and special topics, including assessments required for the initiating event probabilities and human error data and modeling.

  9. Flooding Experiments and Modeling for Improved Reactor Safety

    International Nuclear Information System (INIS)

    Solmos, M.; Hogan, K.J.; VIerow, K.

    2008-01-01

    Countercurrent two-phase flow and 'flooding' phenomena in light water reactor systems are being investigated experimentally and analytically to improve reactor safety of current and future reactors. The aspects that will be better clarified are the effects of condensation and tube inclination on flooding in large diameter tubes. The current project aims to improve the level of understanding of flooding mechanisms and to develop an analysis model for more accurate evaluations of flooding in the pressurizer surge line of a Pressurized Water Reactor (PWR). Interest in flooding has recently increased because Countercurrent Flow Limitation (CCFL) in the AP600 pressurizer surge line can affect the vessel refill rate following a small break LOCA and because analysis of hypothetical severe accidents with the current flooding models in reactor safety codes shows that these models represent the largest uncertainty in analysis of steam generator tube creep rupture. During a hypothetical station blackout without auxiliary feedwater recovery, should the hot leg become voided, the pressurizer liquid will drain to the hot leg and flooding may occur in the surge line. The flooding model heavily influences the pressurizer emptying rate and the potential for surge line structural failure due to overheating and creep rupture. The air-water test results in vertical tubes are presented in this paper along with a semi-empirical correlation for the onset of flooding. The unique aspects of the study include careful experimentation on large-diameter tubes and an integrated program in which air-water testing provides benchmark knowledge and visualization data from which to conduct steam-water testing

  10. Radiology

    International Nuclear Information System (INIS)

    Edholm, P.R.

    1990-01-01

    This is a report describing diagnostic techniques used in radiology. It describes the equipment necessary for, and the operation of a radiological department. Also is described the standard methods used in radiodiagnosis. (K.A.E.)

  11. Review of the German Reactor Safety Study

    International Nuclear Information System (INIS)

    Bayer, A.

    1980-01-01

    The accident risks in German nuclear power plants are reviewed. Parameters influencing the extent and consequences of an accident are differentiated. Risks of normal operation, war, and sabotage have not been considered. Measures taken by the operating shaft in the course of an accident are taken into account. The knowledge thus gained can be applied in the planning of emergency measures. (DG) [de

  12. A bibliography of AECL publications on reactor safety

    International Nuclear Information System (INIS)

    Hawley, N.J.

    1979-12-01

    AECL Publications on Reactor Safety in CANDU Reactors are listed in this bibliography. The listing is chronological and the accompanying index is by subject. The bibliography will be brought up to date annually. (auth)

  13. Reactor safety. Annual technical progress report, Government fiscal year 1979

    International Nuclear Information System (INIS)

    1980-01-01

    Information is presented on LMFBR reactor safety concerning the energetics effects of sodium spray fires; sodium drop and spray burning; core debris accommodation; attenuation in containment; and attenuation in the environment

  14. Fast breeder reactor safety : a perspective

    International Nuclear Information System (INIS)

    Kale, R.D.

    1992-01-01

    Taking into consideration India's limited reserves of natural and vast reserves of thorium, the fast reactor route holds a great promise for India's energy supply in future. The fast reactor fueled with 239 Pu/ 238 U (unused or depleted) produces (breeds) more fissionable fuel material 239 Pu than it consumes. Calculations show that a fast breeder reactor (FBR) increases energy potential of natural uranium by about 60 times. As the fast reactor can also convert 232 Th into 233 U which is a fissionable material, it can make India's thorium reserves a source of almost inexhaustible energy supply for a long time to come. Significant advantage of FBR plants cooled by sodium and their world-wide operating experience are reviewed. There are two main safety issues of FBR, one nuclear and the other non-nuclear. The nuclear issue concerns core disruptive accident and the non-nuclear one concerns the high chemical energy potential of sodium. These two issues are analysed and it is pointed that they are manageable by current design, construction and operational practices. Main findings of safety research during the last six to eight years in West European Countries and United States of America (US) are summarised. Three stage engineered safety provision incorporated into the design of the sodium cooled Fast Breeder Test Reactor (FBTR) commissioned at Kalpakkam are explained. The important design safety features of FBTR such as primary system containment, emergency core cooling, plant protection system, inherent safety features achieved through reactivity coefficients, and natural convection cooling are discussed. Theoretical analysis and experimental research in fast reactor safety carried out at the Indira Gandhi Centre for Atomic Research during the past some years are reviewed. (M.G.B.)

  15. Radiological Control Technician: Phase 1, Site academic training study guides

    International Nuclear Information System (INIS)

    1992-10-01

    This volume is a study guide for training Radiological Control Technicians. Provided herein are support materials for learning radiological documentation, communication systems, counting errors and statistics, dosimetry, contamination control, airborne sampling program methods, respiratory protection, radiological source control, environmental monitoring, access control and work area setup, radiological work coverage, shipment and receipt for radioactive material, radiological incidents and emergencies, personnel decontamination, first aid, radiation survey instrumentation, contamination monitoring, air sampling, and counting room equipment

  16. Nuclear reactor safety. Quarterly progress report, October 1--December 31, 1977

    International Nuclear Information System (INIS)

    Jackson, J.F.; Stevenson, M.G.

    1978-02-01

    Progress in reactor safety research is summarized. LWR studies include TRAC code development for thermal-hydraulic analysis of accidents, containment systems evaluation, and safety experiments. LMFBR studies include SIMMER code development and applications, modeling of core disruptive accidents, and safety test facilities studies. HTGR safety studies cover fission product release and transport, structural evaluation, phenomena modeling, systems analysis, and accident delineation. GCFR studies are focussed on core disruptive testing

  17. Radiologic study on lamina dura

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Hyung Kyu [Dept. of Radiology, College of Dentistry, Seoul National University, Seoul (Korea, Republic of)

    1981-11-15

    This study was performed to investigate the thickness of lamina dura of the human teeth in periodontal disease, which obtained from the intraoral roentgenograms of the 122 cases taken by bisecting technic. All films were divided into the different ages, the different sexes, and the different location of the different teeth. The obtained results were as follows: 1. Compared with the normal teeth, the thickness of lamina dura in periodontal disease is increased in all of different ages, sexes and teeth. 2. Generally, the alveolar crest portion is the thickest among the root surfaces, and midroot, apex followed, and the average thickness of the posterior teeth is thicker than that of anterior teeth. 3. The mean value of the whole maxillary teeth is almost same as that of mandibular teeth. 4. On the whole cases, the differences of male and female is about 0.01 mm, which is not a significant differences.

  18. Radiologic study on lamina dura

    International Nuclear Information System (INIS)

    Ahn, Hyung Kyu

    1981-01-01

    This study was performed to investigate the thickness of lamina dura of the human teeth in periodontal disease, which obtained from the intraoral roentgenograms of the 122 cases taken by bisecting technic. All films were divided into the different ages, the different sexes, and the different location of the different teeth. The obtained results were as follows: 1. Compared with the normal teeth, the thickness of lamina dura in periodontal disease is increased in all of different ages, sexes and teeth. 2. Generally, the alveolar crest portion is the thickest among the root surfaces, and midroot, apex followed, and the average thickness of the posterior teeth is thicker than that of anterior teeth. 3. The mean value of the whole maxillary teeth is almost same as that of mandibular teeth. 4. On the whole cases, the differences of male and female is about 0.01 mm, which is not a significant differences.

  19. Radiology in archaeological studies of incas mummies

    International Nuclear Information System (INIS)

    Previgliano, Carlos H.; Ceruti, Constanza; Arias Araoz, Facundo; Gonzalez Diez, Josefina; Reinhard, Johan

    2005-01-01

    Purpose: The purpose of this paper was to determine the imaging findings in three 500-year-old Inca mummies and how modern radiology can be used in other sciences such as archaeology. Material and Method: Three naturally mummified children were studied using conventional radiography, dental radiography, CT and puncture biopsies. Working sessions were limited to 20 minutes to prevent thawing of the corpses and radiological techniques were adjusted to their particular anatomic position. Results: CT images showed shrinkaged internal organs due to dehydration. The fatty tissue of the bodies was visibly white because of the transformation of it into adipocere, favoring white matter/gray matter differentiation at the central nervous system. The lungs were expanded in the three corpses and right lung and maxillary sinus pathologies were determined in the older girl. Chronological ages of the three children at the time of their deaths were established. DNA studies determined no family links among them. The spleen was not seen in any case. Conclusions: Modern radiology is an excellent tool in archaeological research. Nutritional state, ages and pathologies of the three mummies were evaluated. (author) [es

  20. Radiology

    International Nuclear Information System (INIS)

    Sykora, A.

    2006-01-01

    In this text-book basic knowledge about radiology, biomedical diagnostic methods (radiography, computer tomography), nuclear medicine and safety and radiation protection of personnel on the radiodiagnostic place of work are presented

  1. Osteopoikilosis: A radiological and pathological study

    International Nuclear Information System (INIS)

    Lagier, R.; Mbakop, A.; Bigler, A.

    1984-01-01

    Anatomico-pathological and radiological studies of osteopoikilosis were performed in two cases, one involving a femoral head, excised after a fracture of a femoral neck, in an elderly man and the other following biopsy of an iliac crest in a young woman. In both patients widespread radiological evidence of the disorder was present as an incidental finding. The radiological appearance of rounded and linear densities corresponded to old and inactive remodelling of spongy trabeculae in epiphyseal and metaphyseal locations. The distribution and appearance of these osteopoikilotic densities suggested them to have been related intimately to mechanical strain on spongy bone trabeculae. The diffuse nature of the lesions, their hereditary character, and their possible association with abnormalities of the skin suggest the existence of a particular terrain in which general metabolic conditions of connective tissue may interact with mechanical stresses in bone. Careful analysis of the findings in osteopoikilosis is desirable in order to provide data concerning the physiopathology of the skeleton and to permit more definitive interpretation of localised areas of bone condensation, including those observed not only in solitary bone islands and such conditions as osteopathia striata, but also those associated with infections and tumours. (orig.)

  2. ECORA - Evaluation of Computational Methods for Reactor Safety Analysis

    International Nuclear Information System (INIS)

    Scheuerer, Martina

    2002-01-01

    There were three motivations behind the ECORA Project: - the shortcomings of 0-D system codes in the simulation of 3-D, local flow and heat transfer phenomena, - increased interest in the application of 3-D CFD software as supplement to system codes, - high safety requirements in the nuclear industry required consistent standards for the use and assessment of CFD software. The purpose of ECORA was therefore: - to establish performance criteria for the assessment of CFD software, - to establish Best Practice Guidelines for application and use of CFD software, with the following objectives: - assessment of CFD applications in reactor safety: flows in containment (PANDA experiments) and flows in primary system (UPTF experiments) - Best Practice Guidelines for reactor safety: starting point (ERCOFTAC Best Practice Guidelines), adaptation to CFD application for nuclear safety, extension to assessment of experimental data - recommendations for improvements of CFD software, - network of European 'Centres of Competence for CFD Applications in Reactor Safety'. Currently, there were twelve partners in the ECORA Project, representing nine European countries. The Project was scheduled to last until September 2004. Ms Scheuerer then described the work programme and project structure, the Best Practice Guidelines for CFD simulations, the procedures for quantifying errors, applications of Best Practice Guidelines, Best Practice Guidelines for experimental data, applications to primary system, UPTF and PANDA data. Her conclusions were the following: - the Project had led to the improvement of the quality of CFD calculations in reactor safety, through: the ECORA Best Practice Guidelines, the assessment of shortcomings and the improvement of mathematical models. - It had also led to higher acceptance of CFD in reactor safety. - The next step was the establishment of European 'Centres of Competence for CFD Applications in reactor Safety'

  3. The organization of research reactor safety in the UKAEA

    International Nuclear Information System (INIS)

    Redpath, W.

    1983-01-01

    The present state of organization and development of research reactor safety in the UKAEA are outlined by addressing the fundamental safety principles which have been adopted in keeping with national health and safety requirement. The organisation, assessment and monitoring of research reactor safety on complex multi-discipline and multi-activity nuclear research and development site are discussed. Methods of safety assessment, such as probabilistic risk assessment and risk acceptance criteria, which have been developed and applied in practice are explained, and some indication of the directions in which some of the current developments in the safety of UKAEA research reactors is also included. (A.J.)

  4. Transactions of the Twentieth Water Reactor Safety Information Meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 20th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 21--23, 1992. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included

  5. Nuclear reactor safety: on the history of the regulatory process

    International Nuclear Information System (INIS)

    Okrent, D.

    1981-01-01

    This manuscript is derived from a long report which examines the history of the evolution of light water reactor safety. The central portion of the document provides a historical view of the development of siting policy and the major safety issues which interacted strongly with siting policy. A very incomplete selection of the very many important issues and developments in light water reactor safety is also included. Coverage of the loss-of-coolant accident (LOCA) has deliberately been abbreviated to include only a few selected aspects

  6. Steam--water mixing in nuclear reactor safety loss-of-coolant experiments

    International Nuclear Information System (INIS)

    Naff, S.A.; Schwarz, W.F.

    1978-01-01

    Computer models used to predict the response of reactors to hypothesized accidents necessarily incorporate approximating assumptions. To verify the models by comparing predicted and measured responses in test facilities, these assumptions must be confirmed to be realistic. Recent experiments in facilities capable of repeatedly duplicating the transient behavior of a pressurized water reactor undergoing a pipe rupture show that the assumption of complete water-steam mixing during the transient results in the predicted decompression being faster than that observed. Water reactor safety studies currently in progress include programs aimed at the verification of computer models or ''codes'' used to predict reactor system responses to various hypothesized accidents. The approach is to compare code predictions of transients with the actual test transients in experimental facilities. The purpose of this paper is to explain an important instance in which predictions and data are not in complete agreement and to indicate the significance to water reactor safety studies

  7. Improved Flow Modeling in Transient Reactor Safety Analysis Computer Codes

    International Nuclear Information System (INIS)

    Holowach, M.J.; Hochreiter, L.E.; Cheung, F.B.

    2002-01-01

    A method of accounting for fluid-to-fluid shear in between calculational cells over a wide range of flow conditions envisioned in reactor safety studies has been developed such that it may be easily implemented into a computer code such as COBRA-TF for more detailed subchannel analysis. At a given nodal height in the calculational model, equivalent hydraulic diameters are determined for each specific calculational cell using either laminar or turbulent velocity profiles. The velocity profile may be determined from a separate CFD (Computational Fluid Dynamics) analysis, experimental data, or existing semi-empirical relationships. The equivalent hydraulic diameter is then applied to the wall drag force calculation so as to determine the appropriate equivalent fluid-to-fluid shear caused by the wall for each cell based on the input velocity profile. This means of assigning the shear to a specific cell is independent of the actual wetted perimeter and flow area for the calculational cell. The use of this equivalent hydraulic diameter for each cell within a calculational subchannel results in a representative velocity profile which can further increase the accuracy and detail of heat transfer and fluid flow modeling within the subchannel when utilizing a thermal hydraulics systems analysis computer code such as COBRA-TF. Utilizing COBRA-TF with the flow modeling enhancement results in increased accuracy for a coarse-mesh model without the significantly greater computational and time requirements of a full-scale 3D (three-dimensional) transient CFD calculation. (authors)

  8. Temperature and void reactivity coefficient calculations for the high flux isotope reactor safety analysis report

    International Nuclear Information System (INIS)

    Engle, W.W. Jr.; Williams, L.R.

    1994-07-01

    This report provides documentation of a series of calculations performed in 1991 in order to provide input for the High Flux Isotope Reactor Safety Analysis Report. In particular, temperature and void reactivity coefficients were calculated for beginning-of-life, end-of-life, and xenon equilibrium (29 h) conditions. Much of the data used to prepare the computer models for these calculations was derived from the original HFIR nuclear design study

  9. Rock siting of nuclear power plants from a reactor safety standpoint. Status report October 1974

    International Nuclear Information System (INIS)

    1975-01-01

    The aim of this study is to clearify the advantages and disadvantages of an underground nuclear power plant from a reactor safety point of view, compared to a plant above ground. Principles for the technical design of a rock sited BWR nuclear power plant is presented. Also questions of sabotage and closing down the plant at the end of the operational period are treated. (K.K.)

  10. Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

    International Nuclear Information System (INIS)

    Farmer, Mitchell T.; Bunt, R.; Corradini, M.; Ellison, Paul B.; Francis, M.; Gabor, John D.; Gauntt, R.; Henry, C.; Linthicum, R.; Luangdilok, W.; Lutz, R.; Paik, C.; Plys, M.; Rabiti, Cristian; Rempe, J.; Robb, K.; Wachowiak, R.

    2015-01-01

    The overall objective of this study was to conduct a technology gap evaluation on accident tolerant components and severe accident analysis methodologies with the goal of identifying any data and/or knowledge gaps that may exist, given the current state of light water reactor (LWR) severe accident research, and additionally augmented by insights obtained from the Fukushima accident. The ultimate benefit of this activity is that the results can be used to refine the Department of Energy's (DOE) Reactor Safety Technology (RST) research and development (R&D) program plan to address key knowledge gaps in severe accident phenomena and analyses that affect reactor safety and that are not currently being addressed by the industry or the Nuclear Regulatory Commission (NRC).

  11. Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Farmer, Mitchell T. [Argonne National Lab. (ANL), Argonne, IL (United States); Bunt, R. [Southern Nuclear, Atlanta, GA (United States); Corradini, M. [Univ. of Wisconsin, Madison, WI (United States); Ellison, Paul B. [GE Power and Water, Duluth, GA (United States); Francis, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Gabor, John D. [Erin Engineering, Walnut Creek, CA (United States); Gauntt, R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Henry, C. [Fauske and Associates, Burr Ridge, IL (United States); Linthicum, R. [Exelon Corp., Chicago, IL (United States); Luangdilok, W. [Fauske and Associates, Burr Ridge, IL (United States); Lutz, R. [PWR Owners Group (PWROG); Paik, C. [Fauske and Associates, Burr Ridge, IL (United States); Plys, M. [Fauske and Associates, Burr Ridge, IL (United States); Rabiti, Cristian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rempe, J. [Rempe and Associates LLC, Idaho Falls, ID (United States); Robb, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Wachowiak, R. [Electric Power Research Inst. (EPRI), Knovville, TN (United States)

    2015-01-31

    The overall objective of this study was to conduct a technology gap evaluation on accident tolerant components and severe accident analysis methodologies with the goal of identifying any data and/or knowledge gaps that may exist, given the current state of light water reactor (LWR) severe accident research, and additionally augmented by insights obtained from the Fukushima accident. The ultimate benefit of this activity is that the results can be used to refine the Department of Energy’s (DOE) Reactor Safety Technology (RST) research and development (R&D) program plan to address key knowledge gaps in severe accident phenomena and analyses that affect reactor safety and that are not currently being addressed by the industry or the Nuclear Regulatory Commission (NRC).

  12. Radiological assessments, environmental monitoring, and study design

    International Nuclear Information System (INIS)

    Hansen, W.R.; Elle, D.R.

    1980-01-01

    Studies of the behavior of transuranic elements in the environment form the basic data for applied programs in radiological assessment, environmental monitoring, derivation of radiation-protection standards, and environmental impact statements. This chapter introduces some of the major information requirements of these applications of transuranic research data. Characteristics of the source terms from nuclear activities usually are needed for an analysis of environmental pathways or deployment of monitoring systems. Major inhalation and ingestion pathways are considered in assessments of hazards from transuranics and are discussed from the viewpoint of research needed

  13. European community light water reactor safety research projects. Experimental issue

    International Nuclear Information System (INIS)

    1975-01-01

    Research programs on light water reactor safety currently carried out in the European Community are presented. They cover: accident conditions (LOCA, ECCS, core meltdown, external influences, etc...), fault and accident prevention and means of mitigation, normal operation conditions, on and off site implications and equipment under severe accident conditions, and miscellaneous subjects

  14. 17. meeting of the Society for Reactor Safety. Proceedings

    International Nuclear Information System (INIS)

    1994-06-01

    An autonomous and independent reactor safety research in Germany is indispensable. Three out of the four papers of the meeting deal with the protective aim concept of NPP. Deterministic safety assessment during periodic in-service inspections, a new generation of information engineering, and the incorporation of serious accidents in the containment design of new reactors are considered in detail. (DG) [de

  15. Proceedings of the 4. CSNI workshop on the chemistry of iodine in reactor safety

    International Nuclear Information System (INIS)

    Guentay, S.

    1996-12-01

    The 4. OECD workshop on the chemistry of iodine in reactor safety was held in Wuerenlingen, Switzerland from June 10th to 12th, 1996. It was organised in collaboration with the Laboratory for Safety and Accident Research of the Paul Scherrer Institute. About seventy experts from fourteen OECD member countries attended the meeting, as well as experts from Latvia and the Commission of the European Communities. Thirty-four papers were presented in five sessions on various aspects of national and international programmes, integral and intermediate-scale experiments, experimental homogeneous phase chemistry, surface processes, thermodynamic and kinetic studies and safety applications. Throughout the meeting, emphasis was placed on detailed and open discussions. The purpose of the workshop was to exchange information on the iodine chemistry and other important fission products relevant to reactor safety, to discuss the status of the open issues identified during the previous workshop held in 1991, to define reactor safety issues and to discuss developments and future plans. (author) figs., tabs., refs

  16. Proceedings of the 4. CSNI workshop on the chemistry of iodine in reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Guentay, S [ed.; Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1996-12-01

    The 4. OECD workshop on the chemistry of iodine in reactor safety was held in Wuerenlingen, Switzerland from June 10th to 12th, 1996. It was organised in collaboration with the Laboratory for Safety and Accident Research of the Paul Scherrer Institute. About seventy experts from fourteen OECD member countries attended the meeting, as well as experts from Latvia and the Commission of the European Communities. Thirty-four papers were presented in five sessions on various aspects of national and international programmes, integral and intermediate-scale experiments, experimental homogeneous phase chemistry, surface processes, thermodynamic and kinetic studies and safety applications. Throughout the meeting, emphasis was placed on detailed and open discussions. The purpose of the workshop was to exchange information on the iodine chemistry and other important fission products relevant to reactor safety, to discuss the status of the open issues identified during the previous workshop held in 1991, to define reactor safety issues and to discuss developments and future plans. (author) figs., tabs., refs.

  17. Review of light water reactor safety through the Three Mile Island accident

    International Nuclear Information System (INIS)

    Phung, D.L.

    1984-05-01

    This review of light water reactor safety through the Three Mile Island accident has the purpose of establishing the baseline over which safety achievement post-TMI is assessed, and the need for new reactor designs and business direction is judged. Five major areas of reactor safety pre-TMI are examined: (1) safety philosophy and institutions, (2) reactor design criteria, (3) operational problems, (4) the Rasmussen reactor safety study, and (5) the TMI accident and repercussions. Although nuclear power has made spectacular achievements over the period pre-TMI and although TMI is technically a minor accident, this review concludes that there were basic flaws in the technology and in the manner safety philosophy was conceived and carried out. These flaws included (1) a reactor design that has high core power density, low heat capacity, and low system tolerance to upsets, (2) reactor deployment that had been expedited without extensive operational experience, (3) rules and regulations that had to play catch-up with commercial reactor development, (4) an industry that was fragmented, short-sighted, and tended to rely on the Nuclear Regulatory Commission for safety guidance, (5) information that was not effectively shared, and (6) attention that was inadequate to the human aspects of reactor operation and to public reaction to the specter of a reactor accident, major or minor

  18. Radiology

    International Nuclear Information System (INIS)

    Meyers, M.A.

    1989-01-01

    This paper reports on disease processes originating within the alimentary tract, may extend through the extraperitoneal spaces, and abnormalities primarily arising within other extraperitoneal sites may significantly affect the bowel. Symptoms and signs may be obscure, delayed, or nonspecific, and the area is generally not accessible to auscultation, palpation, or percussion. Radiologic evaluation thus plays a critical role

  19. Radiologic study of silicosis in Korean

    International Nuclear Information System (INIS)

    Park, Sun Ok; Rhee, Chung Sik; Kim, Hee Seap

    1982-01-01

    These radiologic studies were carried out on 265 cases of silicosis which were diagnosed clinically at Industrial Accident Hospital affiliated with Catholic Medical College, during the period of 3 years from 1974 to 1976. 265 cases od silicosis consisted of 96 cases (35%) of coal miner, 91 cases (34%) of coal choicer and 82 cases (31%) of others. The average age was 42.2 years and average working period was 9.2 years. Qualitative and quantitative features in the analysis of roentgen findings were based on UICC/Cincinnati and KLO classification. The qualitative features showed 26% of 'p' opacity, 46% of 'q' opacity, 4% of 'r' opacity as rounded profusion and 5% of 's' opacity, 11% of 't' opacity, 2% of 'u' opacity as irregular profusion of small opacities. Large opacities showed 3% of group A, 2% of group B and 1% of group C. Quantitative features revealed 25% of Type 1, 54% of Type 2, 16% of Type 3 and 5% of Type 4. The qualitative and quantitative features showed significant differences as age and working period increased. 70% of this study group were associated with radiological complications and complication rate was increased with age and working period. Major complications were pulmonary emphysema, tuberculosis and pleural abnormalities

  20. Radiologic study of silicosis in Korean

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sun Ok; Rhee, Chung Sik; Kim, Hee Seap [Ewha Womens University College of Medicine, Seoul (Korea, Republic of)

    1982-09-15

    These radiologic studies were carried out on 265 cases of silicosis which were diagnosed clinically at Industrial Accident Hospital affiliated with Catholic Medical College, during the period of 3 years from 1974 to 1976. 265 cases od silicosis consisted of 96 cases (35%) of coal miner, 91 cases (34%) of coal choicer and 82 cases (31%) of others. The average age was 42.2 years and average working period was 9.2 years. Qualitative and quantitative features in the analysis of roentgen findings were based on UICC/Cincinnati and KLO classification. The qualitative features showed 26% of 'p' opacity, 46% of 'q' opacity, 4% of 'r' opacity as rounded profusion and 5% of 's' opacity, 11% of 't' opacity, 2% of 'u' opacity as irregular profusion of small opacities. Large opacities showed 3% of group A, 2% of group B and 1% of group C. Quantitative features revealed 25% of Type 1, 54% of Type 2, 16% of Type 3 and 5% of Type 4. The qualitative and quantitative features showed significant differences as age and working period increased. 70% of this study group were associated with radiological complications and complication rate was increased with age and working period. Major complications were pulmonary emphysema, tuberculosis and pleural abnormalities.

  1. Radiologic study of osteomyelitis of the jaw

    International Nuclear Information System (INIS)

    Lee, Young Ho; Ahn, Hyung Kyu

    1980-01-01

    The author studied age and sex distribution, etiology, affected site and several radiographic features of osteomyelitis of the jaw. And radiologic classification of osteomyelitis was also done. The material consisted of 118 males and 96 females examined and/or treated under the diagnosis of osteomyelitis during past 11 years (1970-1980.6) in SNUDH. The obtained results were as followings. 1. The incidence is the highest in teen ages (22.9%) and the lowest in seventies. (2.8%). 2. 199 cases were found in lower jaw, and 15 cases in upper jaw. 30.8% of all cases were located at the posterior portion of mandibular body comprising alveolar region. 3. Radiographic examination of osteolytic lesion revealed that 21.5% of all patients had periapical and alveolar bone rarefaction combined with osteoporotic changes were present at the same time. 4. Sclerotic lesions were seen in 62.2% of all patients and 21.5% of sclerotic lesion were diffuse or homogenous type. 5. Based on the radiologic study, classification of the osteomyelitis of the jaw was made. Localized osteolytic type was the highest in incidence (38.8%) and localized sclerotic type was the lowest (7.0%).

  2. Impact of the Three Mile Island accident on reactor safety and licensing in Canada

    International Nuclear Information System (INIS)

    Harvie, J.D.

    1980-06-01

    This paper discusses the implications of the accident at Three Mile Island on reactor safety and licensing in Canada. Reactor safety principles which can be learned from, or are reaffirmed by, the accident are reviewed. It is concluded that reactor safety demands a firm commitment to safety by all those involved in the nuclear industry. (auth)

  3. Radiological research in Europe: a bibliometric study

    International Nuclear Information System (INIS)

    Mela, G.S.; Martinoli, C.; Poggi, E.; Derchi, L.E.

    2003-01-01

    . Although not flawless, and often criticized for a variety of reasons, citation analysis is a commonly used technique in this field, is a frequent means to ''weight'' the scientific production of researchers and is one of the criteria used to assign research grants. Our study shows that European radiology is growing and its production is increasing over time, thus indicating strong commitment to research from European radiologists; however, European radiological research has not yet reached leadership in the literature, and mean indexes addressing the level of resources allocated to research are lower in Europe than in the U.S. This latter point has notable exceptions, but indicates inadequacy of funding, at least in some nations, and in Europe as a whole. The development of research programs within the framework of the European Union specifically aimed to radiology could lead to further advancement of our discipline. (orig.)

  4. Tests for validation of fast neutron reactors safety

    International Nuclear Information System (INIS)

    Nagata, T.; Yamashita, H.

    2001-01-01

    Japanese scientific research and design enterprises in cooperation with industrial and power generating corporations implement a project on creating a fast neutron reactor of the ultimate safety. One of the basic expected results from such a development is creation of a reactor core structure that is able to eliminate recriticality occurrence in the course of reactor accident involving fuel melting. One of the possible ways to solve this problem is to include pipes (meant for specifying directed (controlled) molten fuel relocation) into fuel assembly structure. In the course of conduction and subsequent implementation of such a design the basic issue is to experimentally confirm the operating capacity of FA having such a structure and that is called FAIDUS. Within EAGLE Project on experimental basis of IAE NNC RK an activity has been started on preparation and conduction of out-of-pile and in-pile tests. During tests a sodium coolant will be used. Studies are conducted by NNC RK in cooperation with the Japanese corporations JAPC and JNC. Basic objective of out-of-pile tests was to obtain preliminary information on fuel relocation behavior under conditions simulating accident involving melting of core consisting of FAIDUS FA, which will help to clarify simulation criteria and to develop the most optimum structure of the experimental channel for reactor experiments conduction. The basic objective of in-pile tests was the experimental confirmation of operating capacity of FAIDUS FA model under reactor conditions. According to the program two tests are planned to be performed at IGR reactor: tests for validation of fast neutron reactor safety, and out-of-pile tests at EAGLE experimental facility without sodium coolant

  5. A Few Examples of ISPs Addressing Specific Reactor Safety Problems

    International Nuclear Information System (INIS)

    Reocreux, M.

    2008-01-01

    Four International Standard Problems which were related to safety reactor problems are briefly discussed. ISP-20 (Steam Generator Tube Rupture in DOEL 2) is a unique ISP as it is based on a real incident which occurred in a commercial Power Plant. This ISP clearly illustrated the special problems of an ISP based on a real plant, namely limited access to precise plant data, some lack in the detailed knowledge of sensor behaviour, etc. ISP-26 (ROSA IV-LSTF small break test) was an open ISP. A qualitatively good prediction of the measured events was obtained even if some modelling deficiencies were identified. ISP-27 (BETHSY Exp. 9.1 B) was a blind ISP. All important trends observed during the test were qualitatively calculated by most computer codes. However, some deficiencies in calculating some variables were evident. ISP-33 (PACTEL Natural Circulation) was an exercise with a test facility modelled on the basis of a Russian VVER 440 and with participations from Eastern and Western organisations. ISP-33 was a double-blind exercise. The simulation of some variables caused some problems although they were in principle not too complicated. Post-test calculations demonstrated significant improvements. For all the four ISPs, the influence of the code user was evident and caused some scatter in the results. A specific study was performed in ISP-26 to clarify from where those user effects were coming. The reactor safety problems related to those ISPs are detailed and the specific contribution of the ISPs to bring solutions is discussed.

  6. Radiological safety research for nuclear excavation projects - Interoceanic canal studies

    International Nuclear Information System (INIS)

    Klement, A.W. Jr.

    1969-01-01

    The general radiological problems encountered in nuclear cratering and nuclear excavation projects are discussed. Procedures for assessing radiological problems in such projects are outlined. Included in the discussions are source term, meteorology, fallout prediction and ecological factors. Continuing research requirements as well as pre- and post-excavation studies are important considerations. The procedures followed in the current interoceanic canal feasibility studies provide examples of radiological safety problems, current solutions and needed research. (author)

  7. Radiological safety research for nuclear excavation projects - Interoceanic canal studies

    Energy Technology Data Exchange (ETDEWEB)

    Klement, Jr, A W [U.S. Atomic Energy Commission, Las Vegas, NV (United States)

    1969-07-01

    The general radiological problems encountered in nuclear cratering and nuclear excavation projects are discussed. Procedures for assessing radiological problems in such projects are outlined. Included in the discussions are source term, meteorology, fallout prediction and ecological factors. Continuing research requirements as well as pre- and post-excavation studies are important considerations. The procedures followed in the current interoceanic canal feasibility studies provide examples of radiological safety problems, current solutions and needed research. (author)

  8. Research reactor safety - an overview of crucial aspects

    International Nuclear Information System (INIS)

    Laverie, M.

    1998-01-01

    Chronology of the commissioning orders of the French research reactors illustrates the importance of the time factor. When looking at older reactors, one must, on one hand, demonstrate, not only the absence of risks tied to the reactor's ageing, but, on the other hand, adapt the reactor's original technical designs to today's safety practices and standards. The evolution of reactor safety requirements over the last twenty years sometimes makes this adaptation difficult. The design of the next research reactors, after a one to two decades pause in construction, will require to set up new safety assessment bases that will have to take into account the nuclear power plant safety evolution. As a general statement, research reactor safety approaches will require the incorporation of specific design rules for research reactors: experience feedback for one of a kind design, frequent modifications required by research programmes, special operational requirements with operators/researchers interfaces. (author)

  9. Transactions of the nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1991-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 19th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 28--30, 1991. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from the governments and industry in Europe and Japan are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting, and are given in the order of their presentation in each session. The individual summaries have been cataloged separately

  10. Research reactor safety - an overview of crucial aspects

    Energy Technology Data Exchange (ETDEWEB)

    Laverie, M. [Atomic Energy Commission, Saclay, F-91191 Gif sur Yvette (France)

    1998-07-01

    Chronology of the commissioning orders of the French research reactors illustrates the importance of the time factor. When looking at older reactors, one must, on one hand, demonstrate, not only the absence of risks tied to the reactor's ageing, but, on the other hand, adapt the reactor's original technical designs to today's safety practices and standards. The evolution of reactor safety requirements over the last twenty years sometimes makes this adaptation difficult. The design of the next research reactors, after a one to two decades pause in construction, will require to set up new safety assessment bases that will have to take into account the nuclear power plant safety evolution. As a general statement, research reactor safety approaches will require the incorporation of specific design rules for research reactors: experience feedback for one of a kind design, frequent modifications required by research programmes, special operational requirements with operators/researchers interfaces. (author)

  11. Mortality study of Japanese radiological technologists

    International Nuclear Information System (INIS)

    Aoyama, T.; Futamura, A.; Yamamoto, Y.; Kato, H.; Sugahara, T.

    1983-01-01

    Japanese radiological technologists occupationally have chances of receiving low doses of ionizing radiation. A cohort study was started on them in 1981, since knowledge of the mortality and health of this population is pertinent to the evaluation of the risk from low-level exposure to radiation. A sampling of 2028 Japanese radiological technologists born before 1933 was followed from 1969 to 1982. All deaths were confirmed by checking copies of family registers and the causes were obtained from death certificates. The deaths observed within this group were compared with the expected number of deaths from major causes as estimated using the Japanese life table of 1975. The number of deaths from all causes, 131, was less than the expected 182.39, a difference that is statistically significant at the 1% level. The observed number of deaths from all malignant neoplasms, 51, was slightly larger than that of the expected 48.94, although the difference was not statistically significant. However, there was a significant excess of observed deaths from brain tumour and malignant neoplasms of male urogenital organs in comparison with expected deaths. Deaths from anaemia also significantly exceeded the expected level. The relationship between dose level and cause of death as adjusted by age at death and first year of employment was investigated using contingency table analysis. Accumulated occupational doses were estimated for 599 of the population of 2028. The relative risk of mortality ratios for all causes of death and cancer of all sites in four dose categories, <50, 50-74, 75-99 and 100+ rad, increased with dose but the statistical tests did not show any significant association. Observation and analysis should be continued to check our present findings further and obtain more complete data. (author)

  12. Bearings with a key role in nuclear reactor safety

    International Nuclear Information System (INIS)

    Jackson, J.

    1981-01-01

    The most critical period during the operation of heavy-duty pumps occurs at run-up, when sudden high loads coincide with below normal oil pressure. When those pumps are a key component of a nuclear reactor safety-system, reliability takes on a special meaning. Electricite de France recently invited a British company, Michell Bearings, to find a solution to these 'black-start' problems, the details of which are described in the following article

  13. Research and development program in reactor safety for NUCLEBRAS

    International Nuclear Information System (INIS)

    Pinheiro, R.B.; Resende Lobo, A.A. de; Horta, J.A.L.; Avelar Esteves, F. de; Lepecki, W.P.S.; Mohr, K.; Selvatici, E.

    1984-01-01

    With technical assistance from the IAEA, it was established recently an analytical and experimental Research and Development Program for NUCLEBRAS in the area of reactor safety. The main objectives of this program is to make possible, with low investments, the active participation of NUCLEBRAS in international PWR safety research. The analytical and experimental activities of the program are described with some detail, and the main results achieved up to now are presented. (Author) [pt

  14. Evaluation of the Community's nuclear reactor safety research programme

    International Nuclear Information System (INIS)

    Brandstetter, A.; Goedkoop, J.A.; Jaumotte, A.; Malhouitre, G.; Tomkins, B.; Zorzoli, G.B.

    1986-01-01

    This report describes an evaluation of the 1980-85 CEC reactor safety programme prepared, at the invitation of the Commission, by a panel of six independent experts by means of examining the relevant document and by holding hearings with the responsible CEC staff. It contains the recommendations made by the panel on the following topics: the need for the JRC to continue to make its competence in the reactor safety field available to the Community; the importance of continuity in the JRC and shared-cost action programmes; the difficulty of developing reactor safety research programmes which satisfy the needs of users with diverse needs; the monitoring of the utilization of the research results; the maintenance of the JRC computer codes used by the Member States; the spin-off from research results being made available to other industrial sectors; the continued contact between the JRC researchers and the national experts; the coordination of LWR safety research with that of the Member States; and, the JRC work on fast breeders to be planned with regard to the R and D programmes of the Fast Reactor European Consortium

  15. Reactor Safety Commission Code of Practice for Pressurized Water Reactors

    International Nuclear Information System (INIS)

    1990-01-01

    The Reactor Safety Commission of the Federal German Republic has summarized in the form of Official Guidelines the safety requirements which, in the Commission's view, have to be met in the design, construction and operation of a nuclear power station equipped with a pressurized water reactor. The Third Edition of the RSK Guidelines for pressurized water reactors dated 14.10.81. is a revised and expanded version of the Second Edition dated 24.1.79. The Reactor Safety Commission will with effect from October 1981 use these Guidelines in consultations on the siting of and safety concept for the installation approval of future pressurized water reactors and will assess these nuclear power stations during their erection in the light of these Guidelines. They have not however been immediately conceived for the adaptation of existing nuclear power stations, whether under construction or in operation. The scope of application of these Guidelines to such nuclear power stations will have to be examined for each individual case. The main aim of the Guidelines is to simplify the consultation process within the reactor Safety Commission and to provide early advice on the safety requirements considered necessary by the Commission. (author)

  16. Trends in fusion reactor safety research

    International Nuclear Information System (INIS)

    Herring, J.S.; Holland, D.F.; Piet, S.J.

    1991-01-01

    Fusion has the potential to be an attractive energy source. From the safety and environmental perspective, fusion must avoid concerns about catastrophic accidents and unsolvable waste disposal. In addition, fusion must achieve an acceptable level of risk from operational accidents that result in public exposure and economic loss. Finally, fusion reactors must control routine radioactive effluent, particularly tritium. Major progress in achieving this potential rests on development of low-activation materials or alternative fuels. The safety and performance of various material choices and fuels for commercial fusion reactors can be investigated relatively inexpensively through reactor design studies. These studies bring together experts in a wide range of backgrounds and force the group to either agree on a reactor design or identify areas for further study. Fusion reactors will be complex with distributed radioactive inventories. The next generation of experiments will be critical in demonstrating that acceptable levels of safe operation can be achieved. These machines will use materials which are available today and for which a large database exists (e.g. for 316 stainless steel). Researchers have developed a good understanding of the risks associated with operation of these devices. Specifically, consequences from coolant system failures, loss of vacuum events, tritium releases, and liquid metal reactions have been studied. Recent studies go beyond next step designs and investigate commercial reactor concerns including tritium release and liquid metal reactions. 18 refs

  17. Radiology

    International Nuclear Information System (INIS)

    Lissner, J.

    1985-01-01

    Diagnostic radiology is still the foremost of all innovative medical disciplines. This has many advantages but also some handicaps, e.g. the siting problem of medical equipment whose clinical potential is not fully known. This applies in particular to nuclear spin tomography, where the Laender governments and the Scientific Council seen to agree that all universities should have the appropriate equipment as soon as possible in order to intensify interdisciplinary research. Formerly, in the case of computerized tomography, there was less readiness. As a result, the siting of CT equipment is less organically structured. A special handicap of innovative fields is the problem of training and advanced training. The Chamber of Medicine and the Association of Doctors Participating in the Health Insurance Plan have issued regulations aimed at a better standardisation in this field. (orig.) [de

  18. Reactor safety in Eastern Europe. Proceedings

    International Nuclear Information System (INIS)

    1995-02-01

    The papers presented to the GRS colloquium refer to the cooperative activities for reactor accident analysis and modification of the GRS computer codes for their application to reactors of the Russian design types of WWER or RBMK. Another topic is the safety of RBMK reactors in particular, and the current status of investigations and studies addressing the containment of unit 4 of the Chernobyl reactor station. (HP) [de

  19. Radiological impact assessment in Bagjata uranium deposit: a case study

    International Nuclear Information System (INIS)

    Sarangi, A.K.; Bhowmik, S.C.; Jha, V.N.

    2007-01-01

    The uranium ore mining facility, in addition to the desirable product, produces wastes in the form of environmental releases or effluents to air, water and soil. The toxicological and other (non-radiological) effects are generally addressed in EIA/EMP studies as per MOEF guidelines. Since the uranium ore is radioactive, it is desirable to conduct a study on radiological effects considering the impacts of radiological releases to the environment. Before undertaking the commercial mining operations at Bagjata uranium deposit in the Singhbhum east district of Jharkhand, pre-operational radiological base line data were generated and a separate study on radiological impact on various environmental matrices was conducted in line with the International Atomic Energy Agency's laid out guidelines. The paper describes the philosophy of such studies and the findings that helped in formulating a separate environmental management plan. (author)

  20. Strategies for reactor safety. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, K

    1997-12-01

    The NKS/RAK-1 project formed part of a four-year nuclear research program (1994-1997) in the Nordic countries, the NKS Programme. The project aims were to investigate and evaluate the safety work, to increase realism and reliability of the safety analysis, and to give ideas for how safety can be improved in selected areas. An evaluation of the safety work in nuclear installations in Finland and Sweden was made, and a special effort was devoted to plant modernisation and to see how modern safety standards can be met up with. A combination of more resources and higher efficiency is recommended to meet requirements from plant modernisation and plant renovations. Both the utilities and the safety authorities are recommended to actively follow the evolving safety standards for new reactors. Various approaches to estimating LOCA frequencies have been explored. In particular, a probabilistic model for pipe ruptures due to intergranular stress corrosion has been developed. A survey has been done over methodologies for integrated sequence analysis (ISA), and different approaches have been developed and tested on four sequences. Structured frameworks for integration between PSA and behavioural sciences have been developed, which e.g. have improved PSA. The status of maintenance strategies in Finland and Sweden has been studied and a new maintenance data information system has been developed. (au) 41 refs.

  1. The PEC reactor. Safety analysis: Detailed reports

    Energy Technology Data Exchange (ETDEWEB)

    1988-01-01

    In the safety-analysis of the PEC Brasimone reactor (Italy), attention was focused on the role of plant-incident analysis during the design stage and the conclusions reached. The analysis regarded the following: thermohydraulic incidents at full power; incidents with the reactor shut down; reactivity incidents; core local faults; analysis of fuel-handling incidents; engineered safeguards and passive safety features; coolant leakage and sodium fires; research and development studies on the seismic behaviour of the PEC fast reactor; generalized sodium fire; severe accidents, accident sequences with shudown; reference accident. Both the theoretical and experimental analyses demonstrated the adequacy of the design of the PEC fast reactor, aimed at minimizing the consequences of a hypothetical disruptive core accident with mechanical energy release. It was shown that the containment barriers were sized correctly and that the residual heat from a disassembled core would be removed. The re-evaluation of the source term emphasized the conservative nature of the hypotheses assumed in the preliminary safety analysis for calculating the risk to the public.

  2. Gas-cooled breeder reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Chermanne, J.; Burgsmueller, P. [Societe Belge pour l' Industrie Nucleaire, Brussels

    1981-01-15

    The European Association for the Gas-cooled Breeder Reactor (G B R A), set-up in 1969 prepared between 1972 and 1974 a 1200 MWe Gas-cooled Breeder Reactor (G B R) commercial reference design G B R 4. It was then found necessary that a sound and neutral appraisal of the G B R licenseability be carried out. The Commission of the European Communities (C E C) accepted to sponsor this exercise. At the beginning of 1974, the C E C convened a group of experts to examine on a Community level, the safety documents prepared by the G B R A. A working party was set-up for that purpose. The experts examined a ''Preliminary Safety Working Document'' on which written questions and comments were presented. A ''Supplement'' containing the answers to all the questions plus a detailed fault tree and reliability analysis was then prepared. After a final study of this document and a last series of discussions with G B R A representatives, the experts concluded that on the basis of the evidence presented to the Working Party, no fundamental reasons were identified which would prevent a Gas-cooled Breeder Reactor of the kind proposed by the G B R A achieving a satisfactory safety status. Further work carried out on ultimate accident have confirmed this conclusion. One can therefore claim that the overall safety risk associated with G B R s compares favourably with that of any other reactor system.

  3. Strategies for reactor safety. Final report

    International Nuclear Information System (INIS)

    Andersson, K.

    1997-12-01

    The NKS/RAK-1 project formed part of a four-year nuclear research program (1994-1997) in the Nordic countries, the NKS Programme. The project aims were to investigate and evaluate the safety work, to increase realism and reliability of the safety analysis, and to give ideas for how safety can be improved in selected areas. An evaluation of the safety work in nuclear installations in Finland and Sweden was made, and a special effort was devoted to plant modernisation and to see how modern safety standards can be met up with. A combination of more resources and higher efficiency is recommended to meet requirements from plant modernisation and plant renovations. Both the utilities and the safety authorities are recommended to actively follow the evolving safety standards for new reactors. Various approaches to estimating LOCA frequencies have been explored. In particular, a probabilistic model for pipe ruptures due to intergranular stress corrosion has been developed. A survey has been done over methodologies for integrated sequence analysis (ISA), and different approaches have been developed and tested on four sequences. Structured frameworks for integration between PSA and behavioural sciences have been developed, which e.g. have improved PSA. The status of maintenance strategies in Finland and Sweden has been studied and a new maintenance data information system has been developed. (au)

  4. Gas-cooled fast reactor safety

    International Nuclear Information System (INIS)

    Rickard, C.L.; Simon, R.H.; Buttemer, D.R.

    1977-01-01

    Initial conceptual design work on the GCFR began in the USA in the early 1960s and since the later 1960s has proceeded with considerable international cooperation. A 300 MWe GCFR demonstration plant employing three main cooling loops is currently being developed at General Atomic. A major preapplication licensing review of this demonstration plant was initiated in 1971 leading in 1974 to publication of a Safety Evaluation Report by the USAEC Directorate of Licensing. The preapplication review is continuing by addressing areas of concern identified in this report such that a major part of the work necessary to support the actual licensing of a GCFR demonstration plant has been established. The safety performance of the GCFR demonstration plant is based upon its inherent safety characteristics among which are the single phase and chemically inert coolant which is not activated and has a low reactivity worth, the negative core power and temperature reactivity coefficients and the small and negative steam reactivity worth. Recent studies of larger core designs indicate that as the reactor size increases central fuel, clad and coolant reactivity worths decrease and the Doppler coefficient becomes more negative. These inherent safety characteristics are complemented by safety design features such as enclosing the entire primary coolant system within a prestressed concrete pressure vessel (PCRV), providing two independent and diverse shutdown systems and residual heat removal (RHR) systems, limiting the worth of control rods to less than $1, employing pressure-equalized fuel rods, a core supported rigidly at its upper end and otherwise unrestrained and coolant downflow within the core to enhance debris removal should local melting occur. The structurally redundant PCRV design allows the potential depressurization leak area to be controlled and, since the PCRV is located within a containment building, coolant is present even after a depressurization accident and each RHR

  5. General Employee Radiological Training: Study guide

    International Nuclear Information System (INIS)

    1992-10-01

    Upon completion of this class, the participant will be able to discuss his/her responsibilities for maintaining exposures to radiation and radioactive material As Low As Reasonably Achievable. The participant will be able to select the correct response from a group of responses which verifies his/her ability to: Identify natural background and man-made sources of radiation; state the whole body radiation exposure limit for non-radiological workers; state the potential biological effects from chronic radiation exposure; identify the ALARA concept and practices; state methods used to control radiological material; and state employee responsibilities for the ALARA Program

  6. Swedish Nuclear Power Inspectorate, Office of Reactor Safety. Research plans for the period 1997-1999

    International Nuclear Information System (INIS)

    1997-02-01

    Office of Reactor Safety research is carried out within the following areas: Safety evaluation, Safety analysis, MTO, Materials and chemistry, Non-Destructive Testing, Strength of materials, Thermohydraulics, Nuclear fuel, Serious accidents and Process control. Research is carried out to fulfill SKIs overall goals in accordance with the directives from the Swedish government and parliament, in particular to be a driving force in safety related work when justified by operating experience, research results and technical progress, towards licensees as well as in international cooperation in safety; to promote the maintenance and development of competence in the safety related work at the SKI as well as the licensees and generally in the country, and as a specific role for the Office of Reactor Safety as designated in the internal routines to take initiative to encourage and carry out research into areas of importance for the Office as well as ensuring that research results are disseminated and used both within SKI and in the general work concerning nuclear safety. Research efforts within the Office of Reactor safety are carried out in the form of separate projects which form part of the priority work plans. Project managers, the necessary personnel resources and the budget for each year are included in the Annual Plan and the work is followed up in the same manner as other efforts. Research is performed in different ways, that can vary from laboratory studies to more consultative efforts, and be organised in many different ways such as examination projects, post-graduate studies, work sponsored at research institutes and companies in Sweden and abroad, collaboration in larger international projects, and participation in conferences which provide an important contribution to keeping SKI personnel informed within their specialist areas

  7. Proceedings of the Third CSNI Workshop on Iodine Chemistry in Reactor Safety

    International Nuclear Information System (INIS)

    Ishigure, K.; Saeki, M.; Soda, K.; Sugimoto, J.

    1992-03-01

    The Third CSNI Workshop on Iodine Chemistry in Reactor Safety was held at Tokai Research Establishment of Japan Atomic Energy Research Institute at Tokai-mura, Ibaraki-ken, Japan, on September 11 to 13, 1991. About 60 experts attended the Workshop from 10 countries and 2 international organizations. In the Workshop, 29 papers were presented in five sessions on various aspects of iodine chemistry in reactor safety, such as radiolytic and surface reactions of iodine species, fundamental and integral tests, modeling and code developments. The information exchanged and the discussions followed resulted in extended and promoted understanding of iodine behavior in accidents of light water reactors and also gave a large expectation for the further progresses coming in the future. It should be emphasized that a most important and unique forum has been established through the Workshop for exchanging information and collaboratively solving the important problems in the field of the iodine chemistry in nuclear reactor safety. At the Workshop, an effort was made to integrate all information for better use by safety analysts. There is no doubt that a lot of information on iodine behaviour has been accumulated, but in many cases this information needs to be co-ordinated and well organised for safety analyses of nuclear reactors. It is essential that the results of laboratory studies and integral experiments together with modelling activities are well co-ordinated. Therefore, the goal was: - to review the knowledge and understanding of the chemistry of iodine of relevance to the prediction of its behaviour in nuclear reactors during a range of operational and accident conditions; - to define those areas of chemistry which are important but poorly understood and require further study. As shown by the conclusions of the Workshop, there is no doubt that this objective was widely attained

  8. Some considerations for assurance of reactor safety from experiences in research reactors

    International Nuclear Information System (INIS)

    Okamoto, Sunao; Nishihara, Hideaki; Shibata, Toshikazu

    1981-01-01

    For the purpose of assuring reactor safety and strengthening research in the related fields, a multi-disciplinary group was formed among university researchers, including social scientists, with a special allocation of the Grant-in-Aid from the Ministry of Education, Science and Culture. An excerpt from the first year's report (1979 -- 1980) is edited here, which contains an interpretation of Murphy's reliability engineering law, a scope of reactor diagnostic studies to be pursued at universities, and safety measures already implemented or suggested to be implemented in university research reactors. (author)

  9. Points of emphasis and objectives of reactor safety research

    International Nuclear Information System (INIS)

    Krewer, K.H.

    1982-01-01

    Reactor safety research is part of the presently running second programme on energy research and energy-engineering with which the Federal Government is connecting a whole bundle of economic and ecological aims: medium- and long-term assurance of energy supply, provision and efficient utilization of energy at favourable economic total costs, improvement of the technological performance, consideration of the requirements of the environmental protection, of the careful treatment of the resources, as well as of the protection of the population and personnel from the risks of conversion and use of energy. (orig.) [de

  10. Nuclear power reactor safety research activities in CIAE

    International Nuclear Information System (INIS)

    Pu Shendi; Huang Yucai; Xu Hanming; Zhang Zhongyue

    1994-01-01

    The power reactor safety research activities in CIAE are briefly reviewed. The research work performed in 1980's and 1990's is mainly emphasised, which is closely related to the design, construction and licensing review of Qinshan Nuclear Power Plant and the safety review of Guangdong Nuclear Power Station. Major achievements in the area of thermohydraulics, nuclear fuel, probabilistic safety assessment and severe accident researches are summarized. The foreseeable research plan for the near future, relating to the design and construction of 600 MWe PWR NPP at Qinshan Site (phase II development) is outlined

  11. The impact of WASH-1400 on reactor safety evaluation

    International Nuclear Information System (INIS)

    Tanguy, P.Y.

    1976-01-01

    Trends in reactor safety evaluation in France following the publication of WASH-1400 (the Rasmussen Report) are presented. What is called 'the meteorite case' is first schematically presented as follows: WASH-1400 shows nuclear risk equivalent to meteorite risk and reasonable corrections cannot make many orders of magnitude, consequently present safety rules are adequate. The very impact of WASH-1400 on safety approach is then discussed as for: assistance to deterministic safety analysis, introduction of probabilistic safety criteria, acceptable level of risk, and the use of results in research and reactor operating experience

  12. Review of irradiation experiments for water reactor safety research

    International Nuclear Information System (INIS)

    Tobioka, Toshiaki

    1977-02-01

    A review is made of irradiation experiments for water reactor safety research under way in both commercial power plants and test reactors. Such experiments are grouped in two; first, LWR fuel performance under normal and abnormal operating conditions, and second, irradiation effects on fracture toughness in LWR vessels. In the former are fuel densification, swelling, and the influence of power ramp and cycling on fuel rod, and also fuel rod behavior under accident conditions in in-reactor experiment. In the latter are the effects of neutron exposure level on the ferritic steel of pressure vessels, etc.. (auth.)

  13. A radiologic study of salivary stones

    International Nuclear Information System (INIS)

    Cho, Hyo Suck; Ahn, Hyung Kyu

    1986-01-01

    The author examined fifty cases of sialolithiasis diagnosed in the Dept. of Oral Radiology in SNUH by conventional radiography and sialography, and patient's age, sex, location, radiodensity, numbers, shapes, and relation with ducts a nd parenchymas. The results of this study were as follows: 1. The average age of patients was 38.6 years in submandibular sialolithiasis, and 39.2 years in parotid sialolithiasis. 2. There was slightly higher incidence in males (58.0%) than in females (42.0%). 3. Salivary stones were found to be much more in the submandibular gland and duct (82.0%) than in the parotid gland and duct (18.0%). 4. Of 62 submandibular salivary stones, 33 (53.2%) occurred in the main duct, 25 (40.3%) occurred in the hilum, and 4 (6.5%) occurred in the parenchyma. Of 18 parotid salivary stones, 9(50.0%) occurred in the main duct, 5(27.8%) occurred in the parenchyma, and 4 (22 .2%) occurred in the hilum. 5. Of the submandibular salivary stones, the number of radiopaque type was 45 (75.8%), and the number of radiolucent type was 17 (24.2%). Of the parotid salivary stones, the number of radiopaque type was 12 (66.7%), and the number of radiolucent type was 6 (33.3%). 6. The single type was 30 cases (73.2%) in submandibular gland, 6 cases (66.7%) in parotid gland, and the multiple type was 11 cases (26.8%) in submandibular grand, and 3 cases (33. 3%) in parotid gland. 7. Round shape was 35 cases (43.8%), ovoid shape was 22 cases (27.5%), irregular shape was 17 cases (21.3%), and cylindrical shape was 6 cases (7.5%).

  14. Panel plenary session: Status and future needs in the field of reactor safety research

    International Nuclear Information System (INIS)

    Finzi, S.; Cicognani, G.; Heusener, G.; Geijzers, H.F.G.; Alonso-Santos, A.; Holtbecker, H.F.

    1990-01-01

    Status and future needs in the field of reactor safety research. Overviews are given of the nuclear programme in France and the Netherlands. Spanish and Italian reactor safety research both current and for the future is outlined. LWR safety and the continuation of the establishment of safety standards particularly for LMFBR reactors is discussed. The new framework for the research in reactor safety by the Commission of the European Communities for 1990-1994 is outlined. The discussion which followed is reported. (UK)

  15. Application of software to development of reactor-safety codes

    International Nuclear Information System (INIS)

    Wilburn, N.P.; Niccoli, L.G.

    1980-09-01

    Over the past two-and-a-half decades, the application of new techniques has reduced hardware cost for digital computer systems and increased computational speed by several orders of magnitude. A corresponding cost reduction in business and scientific software development has not occurred. The same situation is seen for software developed to model the thermohydraulic behavior of nuclear systems under hypothetical accident situations. For all cases this is particularly noted when costs over the total software life cycle are considered. A solution to this dilemma for reactor safety code systems has been demonstrated by applying the software engineering techniques which have been developed over the course of the last few years in the aerospace and business communities. These techniques have been applied recently with a great deal of success in four major projects at the Hanford Engineering Development Laboratory (HEDL): 1) a rewrite of a major safety code (MELT); 2) development of a new code system (CONACS) for description of the response of LMFBR containment to hypothetical accidents, and 3) development of two new modules for reactor safety analysis

  16. Considerations concerning the reliability of reactor safety equipment

    International Nuclear Information System (INIS)

    Furet, J.; Guyot, Ch.

    1967-01-01

    A review is made of the circumstances which favor a good collection of maintenance data at the C.E.A. The large amount of data to be treated has made necessary the use of a computer for analyzing automatically the results collected. Here, only particular aspects of the reliability from the point of view of the electronics used for nuclear reactor control will be dealt with: sale and unsafe failures; probability of survival (in the case of reactor safety); availability. The general diagrams of the safety assemblies which have been drawn up for two types of reactor (power reactor and low power experimental reactor) are given. Results are presented of reliability analysis which could be applied to the use of functional modular elements, developed industrially in France. Improvement of this reliability appears to be fairly limited by an increase in the redundancy; on the other hand it is shown how it may be very markedly improved by the use of automatic tests with different frequencies for detecting unsafe failures rates of measurements for the sub-assemblies and for the logic sub-assemblies. Finally examples are given to show the incidence of the complexity and of the use of different technologies in reactor safety equipment on the reliability. (authors) [fr

  17. Advanced nuclear reactor safety issues and research needs

    International Nuclear Information System (INIS)

    2002-01-01

    On 18-20 February 2002, the OECD Nuclear Energy Agency (NEA) organised, with the co-sponsorship of the International Atomic Energy Agency (IAEA) and in collaboration with the European Commission (EC), a Workshop on Advanced Nuclear Reactor Safety Issues and Research Needs. Currently, advanced nuclear reactor projects range from the development of evolutionary and advanced light water reactor (LWR) designs to initial work to develop even further advanced designs which go beyond LWR technology (e.g. high-temperature gas-cooled reactors and liquid metal-cooled reactors). These advanced designs include a greater use of advanced technology and safety features than those employed in currently operating plants or approved designs. The objectives of the workshop were to: - facilitate early identification and resolution of safety issues by developing a consensus among participating countries on the identification of safety issues, the scope of research needed to address these issues and a potential approach to their resolution; - promote the preservation of knowledge and expertise on advanced reactor technology; - provide input to the Generation IV International Forum Technology Road-map. In addition, the workshop tried to link advancement of knowledge and understanding of advanced designs to the regulatory process, with emphasis on building public confidence. It also helped to document current views on advanced reactor safety and technology, thereby contributing to preserving knowledge and expertise before it is lost. (author)

  18. Adapting a reactor safety assessment system for specific plants

    International Nuclear Information System (INIS)

    Ballard, T.L.; Cordes, G.A.

    1991-01-01

    The Reactor Safety Assessment System (RSAS) is an expert system being developed by the Idaho National Engineering Laboratory, the University of Maryland (UofM) and US Nuclear Regulatory Commission (NRC) for use in the NRC Operations center. RSAS is designed to help the Reactor Safety Team monitor and project core status during an emergency at a licensed nuclear power plant. Analysis uses a hierarchical plant model based on equipment availability and automatically input parametric plant information. There are 3 families of designs of pressurized water reactors and 75 plants using modified versions of the basic design. In order to make an RSAS model for each power plant, a generic model for a given plant type is used with differences being specified by plant specific files. Graphical displays of this knowledge are flexible enough to handle any plant configuration. A variety of tools have been implemented to make it easy to modify a design to fit a given plant while minimizing chance for error. 3 refs., 4 figs

  19. Reactor safety instrumentation of Paks NPP (experience and perspective)

    International Nuclear Information System (INIS)

    Elo, S.; Hamar, K.

    1993-01-01

    The majority of the existing control and protection systems in nuclear power plants use old analog technology and design philosophy. Maintenance and the procurement of spare parts is becoming increasingly difficult. In general there is an age degradation concern. Aging degradation in nuclear power plants must be effectively managed to avoid a loss of vital safety function, shutdown of the station, a reduced power generation, or any failure leading to expensive repair. Even with the best efforts in developing reliable and long life instrumentation and control systems for nuclear power plants it is expected that these systems for most plants will require replacements during the life of the plants. The instrumentation and control system of the nuclear power plants designed during the 70's and constructed in the 80's went out-of-date since nuclear safety is not a static concept and the digital computer technology has undergone rapid improvements during the 70's and 80's. Simultaneously the operation and the maintenance of the I ampersand C system of those plants described above becomes more and more difficult and expensive. In this context the pure quality of the former Soviet designed process instrumentation system increases the needs of upgrading this system. The author reviews the main design characteristics of the reactor safety instrumentation of the Paks NPP. Further he attempts to convey the perspective on upgrading the reactor safety instrumentation as seen by the HAEC and its Nuclear Safety Inspectorate

  20. A study on urinary radiologic technology

    International Nuclear Information System (INIS)

    Kim, Young San; Park, Hong Jun; Cheung, Hwan

    1984-01-01

    The Roentgenographic examination of the urinary diseases has become an important part of the diagnostic method for the detection of diseases in human being nowadays. We are concerned about the urinary roentgenography and anatomy and pathology for the diagnostic of the urinary diseases. Be based on the proceeding statement, we have to obtain with the diagnostic effects in proper for the diagnostic exposures. In addition to, we'd like to stress on the radiological anatomy and for the technologist and also discuss about pathological aspect

  1. Radiological study of bronchial mucoid impaction

    International Nuclear Information System (INIS)

    Yu Xiaoyi; Yan Hongzhen; Wang Tongde; Gan Chunlan; Liu Wei; Wang Linhui

    1999-01-01

    Objective: To evaluate the radiological findings of bronchial mucoid impaction in 28 patients in order to improve diagnostic efficacy. Methods: Standard posteroanterior high voltage radiographs were performed in all 28 cases. Among them CT scans were taken in 14 cases, while 3 patients underwent HRCT examination at the same time. Twenty-two patients had a history of expectoration of mucous plugs; in one case with pulmonary atelectasis, a mucous plug was picked out through bronchoscopy. The other 5 cases experienced a lung operation, and a tumor and bronchial mucoid impaction were discovered. Results: Radiographs showed most mucoid impaction as thick, branching structures resembling branches of tree; others were in the shapes of spherical, small clubs, and cuttle fish. In one patient, pulmonary atelectasis was the only radiographic finding. Similarly on CT, most bronchial mucoid impaction were likened to tree branches; the rest presented as small clubs and bunches of grape. A prominent feature of bronchial mucoid impaction, either on plain radiograph or on CT, was that its axis pointed to the hilum, completely consistent with the branching and distribution of the bronchi, and accompanied by bronchiectasis. Conclusions: It is an optimal approach to exploit plain radiograph combined with CT to find out bronchial mucoid impaction. An awareness of its clinical and radiological features may improve better understanding and recognition of the disease

  2. SACRD: a data base for fast reactor safety computer codes, contents and glossary of Version 1 of the system

    International Nuclear Information System (INIS)

    Greene, N.M.; Forsberg, V.M.; Raiford, G.B.; Arwood, J.W.; Flanagan, G.F.

    1979-01-01

    SACRD is a data base of material properties and other handbook data needed in computer codes used for fast reactor safety studies. This document lists the contents of Version 1 and also serves as a glossary of terminology used in the data base. Data are available in the thermodynamics, heat transfer, fluid mechanics, structural mechanics, aerosol transport, meteorology, neutronics and dosimetry areas. Tabular, graphical and parameterized data are provided in many cases

  3. Perspectives of expert systems in the field of reactor safety

    International Nuclear Information System (INIS)

    Bastl, W.

    1989-01-01

    The furure potential of expert systems is based on the following factors: the efficient storage of information in the knowledge basis, the efficient use of comprehensive information bases, the interactive approach, the rapid production of prototypes. The main problems which are encountered at present relate to the input of knowledge derived from experience, the qualification of the contents of the knowledge bases and to the interfacing to technical processes, as real time work is required in such cases. However, the practical use of expert systems in reactor safety is expected to make considerable progress. The following preferred fields should be mentioned: knowledge bases and analysis tools for safety investigations, diagnostic and practising systems for safe operation and, above all in the field of accident management, trainers, in-situ guiding systems or information systems in supraregional guiding centers. (orig./DG) [de

  4. Nuclear reactor safety research since Three Mile Island

    International Nuclear Information System (INIS)

    Mynatt, F.R.

    1982-01-01

    The Three Mile Island nuclear power plant accident has resulted in redirection of reactor safety research priorities. The small release to the environment of radioactive iodine-13 to 17 curies in a total radioactivity release of 2.4 million to 13 million curies-has led to a new emphasis on the physical chemistry of fission product behavior in accidents; the fact that the nuclear core was severely damaged but did not melt down has opened a new accident regime-that of the degraded core; the role of the operators in the progression and severity of the accident has shifted emphasis from equipment reliability to human reliability. As research progresses in these areas, the technical base for regulation and risk analysis will change substantially

  5. Nuclear reactor safety research since three mile island.

    Science.gov (United States)

    Mynatt, F R

    1982-04-09

    The Three Mile Island nuclear power plant accident has resulted in redirection of reactor safety research priorities. The small release to the environment of radioactive iodine-13 to 17 curies in a total radioactivity release of 2.4 million to 13 million curies-has led to a new emphasis on the physical chemistry of fission product behavior in accidents; the fact that the nuclear core was severely damaged but did not melt down has opened a new accident regime-that of the degraded core; the role of the operators in the progression and severity of the accident has shifted emphasis from equipment reliability to human reliability. As research progresses in these areas, the technical base for regulation and risk analysis will change substantially.

  6. Artificial neural network for research reactor safety status monitoring

    International Nuclear Information System (INIS)

    Varde, P.V.

    2001-01-01

    During reactor upset/abnormal conditions, emphasis is placed on plant operator's ability to quickly identify the problem and perform diagnosis and initiate recovery action to ensure safety of the plant. However, the reliability of human action is adversely affected at the time of crisis, due to the time stress and psychological factors. Availability of operational aids capable of monitoring the status of the plant and quickly identifying the deviation from normal operation is expected to significantly improve the operator reliability. Artificial Neural Network (based on Back Propagation Algorithm) has been developed and applied for reactor safety status monitoring, as part of an Operator Support System. ANN has been trained for 14 different plant states using 42 input symptom patterns. Recall tests performed on the ANN show that the system was able to identify the plant state with reasonable accuracy. (author)

  7. Annual report 1986 of Society for Reactor Safety (GRS)

    International Nuclear Information System (INIS)

    1987-01-01

    The overall development of Society for Reactor Safety (GRS) is indicated by its annual volume of achievement. After initially high growth rates that achievement has come to stand at some 62 million marks or so over the last years. GRS today employs some 450 staff, of which 325 are scientific-technical experts representing altogether nearly 4000 man-years of experience in nuclear technology. The report presents essential results from the main points of activity of GRS over 10 years. In accordance with the aim of the institution they primarily cover projects in the sectors safety and radiation protection for nuclear facilities. Since 1985, since the extension of its contract of associates, GRS has also increasingly been concerned with safety questions in non-nuclear technology, concentrating mainly on the transfer of existing methods. (orig./DG) [de

  8. Historical perspective of thermal reactor safety in light water reactors

    International Nuclear Information System (INIS)

    Levy, S.

    1986-01-01

    A brief history of thermal reactor safety in U.S. light water reactors is provided in this paper. Important shortcomings in safety philosophy evolution versus time are identified and potential corrective actions are suggested. It should be recognized, that this analysis represents only one person's opinion and that most historical accountings reflect the author's biases and specific areas of knowledge. In that sense, many of the examples used in this paper are related to heat transfer and fluid flow safety issues, which explains why it has been included in a Thermal Hydraulics session. One additional note of caution: the value of hindsight and the selective nature of human memory when looking at the past cannot be overemphasized in any historical perspective

  9. Reactor safety under design basis flood condition for inland sites

    International Nuclear Information System (INIS)

    Hajela, S.; Bajaj, S.S.; Samota, A.; Verma, U.S.P.; Warudkar, A.S.

    2002-01-01

    Full text: In June 1994, there was an incident of flooding at Kakrapar Atomic Power Station (KAPS) due to combination of heavy rains and mechanical failure in the operation of gates at the adjoining weir. An indepth review of the incident was carried out and a number of flood protection measures were recommended and were implemented at site. As part of this review, a safety analysis was also done to demonstrate reactor safety with a series of failures considered in the flood protection features. For each inland NPP site, as part of design, different flood scenarios are analysed to arrive at design basis flood (DBF) level. This level is estimated based on worst combination of heavy local precipitation, flooding in river, failure of upstream/downstream water control structures

  10. Progress toward international agreement to improve reactor safety

    International Nuclear Information System (INIS)

    Lieberman, J.I.; Graham, B.

    1993-01-01

    Representatives of nearly one-half of the 114 member states of the International Atomic Energy Agency (IAEA), including the United States, have participated in the development of an international nuclear safety conventions proposed multilateral treaty to improve civil nuclear power reactor safety. A preliminary draft of the convention has been developed (referred to as the draft convention for this report), but discussions are continuing, and when the final convention text will be completed and presented to IAEA member states for signature is uncertain. This report responds to the former and current Chairman's request that we provide information on the development of the nuclear safety convention, including a discussion of (1) the draft convention's scope and objectives, (2) how the convention will be implemented and monitored, (3) the views of selected country representatives on what provisions should be included in the draft convention, and (4) the convention's potential benefits and limitations

  11. NRC/DAE reactor safety research Data Bank

    International Nuclear Information System (INIS)

    Laats, E.T.

    1982-01-01

    In 1976, the United States Nuclear Regulatory Commission (NRC) established the NRC/Division of Accident Evaluation (DAE) Data Bank to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. This program has since grown from the conceptual stage to a useful, usable service for computer code development, code assessment, and experimentation groups in meeting the needs of the nuclear industry. Data from 20 facilities are now processed and permanently stored in the Data Bank, which utilizes the Control Data Corporation (CDC) CYBER 176 computer system located at the Idaho National Engineering Laboratory (INEL). New data and data sources are continually being added to the Data Bank. In addition to providing data storage and access software, the Data Bank program supplies data entry, documentation, and training and advisory services to users and the NRC. Management of the NRC/DAE Data Bank is provided by EG and G Idaho, Inc

  12. Thirteenth water reactor safety research information meeting: proceedings Volume 1

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1986-02-01

    This six-volume report contains 151 papers out of the 178 that were presented at the Thirteenth Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 22-25, 1985. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included thirty-one different papers presented by researchers from Japan, Canada and eight European countries. The title of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume presents information on: risk analysis PRA application; severe accident sequence analysis; risk analysis/dependent failure analysis; and industry safety research

  13. Prioritization of R and D programs on probabilistic reactor safety

    International Nuclear Information System (INIS)

    Husseiny, A.A.

    1982-01-01

    An interactive computer code based on the multiattribute utility theory has been developed with graphic capabilities to use in selection of probabilistic reactor safety RandD programs. Utility values and proper graphic representation are made through lottery games on the computer terminal. The code is applied to prioritize a set of RandD programs on LWR safety based on attributes including regulatory issues, institutional issues and operation problems. The methodology is described here in detail with its applications. Some of the input includes statistical distributions and subjective judgments on institutional issues. The flexibility of the approach provides a tool for decision makers whether on individual or group level to assess LWR safety priorities and continuously update their strategies

  14. Twenty-First Water Reactor Safety Information Meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25-27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database

  15. List of reports in reactor safety research by BMFT, EPRI, JSTA, and USNRC

    International Nuclear Information System (INIS)

    1981-05-01

    This list reviews reports from the Federal Republic of Germany, from the United States of America and from Japan concerning special problems in the field of reactor safety research. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. (orig./HP) [de

  16. State of arts and outlook of research reactor safety management promoted by IAEA

    International Nuclear Information System (INIS)

    Hao Xiaofeng

    2005-01-01

    This paper presents the recent activities of IAEA on the research reactor safety, and the trends in the future. According to the present situation of national research reactors, some suggestions are proposed for the cooperation with IAEA on research reactor safety. (author)

  17. Recommendations of the Reactor Safety Commission, 1971--1974

    International Nuclear Information System (INIS)

    The Reactor Safety Commission (RSC) of the German Federal Republic was created in 1958 by the then Federal Minister for Atomic Energy and Hydroeconomy. Its task included the advising of the Federal Minister responsible for protection of the population from possible dangers occurring during peaceful utilization of nuclear energy and in all matters of the safety of nuclear oriented installations. The RSC consists of independent experts from differing specialty areas. The results of their consultations are passed on in recommendations to the appropriate Federal Minister. Since the reappointment and reorganization of the RSC in the year 1971 by the then Federal Minister for Education and Science, the recommendations have been published in the ''Federal Gazette.'' The report presented is divided into two parts with a three part appendix. All recommendations of the RSC made since the reorganization (68th Meeting on 3 November 1971) until expiration of the last appointment, (96th Meeting on 25 July 1974) are compiled in the first section. The second part contains all announcements of the RSC which have appeared in the ''Federal Gazette.'' These concern training, agenda, as well as current members. Appendix A includes the ''Guidelines for Pressurized Water Reactors'' approved in the 93rd Meeting on 24 April 1974. Two key word listings follow in Sections B and C of the Appendix. The report was prepared in behalf of the Federal Minister of the Interior through the Office of the RSC assigned to the Institute for Reactor Safety of the Technical Inspection Association (IRS). The report is continued at regular intervals following each meeting period

  18. Recommendations of the Reactor Safety Commission (RSK) 1975-1977. Vol. 3

    International Nuclear Information System (INIS)

    Schneider, M.

    1978-08-01

    After the recommendations are published in the 'Bundesanzeiger' the Office of the RSK publishes them as a closed report, by order of the Federal Minister of the Interior. The reports are devided in two parts: Part I contains the recommendations which are given by the RSK; part II contains the official notices concerning the RSK. There also is a subject index. Three volumes are published by now: Volume 1: IRS-A-9 (December 1975), Recommendations of the RSK 1971 to 1974 (68th to 96th meeting), pages: I-1 to I-116 and II-1 to II-23 appendix a: RSK-guide lines for PWR, edition 04.74; Volume 2: IRS-A-11 (August 1976), Recommendations of the RSK 1974 to 1975, (97th to 105th meeting), pages: I-117 to I-145; Volume 3: GRS-12 (August 1978), Recommendations of the RSK 1975 to 1977 (106th to 129th meeting), pages: I-146 to I-276 and II-24 to II-25. Volume 3 also contains the recommendation on German Fuel Cycle Center which was given by the Reactor Safety Commision (RSK) in community with the Radiological Protection Commission (SSK), in autumn 1977. (orig./HP) 891 HP [de

  19. Radiation protection study of radiology medical workers in radiodiagnosis area

    International Nuclear Information System (INIS)

    Gaona, E.; Canizal, C.; Garcia, M.A.; Orozco, M.; Rincon, A.; Padilla, Y.; Martinez, A.

    1996-01-01

    Aspects related to radiological safety and its organization in radiodiagnosis were evaluated by means of scanning carried out in 18 hospitals of Mexico City, divided in 11 public institutions and 7 private ones. The population being studied was: hospital personnel that works in radiodiagnosis. The survey was made with 31 dichotomic variables, being obtained 132 surveys. The personnel characteristics are 83% works in public institutions, 49% works in radiodiagnosis, 3% has an academic degree, 13% is member of a hospital professional association, 13% has updated information on radiological protection, 36% was trained, 45% works for more than 2 years, 52% uses personal dosemeter, less than the 20% knows about the fundamentals of the radiological protection and 24% states to suffer from biological radiation effects, due to the exposure to x-rays. As result of the study, it was found that the main problems that the radiological protection has, are: lack of training programs in radiological protection and supervision, medical surveillance and the few number of persons that takes part in clinical meetings and professional associations. (authors). 7 refs., 3 tabs

  20. Radiological follow-up of uncemented knee prostheses. Preliminary study

    International Nuclear Information System (INIS)

    Martin Hervas, C.; Gomez Barrena, E.; Marquez Moreno, I.; Calle Yuste, F.; Ordonez Parra, J.M.

    1993-01-01

    The preliminary results of a prospective study of 40 uncemented total knee prostheses (TKP) are presented following a radiological protocol with fluoroscopic control and follow-up of over 2 years. The prosthesis-bone interface and the components alignment were assessed. Several radiological signs were studied to assess this interface with respect to the fixing of the component, but they showed little clinical correlation. Statistical significance (p<0.05, chisquare) was found only in the observation of sclerosis in areas of support for the tibital tray as a reaction of the bone. This radiological follow-up is of interest to determine the evolution of the interface and position of the implant to prevent complications (especially loosening) in patients, particularly those under 60 years old, who represent the group that can most benefit from prosthetic systems with uncemented anchorage because of their life expectation and level of activity. Author

  1. On application of CFD codes to problems of nuclear reactor safety

    International Nuclear Information System (INIS)

    Muehlbauer, Petr

    2005-01-01

    The 'Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety Problems' held in May 2002 at Aix-en-Province, France, recommended formation of writing groups to report the need of guidelines for use and assessment of CFD in single-phase nuclear reactor safety problems, and on recommended extensions to CFD codes to meet the needs of two-phase problems in nuclear reactor safety. This recommendations was supported also by Working Group on the Analysis and Management of Accidents and led to formation oaf three Writing Groups. The first writing Group prepared a summary of existing best practice guidelines for single phase CFD analysis and made a recommendation on the need for nuclear reactor safety specific guidelines. The second Writing Group selected those nuclear reactor safety applications for which understanding requires or is significantly enhanced by single-phase CFD analysis, and proposed a methodology for establishing assesment matrices relevant to nuclear reactor safety applications. The third writing group performed a classification of nuclear reactor safety problems where extension of CFD to two-phase flow may bring real benefit, a classification of different modeling approaches, and specification and analysis of needs in terms of physical and numerical assessments. This presentation provides a review of these activities with the most important conclusions and recommendations (Authors)

  2. Examination of the bases for proposed innovations in reactor safety technology

    International Nuclear Information System (INIS)

    Moses, D.L.

    1986-01-01

    This paper employs the criteria for evaluations from the Nuclear Power Option Viability Study to examine the bases for proposed innovations in light water reactor safety technology. These bases for innovation fall into four broad categories as follows: (1) virtually exclusive reliance on passive safety features to preclude core damage in all situations, (2) design simplification using some passive safety features to reduce the frequency of core damage to less than about 10 -6 per reactor-year, (3) passive containment to preclude releases from any accident, and (4) designing to limit licensing attention to one or at least a few systems. Of these, only the first two, and perhaps only the second, hold significant promise for providing for the viability of advanced light water reactors

  3. Nuclear reactor safety, a review of the Rasmussen report (WASH -1400)

    International Nuclear Information System (INIS)

    Gilbert, C.P.

    1979-03-01

    The US Reactor Safety Study (WASH-1400), often referred to as RSS or the Rasmussen Report, sets out to estimate the risk to which the public is exposed by the possibility of an accident in one of the first 100 nuclear power stations situated in the USA. This review briefly describes the methods used in RSS, and indicates how the results were obtained. It then discusses the nature of these results, and the comparisons which RSS makes between them and other accident statistics. Finally, the criticisms which have been levelled at RSS are assessed, and the conclusions of a very recent US Nuclear Regulatory Commission review are included in appendix. RSS concludes that the risk due to reactor accidents is smaller than that associated with many other aspects of everyday life. While there are shortcomings in RSS, the author has little doubt that the above conclusion is valid

  4. Coupled high fidelity thermal hydraulics and neutronics for reactor safety simulations

    International Nuclear Information System (INIS)

    Vincent A. Mousseau; Hongbin Zhang; Haihua Zhao

    2008-01-01

    This work is a continuation of previous work on the importance of accuracy in the simulation of nuclear reactor safety transients. This work is qualitative in nature and future work will be more quantitative. The focus of this work will be on a simplified single phase nuclear reactor primary. The transient of interest investigates the importance of accuracy related to passive (inherent) safety systems. The transient run here will be an Unprotected Loss of Flow (ULOF) transient. Here the coolant pump is turned off and the un-SCRAM-ed reactor transitions from forced to free convection (Natural circulation). Results will be presented that show the difference that the first order in time truncation physics makes on the transient. The purpose of this document is to illuminate a possible problem in traditional reactor simulation approaches. Detailed studies need to be done on each simulation code for each transient analyzed to determine if the first order truncation physics plays an important role

  5. Software coding for reliable data communication in a reactor safety system

    International Nuclear Information System (INIS)

    Maghsoodi, R.

    1978-01-01

    A software coding method is proposed to improve the communication reliability of a microprocessor based fast-reactor safety system. This method which replaces the conventional coding circuitry, applies a program to code the data which is communicated between the processors via their data memories. The system requirements are studied and the suitable codes are suggested. The problems associated with hardware coders, and the advantages of software coding methods are discussed. The product code which proves a faster coding time over the cyclic code is chosen as the final code. Then the improvement of the communication reliability is derived for a processor and its data memory. The result is used to calculate the reliability improvement of the processing channel as the basic unit for the safety system. (author)

  6. USA NRC/RSR Data Bank System and Reactor Safety Research Data Repository (RSRDR)

    International Nuclear Information System (INIS)

    Maskewitz, B.F.; Bankert, S.F.

    1979-01-01

    The United States Nuclear Regulatory Commission (NRC), through its Division of Reactor Safety Research (RSR) of the Office of Nuclear Regulatory Research, has established the NRC/RSR Data Bank Program to collect, process, and make available data from the many domestic and foreign water reactor safety research programs. An increasing number of requests for data and/or calculations generated by NRC Contractors led to the initiation of the program which allows timely and direct access to water reactor safety data in a manner most useful to the user. The program consists of three main elements: data sources, service organizations, and a data repository

  7. Sodium fast reactor safety and licensing research plan. Volume II.

    Energy Technology Data Exchange (ETDEWEB)

    Ludewig, H. (Brokhaven National Laboratory, Upton, NY); Powers, D. A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A. (Argonne National Laboratory, Argonne, IL); Phillips, J.; Zeyen, R. (Institute for Energy Petten, Saint-Paul-lez-Durance, France); Clement, B. (IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France); Garner, Frank (Radiation Effects Consulting, Richland, WA); Walters, Leon (Advanced Reactor Concepts, Los Alamos, NM); Wright, Steve; Ott, Larry J. (Oak Ridge National Laboratory, Oak Ridge, TN); Suo-Anttila, Ahti Jorma; Denning, Richard (Ohio State University, Columbus, OH); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki, Japan); Ohno, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Miyhara, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Yacout, Abdellatif (Argonne National Laboratory, Argonne, IL); Farmer, M. (Argonne National Laboratory, Argonne, IL); Wade, D. (Argonne National Laboratory, Argonne, IL); Grandy, C. (Argonne National Laboratory, Argonne, IL); Schmidt, R.; Cahalen, J. (Argonne National Laboratory, Argonne, IL); Olivier, Tara Jean; Budnitz, R. (Lawrence Berkeley National Laboratory, Berkeley, CA); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki, Japan); Serre, Frederic (Centre d' %C3%94etudes nucl%C3%94eaires de Cadarache, Cea, France); Natesan, Ken (Argonne National Laboratory, Argonne, IL); Carbajo, Juan J. (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin-Madison, Madison, WI); Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN); Bari, R. (Brokhaven National Laboratory, Upton, NY); Porter D. (Idaho National Laboratory, Idaho Falls, ID); Lambert, J. (Argonne National Laboratory, Argonne, IL); Hayes, S. (Idaho National Laboratory, Idaho Falls, ID); Sackett, J. (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.

    2012-05-01

    Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

  8. The assessment of structural dynamics problems in nuclear reactor safety

    International Nuclear Information System (INIS)

    Liebe, R.

    1978-10-01

    The paper discusses important physical features of structural dynamics problems in reactor safety. First a general characterization is given of the following problems: Containment deformation due to pool-dynamics during BWR-blowdown; behavior of the core internals due to PWR-blowdown loads; dynamic response of a nuclear power plant during an earthquake; fuel element deformation due to local pressure pulses in an LMFBR core. Several criterias are formulated to classify typical problems so that a better choise can be made both of appropriate mathematical/numerical as well as experimental techniques. The degree of physical coupling between structural dynamics and fluid dynamics is discussed in more detail since it requires particular attention when selecting problem-oriented methods of solution. Some examples are given to illustrate the application and to compare advantages and disadvantages of several numerical methods. Then description is given of experimental techniques in structural dynamics and typical problem areas are identified. Finally some results are presented concerning the fuel element deformation problem in LMFBRs and from the general considerations some important conclusions are summarized. (orig.) 891 RW 892 AP [de

  9. Application of CFD Codes in Nuclear Reactor Safety Analysis

    Directory of Open Access Journals (Sweden)

    T. Höhne

    2010-01-01

    Full Text Available Computational Fluid Dynamics (CFD is increasingly being used in nuclear reactor safety (NRS analyses as a tool that enables safety relevant phenomena occurring in the reactor coolant system to be described in more detail. Numerical investigations on single phase coolant mixing in Pressurised Water Reactors (PWR have been performed at the FZD for almost a decade. The work is aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity. For the experimental investigation of horizontal two phase flows, different non pressurized channels and the TOPFLOW Hot Leg model in a pressure chamber was build and simulated with ANSYS CFX. In a common project between the University of Applied Sciences Zittau/Görlitz and FZD the behaviour of insulation material released by a LOCA released into the containment and might compromise the long term emergency cooling systems is investigated. Moreover, the actual capability of CFD is shown to contribute to fuel rod bundle design with a good CHF performance.

  10. IAEA activities in the field of research reactors safety

    International Nuclear Information System (INIS)

    Ciuculescu, C.; Boado Magan, H.J.

    2004-01-01

    IAEA activities in the field of research reactor safety are included in the programme of the Division of Nuclear Installations Safety. Following the objectives of the Division, the results of the IAEA missions and the recommendations from International Advisory Groups, the IAEA has conducted in recent years a certain number of activities aiming to enhance the safety of research reactors. The following activities will be presented: (a) the new Requirements for the Safety of Research Reactors, main features and differences with previous standards (SS-35-S1 and SS-35-S2) and the grading approach for implementation; (b) new documents being developed (safety guides, safety reports and TECDOC's); (c) activities related to the Incident Reporting System for Research Reactor (IRSRR); (d) the new features implemented for the INSARR missions; (e) the Code of Conduct on the Safety of Research Reactors adopted by the Board of Governors on 8 March 2004, following the General Conference Resolution GC(45)/RES/10; and (f) the survey on the safety of research reactors published on the IAEA website on February 2003 and the results obtained. (author)

  11. Sodium fast reactor safety and licensing research plan - Volume II

    International Nuclear Information System (INIS)

    Ludewig, H.; Powers, D.A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A.; Phillips, J.; Zeyen, R.; Clement, B.; Garner, Frank; Walters, Leon; Wright, Steve; Ott, Larry J.; Suo-Anttila, Ahti Jorma; Denning, Richard; Ohshima, Hiroyuki; Ohno, S.; Miyhara, S.; Yacout, Abdellatif; Farmer, M.; Wade, D.; Grandy, C.; Schmidt, R.; Cahalen, J.; Olivier, Tara Jean; Budnitz, R.; Tobita, Yoshiharu; Serre, Frederic; Natesan, Ken; Carbajo, Juan J.; Jeong, Hae-Yong; Wigeland, Roald; Corradini, Michael; Thomas, Justin; Wei, Tom; Sofu, Tanju; Flanagan, George F.; Bari, R.; Porter D.

    2012-01-01

    Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

  12. Reactor engineering and engineered reactor safety in France

    International Nuclear Information System (INIS)

    1987-01-01

    The proceedings give the full text of the lectures held by acknowledged French experts at the KTG Seminar in Mainz on March 10, 1987, all dealing with the leading topic of the current status of reactor engineering and development in France. Although the basic engineering principles and construction lines as well as the safety philosophy are the same in France as in West Germany, there have been distinctive developments over many years in the two countries that by now are not well known even among experts in this field, and hence cannot be properly assessed. Non-availability of relevant surveys or other type of literature in the German language reviewing the French developments is another factor that hitherto was a handicap to mutual exchange of information. The seminar was intended to close this gap. The proceedings should be read by all those in West Germany who wish to be informed about the developments in reactor engineering and reactor safety in France. (orig./DG) [de

  13. Gas-cooled reactor safety and accident analysis

    International Nuclear Information System (INIS)

    1985-12-01

    The Specialists' Meeting on Gas-Cooled Reactor Safety and Accident Analysis was convened by the International Atomic Energy Agency in Oak Ridge on the invitation of the Department of Energy in Washington, USA. The meeting was hosted by the Oak Ridge National Laboratory. The purpose of the meeting was to provide an opportunity to compare and discuss results of safety and accident analysis of gas-cooled reactors under development, construction or in operation, to review their lay-out, design, and their operational performance, and to identify areas in which additional research and development are needed. The meeting emphasized the high safety margins of gas-cooled reactors and gave particular attention to the inherent safety features of small reactor units. The meeting was subdivided into four technical sessions: Safety and Related Experience with Operating Gas-Cooled Reactors (4 papers); Risk and Safety Analysis (11 papers); Accident Analysis (9 papers); Miscellaneous Related Topics (5 papers). A separate abstract was prepared for each of these papers

  14. Effect of DUPIC cycle on CANDU reactor safety parameters

    Energy Technology Data Exchange (ETDEWEB)

    Mohamed, Nader M. A. [Atomic Energy Authority, ETRR-2, Cairo (Egypt); Badawi, Alya [Dept. of Nuclear and Radiation Engineering, Alexandria University, Alexandria (Egypt)

    2016-10-15

    Although, the direct use of spent pressurized water reactor (PWR) fuel in CANda Deuterium Uranium (CANDU) reactors (DUPIC) cycle is still under investigation, DUPIC cycle is a promising method for uranium utilization improvement, for reduction of high level nuclear waste, and for high degree of proliferation resistance. This paper focuses on the effect of DUPIC cycle on CANDU reactor safety parameters. MCNP6 was used for lattice cell simulation of a typical 3,411 MWth PWR fueled by UO{sub 2} enriched to 4.5w/o U-235 to calculate the spent fuel inventories after a burnup of 51.7 MWd/kgU. The code was also used to simulate the lattice cell of CANDU-6 reactor fueled with spent fuel after its fabrication into the standard 37-element fuel bundle. It is assumed a 5-year cooling time between the spent fuel discharges from the PWR to the loading into the CANDU-6. The simulation was carried out to calculate the burnup and the effect of DUPIC fuel on: (1) the power distribution amongst the fuel elements of the bundle; (2) the coolant void reactivity; and (3) the reactor point-kinetics parameters.

  15. Issues affecting advanced passive light-water reactor safety analysis

    International Nuclear Information System (INIS)

    Beelman, R.J.; Fletcher, C.D.; Modro, S.M.

    1992-01-01

    Next generation commercial reactor designs emphasize enhanced safety through improved safety system reliability and performance by means of system simplification and reliance on immutable natural forces for system operation. Simulating the performance of these safety systems will be central to analytical safety evaluation of advanced passive reactor designs. Yet the characteristically small driving forces of these safety systems pose challenging computational problems to current thermal-hydraulic systems analysis codes. Additionally, the safety systems generally interact closely with one another, requiring accurate, integrated simulation of the nuclear steam supply system, engineered safeguards and containment. Furthermore, numerical safety analysis of these advanced passive reactor designs wig necessitate simulation of long-duration, slowly-developing transients compared with current reactor designs. The composite effects of small computational inaccuracies on induced system interactions and perturbations over long periods may well lead to predicted results which are significantly different than would otherwise be expected or might actually occur. Comparisons between the engineered safety features of competing US advanced light water reactor designs and analogous present day reactor designs are examined relative to the adequacy of existing thermal-hydraulic safety codes in predicting the mechanisms of passive safety. Areas where existing codes might require modification, extension or assessment relative to passive safety designs are identified. Conclusions concerning the applicability of these codes to advanced passive light water reactor safety analysis are presented

  16. I. Reactor safety (including comments on criticisms of WASH-1400)

    International Nuclear Information System (INIS)

    1976-01-01

    A major concern in any nuclear power programme is a reactor accident resulting in a large release of radioactivity to the environment. Serious reactor accidents are possible and the risk of such accidents cannot be reduced to zero i.e. absolute safety cannot be assured. All that can be expected is that the measures used to ensure safety in the design and operation of a reactor are such that the risk of accident is reduced to acceptably low levels. No member of the general public is known to have died or been injured as a result of an accident in over 1000 commercial nuclear power reactor-years. Some accidents in power reactors in operation today have come close enough to an environmental release of radioactivity to cause serious public concern about future safety. Apparent inadequacies in safety practices disclosed by former members of the nuclear power industry have added to this concern. To obtain an objective appraisal of the reactor safety issue this report examines the measures taken in the design and operation of nuclear reactors to reduce the probability of accident to acceptably low levels

  17. The use of experimental data in an MTR-type nuclear reactor safety analysis

    Science.gov (United States)

    Day, Simon E.

    Reactivity initiated accidents (RIAs) are a category of events required for research reactor safety analysis. A subset of this is unprotected RIAs in which mechanical systems or human intervention are not credited in the response of the system. Light-water cooled and moderated MTR-type ( i.e., aluminum-clad uranium plate fuel) reactors are self-limiting up to some reactivity insertion limit beyond which fuel damage occurs. This characteristic was studied in the Borax and Spert reactor tests of the 1950s and 1960s in the USA. This thesis considers the use of this experimental data in generic MTR-type reactor safety analysis. The approach presented herein is based on fundamental phenomenological understanding and uses correlations in the reactor test data with suitable account taken for differences in important system parameters. Specifically, a semi-empirical approach is used to quantify the relationship between the power, energy and temperature rise response of the system as well as parametric dependencies on void coefficient and the degree of subcooling. Secondary effects including the dependence on coolant flow are also examined. A rigorous curve fitting approach and error assessment is used to quantify the trends in the experimental data. In addition to the initial power burst stage of an unprotected transient, the longer term stability of the system is considered with a stylized treatment of characteristic power/temperature oscillations (chugging). A bridge from the HEU-based experimental data to the LEU fuel cycle is assessed and outlined based on existing simulation results presented in the literature. A cell-model based parametric study is included. The results are used to construct a practical safety analysis methodology for determining reactivity insertion safety limits for a light-water moderated and cooled MTR-type core.

  18. The use of experimental data in an MTR-type nuclear reactor safety analysis

    International Nuclear Information System (INIS)

    Day, S.E.

    2006-01-01

    Reactivity initiated accidents (RIAs) are a category of events required for research reactor safety analysis. A subset of this is unprotected RIAs in which mechanical systems or human intervention are not credited in the response of the system. Light-water cooled and moderated MTR-type (i.e., aluminum-clad uranium plate fuel) reactors are self-limiting up to some reactivity insertion limit beyond which fuel damage occurs. This characteristic was studied in the Borax and Spert reactor tests of the 1950s and 1960s in the USA. This thesis considers the use of this experimental data in generic MTR-type reactor safety analysis. The approach presented herein is based on fundamental phenomenological understanding and uses correlations in the reactor test data with suitable account taken for differences in important system parameters. Specifically, a semi-empirical approach is used to quantify the relationship between the power, energy and temperature rise response of the system as well as parametric dependencies on void coefficient and the degree of subcooling. Secondary effects including the dependence on coolant flow are also examined. A rigorous curve fitting approach and error assessment is used to quantify the trends in the experimental data. In addition to the initial power burst stage of an unprotected transient, the longer term stability of the system is considered with a stylized treatment of characteristic power/temperature oscillations (chugging). A bridge from the HEU-based experimental data to the LEU fuel cycle is assessed and outlined based on existing simulation results presented in the literature. A cell-model based parametric study is included. The results are used to construct a practical safety analysis methodology for determining reactivity insertion safety limits for a light-water moderated and cooled MTR-type core. (author)

  19. The use of experimental data in an MTR-type nuclear reactor safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Day, S.E

    2006-07-01

    Reactivity initiated accidents (RIAs) are a category of events required for research reactor safety analysis. A subset of this is unprotected RIAs in which mechanical systems or human intervention are not credited in the response of the system. Light-water cooled and moderated MTR-type (i.e., aluminum-clad uranium plate fuel) reactors are self-limiting up to some reactivity insertion limit beyond which fuel damage occurs. This characteristic was studied in the Borax and Spert reactor tests of the 1950s and 1960s in the USA. This thesis considers the use of this experimental data in generic MTR-type reactor safety analysis. The approach presented herein is based on fundamental phenomenological understanding and uses correlations in the reactor test data with suitable account taken for differences in important system parameters. Specifically, a semi-empirical approach is used to quantify the relationship between the power, energy and temperature rise response of the system as well as parametric dependencies on void coefficient and the degree of subcooling. Secondary effects including the dependence on coolant flow are also examined. A rigorous curve fitting approach and error assessment is used to quantify the trends in the experimental data. In addition to the initial power burst stage of an unprotected transient, the longer term stability of the system is considered with a stylized treatment of characteristic power/temperature oscillations (chugging). A bridge from the HEU-based experimental data to the LEU fuel cycle is assessed and outlined based on existing simulation results presented in the literature. A cell-model based parametric study is included. The results are used to construct a practical safety analysis methodology for determining reactivity insertion safety limits for a light-water moderated and cooled MTR-type core. (author)

  20. Adaptive support for user interface customization : a study in radiology

    NARCIS (Netherlands)

    Jorritsma, Wiard; Cnossen, Fokie; van Ooijen, Peter M. A.

    Objectives: This study aimed to evaluate the usefulness of adaptive customization support in a natural work environment: the Picture Archiving and Communication System (PACS) in radiology. Methods: Adaptive support was given in the form of customization suggestions, generated based on behavioral

  1. Thermal hydraulic tests for reactor safety system -Research on the improvement of nuclear safety-

    International Nuclear Information System (INIS)

    Chung, Moon Ki; Park, Chun Kyeong; Yang, Seon Kyu; Chung, Chang Hwan; Chun, Shee Yeong; Song, Cheol Hwa; Chun, Hyeong Gil; Chang, Seok Kyu; Chung, Heung Joon; Won, Soon Yeon; Cho, Yeong Ro; Kim, Bok Deuk; Min, Kyeong Ho

    1994-07-01

    The present research aims at the development of the thermal hydraulic verification test technology for the reactor safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. (Author)

  2. List of reports on reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1984-10-01

    The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  3. Proceedings of the third CSNI workshop on iodine chemistry in reactor safety

    International Nuclear Information System (INIS)

    Ishigure, Kenkichi; Saeki, Masakatsu; Soda, Kunihisa; Sugimoto, Jun

    1992-03-01

    This issue is the collection of the papers presented at the CSNI (Committee on the Safety of Nuclear Installations) workshop on iodine chemistry in reactor safety. The 31 of the presented papers are indexed individually. (J.P.N.)

  4. List of reports on reactor safety research by the BMFT and the USNRC

    International Nuclear Information System (INIS)

    1977-05-01

    This list reviews reports from the Federal Republic of Germany and from the United States of America concerning special problems in the field of Reactor Safety Research which have been collected in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order: Country of origin, problem area concerned according to the Reactor Safety Research Program of BMFT, reporting organisation. The list or reports appears quarterly. This edition contains all reports as registered from January through March 1977. (orig./HK) [de

  5. Progress report - list of reports from BMFT, CEA, EPRI, JSTA and USNRC reactor safety research

    International Nuclear Information System (INIS)

    1982-10-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  6. List of reports from BMFT, CEA, EPRI, JSTA and USNRC concerning reactor safety research

    International Nuclear Information System (INIS)

    1982-02-01

    This list reviews reports from the Federal Republic of Germany, from France from Japan and from the United States of America concerning special problems in the field of reactor safety research. According to the cooperation in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  7. Proceedings of the international topical meeting on advanced reactors safety: Volume 2

    International Nuclear Information System (INIS)

    1997-01-01

    In this volume, 89 papers are grouped under the following headings: advances in research/test reactor safety; advanced reactor accident management and emergency actions; advanced reactors instrumentation/controls/human factors; probabilistic risk/safety and reliability assessments; steam explosion research and issues; advanced reactor severe accident issues and research (analysis and assessments); advanced reactor thermal hydraulics; accelerator-driven source safety; liquid-metal reactor safety; structural assessments and issues; late papers

  8. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1976

    International Nuclear Information System (INIS)

    Ferguson, J.B.

    1977-04-01

    Light water reactor safety research performed October through December 1976 is discussed. An analysis to determine the effect of emergency core coolant (ECC) injection location and pump speed on system response characteristics was performed. An analysis to evaluate the capability of commonly used critical heat flux (CHF) correlations to calculate the time of the first CHF in the Semiscale core during a loss-of-coolant experiment (LOCE) was performed. A test program and study to determine the effect thermocouples mounted on the outside fuel rod surfaces would have on the departure from nucleate boiling (DNB) phenomena in the LOFT core during steady state operation were completed. A correlation for use in predicting DNB heat fluxes in the LOFT core was developed. Tests of an experimental transit time flowmeter were completed. A nuclear test was performed to obtain fuel rod behavior data from four PWR-type rods during film boiling operation representative of PWR conditions. Preliminary results from the postirradiation examination of Test IE-1 fuel rods are given. Results of Irradiation Effects Tests IE-2 and IE-3 are given. Gap Conductance Test GC 2-1 was performed to evaluate the effects of fuel density, initial gap width, and fill gas composition on the pellet-cladding gap conductance

  9. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1976

    Energy Technology Data Exchange (ETDEWEB)

    Ferguson, J. B. [ed.

    1977-04-01

    Light water reactor safety research performed October through December 1976 is discussed. An analysis to determine the effect of emergency core coolant (ECC) injection location and pump speed on system response characteristics was performed. An analysis to evaluate the capability of commonly used critical heat flux (CHF) correlations to calculate the time of the first CHF in the Semiscale core during a loss-of-coolant experiment (LOCE) was performed. A test program and study to determine the effect thermocouples mounted on the outside fuel rod surfaces would have on the departure from nucleate boiling (DNB) phenomena in the LOFT core during steady state operation were completed. A correlation for use in predicting DNB heat fluxes in the LOFT core was developed. Tests of an experimental transit time flowmeter were completed. A nuclear test was performed to obtain fuel rod behavior data from four PWR-type rods during film boiling operation representative of PWR conditions. Preliminary results from the postirradiation examination of Test IE-1 fuel rods are given. Results of Irradiation Effects Tests IE-2 and IE-3 are given. Gap Conductance Test GC 2-1 was performed to evaluate the effects of fuel density, initial gap width, and fill gas composition on the pellet-cladding gap conductance.

  10. Reactor safety research and development in Chalk River Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Nitheanandan, T. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    Atomic Energy of Canada Limited's Chalk River Laboratories provides three different services to stakeholders and customers. The first service provided by the laboratory is the implementation of Research and Development (R&D) programs to provide the underlying technological basis of safe nuclear power reactor designs. A significant portion of the Canadian R&D capability in reactor safety resides at Atomic Energy of Canada Limited's Chalk River Laboratories, and this capability was instrumental in providing the science and technology required to aid in the safety design of CANDU power reactors. The second role of the laboratory has been in supporting nuclear facility licensees to ensure the continued safe operation of nuclear facilities, and to develop safety cases to justify continued operation. The licensing of plant life extension is a key industry objective, requiring extensive research on degradation mechanisms, such that safety cases are based on the original safety design data and valid and realistic assumptions regarding the effect of ageing and management of plant life. Recently, Chalk River Laboratories has been engaged in a third role in research to provide the technical basis and improved understanding for decision making by regulatory bodies. The state-of-the-art test facilities in Chalk River Laboratories have been contributing to the R&D needs of all three roles, not only in Canada but also in the international community, thorough Canada's participation in cooperative programs lead by International Atomic Energy Agency and the OECD's Nuclear Energy Agency. (author)

  11. COUNTERCURRENT FLOW LIMITATION EXPERIMENTS AND MODELING FOR IMPROVED REACTOR SAFETY

    International Nuclear Information System (INIS)

    Vierow, Karen

    2008-01-01

    This project is investigating countercurrent flow and 'flooding' phenomena in light water reactor systems to improve reactor safety of current and future reactors. To better understand the occurrence of flooding in the surge line geometry of a PWR, two experimental programs were performed. In the first, a test facility with an acrylic test section provided visual data on flooding for air-water systems in large diameter tubes. This test section also allowed for development of techniques to form an annular liquid film along the inner surface of the 'surge line' and other techniques which would be difficult to verify in an opaque test section. Based on experiences in the air-water testing and the improved understanding of flooding phenomena, two series of tests were conducted in a large-diameter, stainless steel test section. Air-water test results and steam-water test results were directly compared to note the effect of condensation. Results indicate that, as for smaller diameter tubes, the flooding phenomena is predominantly driven by the hydrodynamics. Tests with the test sections inclined were attempted but the annular film was easily disrupted. A theoretical model for steam venting from inclined tubes is proposed herein and validated against air-water data. Empirical correlations were proposed for air-water and steam-water data. Methods for developing analytical models of the air-water and steam-water systems are discussed, as is the applicability of the current data to the surge line conditions. This report documents the project results from July 1, 2005 through June 30, 2008

  12. Common fluoroscopic studies in radiology : conduct and analysis method

    International Nuclear Information System (INIS)

    Valverde Sanchez, Allan

    2011-01-01

    A countless number of radiological procedures, that have involved the use of fluoroscopy and contrast media of different indole, have been carried out in all radiology services and medical images of Costa Rica for the diagnosis of diseases or conditions, in both adults and in children. Fluoroscopic studies, often called special or contrast studies, have had particular conditions for its realization. Some from the medical point of view: adequate training in the technical and cognitive development when evaluating the images to not miss important details. Other by the patient: adequate preparation to achieve the best images for optimal diagnosis. For example, adequate bowel preparation is essential for a barium enema, to cooperation by the patient to meet specific indications that the physician dictates when swallowing postures or just when you are prompted. Criteria have been met and unified for contrast studies in different hospitals and clinics. The indications, contra, method, technique of procedure, points to remember, number of images or projections minimum required in the interpretation of contrast studies, as well as a report template of standard and ideal study are presented in a simple, systematic and logical. The manual is intended for residents and attending physicians specialists in radiology and medical imaging including contrast studies more common. Spaces are promoted with current technology studies to set aside more complicated and less sophisticated as have been the fluoroscopic studies; however, in the national reality, access to computerized tomography and magnetic resonance imaging is not as easy. Radiological studies with fluoroscopy performed by trained staff led the treating physician to make sound decisions based on studies relatively simple and easy to do. The tests with the use of fluoroscopic have been named: the esophagogram, gastroduodenal series, gastro intestinal transit, the hysterosalpingography, the cystography and the

  13. RADIOLOGICAL STUDY OF HUMAN LUMBAR VERTEBRAL CANAL IN VIDHARBHA REGION

    Directory of Open Access Journals (Sweden)

    Shruti

    2015-06-01

    Full Text Available Increase in number of patients suffering from backache all over world needs changing health polices and cost benefit analysis, it is important to look at diseases causing low back pain and for this study of radiological structure of lumbar vertebral canal is undertaken. AIMS : To reveal the radiological feature of Human lumbar vert ebral canal. METHOD AND MATERIAL : 50 - xray of lumbar canal was collected from orthopedic department of government medical college, Nagpur. STATISTICAL ANALYSIS : Data is presented in mean ± standard deviation and categorical variable are presented in percen tage. Comparison with previous study is done. RESULT : M aximum measurement as greater in male than female of same age group. CONCLUSION : T he present study and previous studies are compared and the non - significant result is found.

  14. Radiological study of cerebro-vascular accidents

    International Nuclear Information System (INIS)

    Misri, H.T.; Kabawe, Bassam

    1991-01-01

    The role of computerized tomography scanner in studying the cerebro-vascular accidents has been discussed. One hundred fifty patients with cerebro-vascular accidents were studied at Aleppo University Hospital between 1989-1990. Clinical history and physical examination were recorded, as well as, computerized tomography scanning in all cases without using the contrast media mostly. Relationship between the density of the lesion (inforctionor hemorrhage) and the time has been found. This relationship can help in forensic medicine. (author). 29 refs., 5 tabs., 2 figs

  15. Clinical and radiologic study of odontogenic keratocyst

    International Nuclear Information System (INIS)

    Kim, Sang Rae; Park, Tae Won

    1984-01-01

    The purpose of this article is to define further clinical behaviors and radiographic appearances of odontogenic keratocyst developed in jaws, with special interest in recurrent rate which is generally high. 32 patients whose microscopic examinations were verified as odontogenic keratocyst were examined in this study. The results of this study were as follows. 1. There was an apparent sex predilection for male. 2. The peak incidence was the second and third decades with gradual decline thereafter with a mean age of 31 years 7 months. 3. The most common site was a mandibular molar-ramus region, 22 cases (68.8%) occurred in the mandible and 10 cases (31.3%) in the maxilla.

  16. Clinical and radiologic study of odontogenic keratocyst

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sang Rae; Park, Tae Won [Department of Radiology, College of Dentistry, Seoul National University, Seoul (Korea, Republic of)

    1984-11-15

    The purpose of this article is to define further clinical behaviors and radiographic appearances of odontogenic keratocyst developed in jaws, with special interest in recurrent rate which is generally high. 32 patients whose microscopic examinations were verified as odontogenic keratocyst were examined in this study. The results of this study were as follows. 1. There was an apparent sex predilection for male. 2. The peak incidence was the second and third decades with gradual decline thereafter with a mean age of 31 years 7 months. 3. The most common site was a mandibular molar-ramus region, 22 cases (68.8%) occurred in the mandible and 10 cases (31.3%) in the maxilla.

  17. Use of FPGA and CPLD in nuclear reactor safety systems and its regulatory review requirements for reactor safety

    International Nuclear Information System (INIS)

    Roy, Suvadip; Biswas, Animesh; Pradhan, S.K.

    2015-01-01

    Field Programmable Gate Arrays (FPGA) and Complex Programmable Logic Devices (CPLD) is being used widely in safety critical and safety related systems in nuclear power plans like in trip logic units, Engineered Safety Feature (ESF) actuation decision logic and neutronic signal processing for their reprogrammability feature and compact design. These HDL Programmable devices (HPD) are complex devices consisting of both hardware and software which is used to implement the logic on the FPGA. It is observed that these Programmable devices suffer from various modes of failure and the major failures in these devices are due to Single Event Upset (SEU), where a highly energetic ionizing radiation may lead to device failure which can even occur in radiologically benign environment. Other failures can occur during steps of developing the hardware using software tools like during Synthesis and placement and routing of the desired hardware. Here a study on use of such devices in Nuclear Reactors, study on mode of failures of these devices, way to tackle such failure and development of review guidelines for review of such devices used in safety critical and safety related systems with special emphasis on choice of software tools, way to mitigate effects of SEU and simulation and hardware testing results to be reviewed by regulatory body during design safety review is done. (author)

  18. Hydroxylamine as a potential reagent for dissolution off gas scrubbing in spent fuel reprocessing: kinetics of the iodine reduction. An example of similarity between the studies on the chemistry of iodine in reactor safety and in spent fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Cau Dit Coumes, C; Devisme, F [Commissariat a l` Energie Atomique, CE/VRH, Bagnols-sur-Ceze (France); Vargas, S; Chopin-Dumas, J [Laboratoire d` Electrochimie Inorganique, ENSSPICAM, Marseille (France)

    1996-12-01

    Iodine, which can be released inside the containment building when an accident occurs, can be traced, in normal operating conditions, at the back end of the fuel cycle. Hydroxylamine has been selected as a reagent of potential interest to trap iodine in the dissolution off gas treatment. The kinetics of the reaction between hydroxylamine and iodine has been studied in a narrow range of pH (1-2), with hydroxylamine in excess (ratios of hydroxylamine to iodine initial concentrations varying from 2 to 40), at constant temperature (30{sup o}C) and ionic strength (0.1 mol/L). Spectrophotometry and voltametry have been coupled for analytical investigation. The problem of the rapid mixing of the reactants has been solved using a continuous reactor. Triiodide has been shown non reactive towards hydroxylamine. An initial rate law has been proposed, pointing out the first order of the reaction with respect to hydroxylamine and iodine, and the inhibitory effect of iodide and hydrogen ions. Nitrous acid has been identified as a transitory product. Nitrous oxide and nitrogen monoxide have been detected by gas chromatography, the ratio of the amounts of products formed depending on acidity. The complexity of the overall reaction has been ascribed to the competition of four reactions as previously proposed in the literature. (author) 8 figs., 1 tab., 13 refs.

  19. Hydroxylamine as a potential reagent for dissolution off gas scrubbing in spent fuel reprocessing: kinetics of the iodine reduction. An example of similarity between the studies on the chemistry of iodine in reactor safety and in spent fuel reprocessing

    International Nuclear Information System (INIS)

    Cau Dit Coumes, C.; Devisme, F.; Vargas, S.; Chopin-Dumas, J.

    1996-01-01

    Iodine, which can be released inside the containment building when an accident occurs, can be traced, in normal operating conditions, at the back end of the fuel cycle. Hydroxylamine has been selected as a reagent of potential interest to trap iodine in the dissolution off gas treatment. The kinetics of the reaction between hydroxylamine and iodine has been studied in a narrow range of pH (1-2), with hydroxylamine in excess (ratios of hydroxylamine to iodine initial concentrations varying from 2 to 40), at constant temperature (30 o C) and ionic strength (0.1 mol/L). Spectrophotometry and voltametry have been coupled for analytical investigation. The problem of the rapid mixing of the reactants has been solved using a continuous reactor. Triiodide has been shown non reactive towards hydroxylamine. An initial rate law has been proposed, pointing out the first order of the reaction with respect to hydroxylamine and iodine, and the inhibitory effect of iodide and hydrogen ions. Nitrous acid has been identified as a transitory product. Nitrous oxide and nitrogen monoxide have been detected by gas chromatography, the ratio of the amounts of products formed depending on acidity. The complexity of the overall reaction has been ascribed to the competition of four reactions as previously proposed in the literature. (author) 8 figs., 1 tab., 13 refs

  20. Clinical, radiological and imunogenectical study in patients with Reiter's Syndrome

    International Nuclear Information System (INIS)

    Souza Meirelles, E. de.

    1987-01-01

    This study puspose was to investigate the clinical, radiological and immunogenetical parameters from a brazilian Reiter's Syndrome population. Twenty Reiter's Syndrome patients from ''Hospital das Clinicas da Faculdade de Medicina da Universidade de Sao Paulo'' were prospectivelly studied in their demographical (sex, race, age at study, age at disease onset and disease duration), epidemiological (family history), clinical (general, articular, mucocutaneous, genitourinary, ocular and intestinal manifestations besides functional capacity at study), radiological (sacro-iliitis, spondylitis and calcaneal spur) and immunogenetical (HLA loci A, B and DR typing). The technique employed in the 61 aloantigens from loci HLA A (17), B (34) and DR (10) typing was Terasaki microlymphocitotoxicity modified by Danilovs, had being performed in the ''Laboratorio de Imunogenetica da Faculdade de Medicina da Universidade de Sao Paulo''. We concluded that the clinical, radiological and immunogenetical Reiter's Syndrome expression in the brazilian population is similar to the others north american or european already studied populations and that the probability of one brazilian HLA B27 positie individual to develop Reiter's Syndrome is 19 fold larger when compared to one brazilian HLA B27 negative individual. (author) [pt

  1. Radiological Protection Studies for NGLS XTOD

    Energy Technology Data Exchange (ETDEWEB)

    Xiao, Shanjie [SLAC National Accelerator Lab., Menlo Park, CA (United States); Santana-Leitner, Mario [SLAC National Accelerator Lab., Menlo Park, CA (United States); Rokni, Sayed [SLAC National Accelerator Lab., Menlo Park, CA (United States); Donahue, Rick [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Emma, Paul [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Floyd, James [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Warwick, Tony [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2017-11-21

    The X-ray transport, optics and diagnostic system (XTOD) starts from the end of bending magnets sending electrons to the main dump and ends at the end wall separating the accelerator tunnel from the user experimental hall (hereafter referred as EH wall), as shown in Figure 1. Figure 1.a shows the general schematic and Figure 1.b shows the initial layout with possible shielding components. This document summarizes the extensive studies on the shielding and collimator system design necessary to meet the radiation protection requirements.

  2. Radiological study of Mersing District, Johor, Malaysia

    Science.gov (United States)

    Saleh, Muneer Aziz; Ramli, Ahmad Termizi; Alajerami, Yasser; Aliyu, Abubakar Sadiq; Bt Basri, Nor Afifah

    2013-04-01

    A potential site has been selected for a nuclear power plant (NPP) in Mersing District of Malaysia. This study aims at providing the base line data of this district for the first time, in line with the International Atomic Energy Agency (IAEA) for NPP sitting criteria. The mean dose rate, mean population weighted dose rate and annual effective dose are found to be 140 nGy h-1, 0.836 mSv y-1 and 0.857 mSv, respectively. A hyper Purity Germanium Detector (HPGe) is used in determining the activity concentrations of 232Th, 226Ra and 40K. The activity concentration ranges from 16±1 to 410±15 Bq kg-1 for 232Th, 17±1 to 271±8 Bq kg-1 for 226Ra and 13±3 to 1434±57 Bq kg-1 for 40K. In addition, a Low Background Alpha Beta Series 5 XLB Automatic was used in the determination of gross alpha and gross beta activity. The result ranges from 202±50 to 2325±466 Bq kg-1 for gross alpha and 164±17 to 2447±103 Bq kg-1 for gross beta. Contour maps were produced for isodose, activity concentration of 232Th, 226Ra, 40K, gross alpha and gross beta for the study area. The results are compared with UNSCEAR (2000).

  3. Radiologic study of the canine urethra

    International Nuclear Information System (INIS)

    Poogird, W.; Wood, A.K.W.

    1986-01-01

    The structure and function of the canine urethra were studied during retrograde and voiding urethrography in 9 male and 8 female dogs. The lumen of the prostatic portion of the urethra was variable in diameter. During retrograde urethrography, the lumen was narrow with streaks of contrast medium outlining mucosal folds, but during voiding, it was dilated and a spindle-shaped seminal hillock was detected. Retrograde urethrography revealed other regions of the urethra of males and females had a smooth radiographic outline. During voiding urethrography, characteristic identical urethral contractions were observed in the caudal portion of the pelvic urethra (male) and in the caudal half of the urethra (female). Contractions were progressive, occurred where striated muscle was present in the urethral wall, and resulted in an intermittent flow of urine from the urethra. In the male, contractions had a rate of 2.02 +/- 0.23 contraction/s and 1.65 +/- 0.53 in the females. Contractions may have a role in the controlled voiding of small volumes of urine necessary for the repeated marking of territory, in the passage of the ejaculate along the male urethra during copulation, and in the clearance of any residual urine from the urethra at the completion of micturition

  4. Basic radiological studies contamination control experiments

    International Nuclear Information System (INIS)

    Duce, S.W.; Winberg, M.R.; Freeman, A.L.

    1989-09-01

    This report describes the results of experiments relating to contamination control performed in support of the Environmental Restoration Programs Retrieval Project. During the years 1950 to 1970 waste contaminated with plutonium and other transuranic radionuclides was disposed of in shallow land-filled pits and trenches at the Idaho National Engineering Laboratory. Due to potential for migration of radionuclides to an existing aquifer the feasibility of retrieving and repackaging the waste for placement in a final repository is being examined as part of a retrieval project. Contamination control experiments were conducted to determine expected respirable and nonrespirable plutonium contaminated dust fractions and the effectiveness of various dust suppression techniques. Three soil types were tested to determine respirable fractions: Rocky Flats Plant generic soil, Radioactive Waste Management Complex generic soil, and a 1:1 blend of the two soil types. Overall, the average respirable fraction of airborne dust was 5.4% by weight. Three contamination control techniques were studied: soil fixative sprays, misting agents, and dust suppression agents. All of the tested agents proved to be effective in reducing dust in the air. Details of product performance and recommended usage are discussed

  5. Radiological study of the mandibular fractures

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ju Won; Kim, Kyoung A; Koh, Kwang Jun [Department of Oral and Maxillofacial Radiology, School of Dentistry, and Institute of Oral Bio Science, Chonbuk National University, Jeonju (Korea, Republic of)

    2009-06-15

    To classify and evaluate mandibular fractures. The author classified mandibular fractures of 284 patients who were referred to the Chonbuk National University Dental Hospital during the period from March 2004 to June 2007. This study was based on the conventional radiographs as well as computed tomographs which were pertained to the 284 patients who have had the mandibular fractures including the facial bone fractures. And mandibular fractures were classified with respect to gender, age, site and type of the fractures. More frequently affected gender with mandibular fracture was male with the ratio of 3.3 : 1. The most frequently affected age with mandibular fracture was third decade (38%), followed by fourth decade (16%), second decade (15%), fifth decade (11%), sixth decade (7%), seventh decade (5%), eighth decade (4%), first decade (4%), and ninth decade (0.3%). The most frequent type of mandibular fracture was single fracture (58%), followed by double fracture (39%), triple fracture (3%). The most common site of mandibular fracture was mandibular condyle as 113 cases (27.7%) and the next was mandibular symphysis as 109 cases (26.7%), mandibular angle as 103 cases (25.3%), mandibular body as 83 cases (20.3%) in order. The sum of fracture sites were 408 sites and there were 1.4 fracture sites per one patient. The number of mandible fractures accompanied with facial bone fractures were 41 cases (14.4%). The results showed the most frequent type and common site of mandibular fracture was single fracture and mandibular condyle respectively.

  6. Radiological study of the mandibular fractures

    International Nuclear Information System (INIS)

    Kim, Ju Won; Kim, Kyoung A; Koh, Kwang Jun

    2009-01-01

    To classify and evaluate mandibular fractures. The author classified mandibular fractures of 284 patients who were referred to the Chonbuk National University Dental Hospital during the period from March 2004 to June 2007. This study was based on the conventional radiographs as well as computed tomographs which were pertained to the 284 patients who have had the mandibular fractures including the facial bone fractures. And mandibular fractures were classified with respect to gender, age, site and type of the fractures. More frequently affected gender with mandibular fracture was male with the ratio of 3.3 : 1. The most frequently affected age with mandibular fracture was third decade (38%), followed by fourth decade (16%), second decade (15%), fifth decade (11%), sixth decade (7%), seventh decade (5%), eighth decade (4%), first decade (4%), and ninth decade (0.3%). The most frequent type of mandibular fracture was single fracture (58%), followed by double fracture (39%), triple fracture (3%). The most common site of mandibular fracture was mandibular condyle as 113 cases (27.7%) and the next was mandibular symphysis as 109 cases (26.7%), mandibular angle as 103 cases (25.3%), mandibular body as 83 cases (20.3%) in order. The sum of fracture sites were 408 sites and there were 1.4 fracture sites per one patient. The number of mandible fractures accompanied with facial bone fractures were 41 cases (14.4%). The results showed the most frequent type and common site of mandibular fracture was single fracture and mandibular condyle respectively.

  7. Sodium spray release accident analysis for fast reactor safety studies

    International Nuclear Information System (INIS)

    Shire, P.R.

    1976-01-01

    A computer code has been developed to model the effects of postulated sodium spray release from LMFBR piping, although this is an event of extremely low probability. The calculation method utilizes gas convection and droplet combustion theory to calculate the pressure and temperature effects in a range of 0 to 21 mole percent oxygen with humidity. Droplet motion and large aggregate sodium surface area result in rapid release of combustion and sensible heat causing a nearly adiabatic pressure rise which peaks in several seconds. This analytical tool has indicated reasonable agreement with prototypic test data for a range of oxygen and water vapor concentrations, cell volumes and droplet sizes

  8. Sodium spray release accident analysis for fast reactor safety studies

    International Nuclear Information System (INIS)

    Shire, P.R.

    1976-10-01

    A computer code has been developed to model the effects of postulated sodium spray release from LMFBR piping. The calculation method utilizes gas convection and droplet combustion theory to calculate the pressure and temperature effects in a range of 0 to 21% oxygen. Droplet motion and large aggregate sodium surface area result in rapid release of combustion and sensible heat causing a nearly adiabtic pressure pulse peaking in a matter of seconds. This analytical tool has indicated good agreement with prototypic test data for a range of oxygen concentrations, cell volumes and droplet sizes

  9. Radiologic studies in two outbreaks of isolated vasculitis in the central nervous system

    International Nuclear Information System (INIS)

    Robertson, H.J.; Perez, M.; Tilton, A.H.; Garcia, C.; McGarry, P.

    1989-01-01

    Cerebral vasculitis is only occasionally diagnosed with angiography. Two outbreaks of isolated central nervous system vasculitis permitted a comparison of the accuracy of diagnostic radiologic studies. Two new radiologic features and methods of diagnosis are discussed

  10. Pediatric surgical diseases. A radiological surgical case study approach

    International Nuclear Information System (INIS)

    Esposito, Ciro; Esposito, Giovanni

    2009-01-01

    Radiologic evaluation of an infant or child suspected of having a surgical disease can be a complex problem. With this volume, the editors have created a book focused on pediatric imaging written by pediatricians, pediatric surgeons and pediatric radiologists. This book is a collection of over 200 case reports. The concept is a case study approach: The reader is given radiologic images (plain radiography, computed tomography, magnetic resonance imaging, ultrasonography, etc.) and the clinical history of the patient. On the basis of this information, the reader is asked to identify a diagnostic and therapeutic strategy. Each case is complemented by information on the disease affecting the patient and the management of the case shown, including therapy and follow-up. This educational text is targeted at all medical professionals faced with a variety of diagnostic and therapeutic problems affecting infants and children. (orig.)

  11. Pediatric surgical diseases. A radiological surgical case study approach

    Energy Technology Data Exchange (ETDEWEB)

    Esposito, Ciro [Federico II Univ. of Naples (Italy). Chair of Pediatric Surgery; Esposito, Giovanni (eds.) [Federico II Univ. of Naples (Italy). School of Medicine

    2009-07-01

    Radiologic evaluation of an infant or child suspected of having a surgical disease can be a complex problem. With this volume, the editors have created a book focused on pediatric imaging written by pediatricians, pediatric surgeons and pediatric radiologists. This book is a collection of over 200 case reports. The concept is a case study approach: The reader is given radiologic images (plain radiography, computed tomography, magnetic resonance imaging, ultrasonography, etc.) and the clinical history of the patient. On the basis of this information, the reader is asked to identify a diagnostic and therapeutic strategy. Each case is complemented by information on the disease affecting the patient and the management of the case shown, including therapy and follow-up. This educational text is targeted at all medical professionals faced with a variety of diagnostic and therapeutic problems affecting infants and children. (orig.)

  12. A radiological study on lumbar disc herniation in Korean

    International Nuclear Information System (INIS)

    Seol, Hae Young; Park, In Sik; Suh, Won Hyuk; Lee, Min Jae

    1979-01-01

    Among the patients operated because of lumbar disc herniation from January 1973 to May 1979 at Korea University Hospital, 154 cases were analyzed radiologically and the following conclusions were obtained. 1. The ratio of male to female was 1.96 : 1. 2. The incidences of single and multiple involvement were 74.7% and 25.3%. 3. Most frequent level of lumbar disc herniation was L4-5 interspace. 4. The incidences of left, central and bilateral defects were 45.45%, 33.76%, 12.33% and 8.44% respectively. 5. The incidences of spina bifida and transitional vertebra were 24.04% and 9.09% respectively. 6. The overall mean of the lumbosacral angle was 33.97 .deg. 7. The overall mean depth of the lumbar lordosis was 8.48 mm. 8. The ratio of the height of L4-5 interspace to the shorter anteroposterior diameter of L-5 body was obtained by authors' idea. The mean ratios of male and female patients of L4-5 disc herniation which had no evidence of the narrowing of L4-5 interspace on simple radiologic finding were 0.3042 and 0.3064 respectively. So the ratio had a little value in the diagnosis of L4-5 disc herniation on simple radiologic study. 9. Myelography had high diagnostic accuracy, and the majority of the pseudonegative finding on lumbar disc herniation myelographically was seen at L4-5 disc herniation.

  13. A radiological study on lumbar disc herniation in Korean

    Energy Technology Data Exchange (ETDEWEB)

    Seol, Hae Young; Park, In Sik; Suh, Won Hyuk; Lee, Min Jae [Korea University College of Medicine, Seoul (Korea, Republic of)

    1979-12-15

    Among the patients operated because of lumbar disc herniation from January 1973 to May 1979 at Korea University Hospital, 154 cases were analyzed radiologically and the following conclusions were obtained. 1. The ratio of male to female was 1.96 : 1. 2. The incidences of single and multiple involvement were 74.7% and 25.3%. 3. Most frequent level of lumbar disc herniation was L4-5 interspace. 4. The incidences of left, central and bilateral defects were 45.45%, 33.76%, 12.33% and 8.44% respectively. 5. The incidences of spina bifida and transitional vertebra were 24.04% and 9.09% respectively. 6. The overall mean of the lumbosacral angle was 33.97 .deg. 7. The overall mean depth of the lumbar lordosis was 8.48 mm. 8. The ratio of the height of L4-5 interspace to the shorter anteroposterior diameter of L-5 body was obtained by authors' idea. The mean ratios of male and female patients of L4-5 disc herniation which had no evidence of the narrowing of L4-5 interspace on simple radiologic finding were 0.3042 and 0.3064 respectively. So the ratio had a little value in the diagnosis of L4-5 disc herniation on simple radiologic study. 9. Myelography had high diagnostic accuracy, and the majority of the pseudonegative finding on lumbar disc herniation myelographically was seen at L4-5 disc herniation.

  14. Physicochemical and radiological studies on some egyptian aquatic areas

    International Nuclear Information System (INIS)

    Youssef, S.K.; Abdel Malik, W.E.Y.; Seifin, S.M.; Abou-zeid, H.M.

    2005-01-01

    For the purpose of estimating the radiological health and safety to the Egyptian population arises from the natural background involved with coastal areas, it is necessary to make a comprehensive study to investigate the natural radionuclides activities in this environmental ecology. The locations of such areas were chosen from those in which people spend some time (e.g. the Mediterranean and Red Sea beaches, Suez Canal in addition to the River Nile Ismailia Canal and Quaroun Lake). Water and soil samples were brought from these locations and subjected to intensive physical, chemical analysis and radiological investigations. The densities of the collected soil samples were found to fall in the region of clay densities (2.30 - 2.70 g/cm 3 ). The particle size distribution analysis, of these soil samples showed values ranging from 128 Μ m to 1303 Μ according to sample site. The collected samples are mainly silicates with variable amounts of the major cations; Ca + +, Mg + +, Na + , K + with some other trace elements. For the radiological investigations 238 U , 226 R a, 232 T h and 40 K activity concentrations were resolved by spectroscopy technique. The majority of samples examined in this work showed variable activities of the naturally occurring radionuclides with fairly low levels compared with literature values reported in other countries. The analysis and discussions of the obtained data are thoroughly performed with the use of equations to estimate the radiation doses

  15. Importance of Sodium Fuel Interaction in Fast Reactor Safety Evaluation - CEA Point of View

    International Nuclear Information System (INIS)

    Tanguy, P.

    1976-01-01

    The consequences of interactions between molten metal (aluminium-uranium alloy) and water have long been a subject of concern for those in charge of reactor safety, following accidents observed or induced in certain reactors (BORAX, SL1, SPERT 1 D). In such accidents, as in similar cases occurring in traditional industries (aluminium foundries, steel works, paper mills...) the contact between the hot liquid product and the coolant entails rapid vaporization of the latter with effects identical to that of an explosive. Although chemical reactions of water decomposition occur in some cases, the main phenomenon is the conversion of the thermal energy stored in the hot substance into mechanical energy. Despite the fact that a molten oxide fuel differs from an aluminium-uranium alloy, as does sodium from water, the consequences of possible contact between the molten mixed uranium and plutonium oxide and sodium must be carefully studied since such a contact may occur in accident conditions in sodium-cooled fast neutron reactors. The essential purpose of an evaluation of reactor safety in accident conditions is in fact to ensure the containment of dangerous products Consequently, any phenomenon likely to endanger containment barriers must be carefully examined. In conclusion: Whereas an accident within an assembly seems to show little likelihood of creating conditions seriously endangering fuel containment, the gravity of problems associated with an overall accident on the core is worthy of thorough and attentive study. In the case of an overall accident on the core of a fast reactor, the interaction between the molten fuel and the sodium is of consequence at two levels. The first is the retention of mechanical energy which may be considerable. The second is the recovery of fuel fragments in an overall cooled configuration but where local cooling problems may give rise to interaction. A greater effort is required in performing tests and mastering their results to

  16. List of reports on reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1985-08-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. According to the cooperation of the Federal Ministry for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available from the Society for Reactor Safety (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  17. Study of photoconductor-based radiological image sensors

    International Nuclear Information System (INIS)

    Beaumont, Francois

    1989-01-01

    Because of the evolution of medical imaging techniques to digital Systems, it is necessary to replace radiological film which has many drawbacks, by a detector quite as efficient and quickly giving a digitizable signal. The purpose of this thesis is to find new X-ray digital imaging processes using photoconductor materials such as amorphous selenium. After reviewing the principle of direct radiology and functions to be served by the X-ray sensor (i.e. detection, memory, assignment, visualization), we explain specification. We especially show the constraints due to the object to be radiographed (condition of minimal exposure), and to the reading signal (electronic noise detection associated with a reading frequency). As a result of this study, a first photoconductor sensor could be designed. Its principle is based on photo-carrier trapping at dielectric-photoconductor structure interface. The reading System needs the scanning of a laser beam upon the sensor surface. The dielectric-photoconductor structure enabled us to estimate the possibilities offered by the sensor and to build a complete x-ray imaging System. The originality of thermo-dielectric sensor, that was next studied, is to allow a thermal assignment reading. The chosen System consists in varying the ferroelectric polymer capacity whose dielectric permittivity is weak at room temperature. The thermo-dielectric material was studied by thermal or Joule effect stimulation. During our experiments, trapping was found in a sensor made of amorphous selenium between two electrodes. This new effect was performed and enabled us to expose a first interpretation. Eventually, the comparison of these new sensor concepts with radiological film shows the advantage of the proposed solution. (author) [fr

  18. RETU. The Finnish research programme on reactor safety. Interim report 1995 - May 1997

    International Nuclear Information System (INIS)

    Vanttola, T.; Puska, E.K.

    1997-08-01

    The Finnish national research programme on Reactor Safety (RETU, 1995-1998) concentrates on the search of safe limits of nuclear fuel and the reactor core, accident management methods and risk management of the operation of nuclear power plants. The annual volume of the programme has been about 26 person years and the annual funding FIM 15 million. This report summarises the structure and objectives of the programme, research fields included and the main results obtained during the period 1995 - May 1997. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel is studied both in normal operation and during power transients. The static and dynamic reactor analysis codes are developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients and accidents. Research on accident management aims at development and validation of calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Other goals are to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. In the field of risk management probabilistic methods are developed for safety related decision making and for complex phenomena and event sequences. Effects of maintenance on nuclear power plant safety are studied and more effective methods for the assessment of human reliability and safety critical organisations are searched

  19. RETU. The Finnish research programme on reactor safety. Interim report 1995 - May 1997

    Energy Technology Data Exchange (ETDEWEB)

    Vanttola, T; Puska, E K [VTT Energy, Espoo (Finland). Nuclear Energy; eds.

    1997-08-01

    The Finnish national research programme on Reactor Safety (RETU, 1995-1998) concentrates on the search of safe limits of nuclear fuel and the reactor core, accident management methods and risk management of the operation of nuclear power plants. The annual volume of the programme has been about 26 person years and the annual funding FIM 15 million. This report summarises the structure and objectives of the programme, research fields included and the main results obtained during the period 1995 - May 1997. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel is studied both in normal operation and during power transients. The static and dynamic reactor analysis codes are developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients and accidents. Research on accident management aims at development and validation of calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Other goals are to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. In the field of risk management probabilistic methods are developed for safety related decision making and for complex phenomena and event sequences. Effects of maintenance on nuclear power plant safety are studied and more effective methods for the assessment of human reliability and safety critical organisations are searched. 135 refs.

  20. Estimate of dose in interventional radiology: a study of cases

    International Nuclear Information System (INIS)

    Pinto, N.; Braz, D.; Lopes, R.; Vallim, M.; Padilha, L.; Azevedo, F.; Barroso, R.

    2006-01-01

    Values of absorbed dose taken by patients and professionals involved in interventional radiology can be significant mainly for the reason of these proceedings taking long time of fluoroscopy There are many methods to estimate and reduce doses of radiation in the interventional radiology, particularly because the fluoroscopy is responsible for the high dose contribution in the patient and in the professional. The aim of this work is the thermoluminescent dosimetry to estimate the dose values of the extremities of the professionals involved in the interventional radiology and the product dose-area was investigated using a Diamentor. This evaluation is particularly useful for proceedings that interest multiple parts of the organism. In this study were used thermoluminescent dosimeters (LiF:Mg, Ti - Harshaw) to estimate the dose values of the extremities of the professionals and to calibrate them. They were irradiated with X rays at 50 mGy, in Kerma in air and read in the reader Harshaw-5500. The product dose-area (D.A.P.) were obtained through the Diamentor (M2-P.T.W.) calibrated in Cgy.cm 2 fixed in the exit of the X-rays tube. The patients of these study were divided in three groups: individuals submitted to proceedings of embolization, individuals submitted to cerebral and renal arteriography and individuals submitted to proceedings of Transjungular Inthahepatic Porta Systemic Stent Shunt (TIPS). The texts were always carried out by the same group: radiologist doctor), an auxiliary doctor and a nursing auxiliary. The section of interventional radiology has an Angiostar Plus Siemens equipment type arc C, in which there is trifocal Megalix X-ray tube and a intensifier of image from Sirecon 40-4 HDR/33 HDR. In this work the dose estimated values were 137.25 mSv/year for the doctors, 40.27 mSv/year for the nursing and 51.95 mSv/year for the auxiliary doctor and they are below the rule, but in this study it was not taken in consideration the emergency texts as they were

  1. List of BMFT, USNRC, EPRI, and STA reports on reactor safety research

    International Nuclear Information System (INIS)

    1980-07-01

    This list reviews reports from the Federal Republic of Germany, from the United States of America and from Japan concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the United States Nuclear Regulatory Commission (USNRC), the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order : Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. (orig./HP) [de

  2. List of reports in reactor safety research by BMFT, USNRC, EPRI and JSTA

    International Nuclear Information System (INIS)

    1981-01-01

    This list reviews reports from the Federal Republic of Germany, from the United States of America and from Japan concerning special problems in the field of Reactor Safety research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the United States Nuclear Regulatory Commission (USNRC), the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. (orig.) [de

  3. Reactor Safety Assessment System--A situation assessment aid for USNRC emergency response

    International Nuclear Information System (INIS)

    Bray, M.A.; Sebo, D.E.; Dixon, B.W.

    1985-01-01

    The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (USNRC). RSAS is intended for use at the NRC's Operations Center in the event of a serious incident at a licensed nuclear power plant. The system uses plant parameter data and status information from the power plant. It has a rule base that uses the parametric values, the known operator actions, and the time sequence information in the data to generate situation assessment conclusions for use by the NRC Reactor Safety Team. RSAS rules currently cover one specific reactor type and use setpoints specific to one power plant

  4. Reactor Safety Assessment System: a situation assessment aid for USNRC emergency response

    International Nuclear Information System (INIS)

    Bray, M.A.; Sebo, D.E.; Dixon, B.W.

    1985-04-01

    The Reactor Safety Assessment System is an expert system under development for the United States Nuclear Regulatory Commission (NRC). RSAS is intended for use at the NRC's Operations Center in the event of a serious incident at a licensed nuclear power plant. The system uses plant parameter data and status information from the power plant. It has a rule base which uses the parametric values, the known operator actions and the time sequence information in the data to generate situation assessment conclusions for use by the NRC Reactor Safety Team. RSAS rules currently cover one specific reactor type and use setpoints specific to one power plant. 5 figs

  5. Physics design of fast reactor safety test facilities for in-pile experiments

    International Nuclear Information System (INIS)

    Travelli, A.; Matos, J.E.; Snelgrove, J.L.; Shaftman, D.H.; Tzanos, C.P.; Lam, S.K.; Pennington, E.M.; Woodruff, W.L.

    1976-01-01

    A determined effort to identify and resolve current Fast Breeder Reactor safety testing needs has recently resulted in a number of conceptual designs for FBR safety test facilities which are very complex and diverse both in their features and in their purpose. The paper discusses the physics foundations common to most fast reactor safety test facilities and the constraints which they impose on the design. The logical evolution, features, and capabilities of several major conceptual designs are discussed on the basis of this common background

  6. RESI-1 and RESI-2: pPrototypes of an information system on reactor safety

    International Nuclear Information System (INIS)

    Schultheiss, G.F.; Eglin, W.; Katz, F.W.; Krings, T.; Pee, A.; Schlechtendahl, E.G.

    1975-04-01

    To demonstrate by practical experience the feasibility of the information system elaborated in the 'Study of an Information System on Reactor Safety RESI' (KFK 1900), the prototype systems RESI-1 and RESI-2 were developed and tested in operation. The two systems have been considerably reduced both in extent and contents as compared to the information system described in the study. The RESI-1 prototype system is a paper version established for verification of all the individual functions before passing over to the computer-aided interactive version RESI-2. RESI-2 is based on the GOLEM system of Siemens. Both protoype systems have proved that the essential features: 1) documentation, 2) formulation of and answering to safety questions, which are relevant with respect to particular licensing cases, 3) formulation of safety questions related to individual reactor types can be managed satisfactorily. All the functions of information retrieval have been tested carefully over several months. Particularities of project development and of the methods elaborated are described in detail and presented in this report. (orig.) [de

  7. A radiological study on lumbar disc herniation in Korean

    Energy Technology Data Exchange (ETDEWEB)

    Seol, Hae Young; Park, In Sik; Suh, Won Hyuk; Lee, Min Jae [Korea University College of Medicine, Seoul (Korea, Republic of)

    1979-12-15

    Among the patients operated because of lumbar disc herniation from January 1973 to May 1979 at Korea University Hospital, 154 cases were analyzed radiologically and the following conclusions were obtained. 1. The ratio of male to female was 1.96 : 1. 2. The incidences of single and multiple involvement were 74.7% and 25.3%. 3. Most frequent level of lumbar disc herniation was L4-5 interspace. 4. The incidences of left, central and bilateral defects were 45.45%, 33.76%, 12.33% and 8.44% respectively. 5. The incidences of spina bifida and transitional vertebra were 24.04% and 9.09% respectively. 6. The overall mean of the lumbosacral angle was 33.97 .deg. 7. The overall mean depth of the lumbar lordosis was 8.48 mm. 8. The ratio of the height of L4-5 interspace to the shorter anteroposterior diameter of L-5 body was obtained by authors' idea. The mean ratios of male and female patients of L4-5 disc herniation which had no evidence of the narrowing of L4-5 interspace on simple radiologic finding were 0.3042 and 0.3064 respectively. So the ratio had a little value in the diagnosis of L4-5 disc herniation on simple radiologic study. 9. Myelography had high diagnostic accuracy, and the majority of the pseudonegative finding on lumbar disc herniation myelographically was seen at L4-5 disc herniation.

  8. Health Care Delivery Meets Hospitality: A Pilot Study in Radiology.

    Science.gov (United States)

    Steele, Joseph Rodgers; Jones, A Kyle; Clarke, Ryan K; Shoemaker, Stowe

    2015-06-01

    The patient experience has moved to the forefront of health care-delivery research. The University of Texas MD Anderson Cancer Center Department of Diagnostic Radiology began collaborating in 2011 with the University of Houston Conrad N. Hilton College of Hotel and Restaurant Management, and in 2013 with the University of Nevada, Las Vegas, William F. Harrah College of Hotel Administration, to explore the application of service science to improving the patient experience. A collaborative pilot study was undertaken by these 3 institutions to identify and rank the specific needs and expectations of patients undergoing imaging procedures in the MD Anderson Department of Diagnostic Radiology. We first conducted interviews with patients, providers, and staff to identify factors perceived to affect the patient experience. Next, to confirm these factors and determine their relative importance, we surveyed more than 6,000 patients by e-mail. All factors considered important in the interviews were confirmed as important in the surveys. The surveys showed that the most important factors were acknowledgment of the patient's concerns, being treated with respect, and being treated like a person, not a "number"; these factors were more important than privacy, short waiting times, being able to meet with a radiologist, and being approached by a staff member versus having one's name called out in the waiting room. Our work shows that it is possible to identify and rank factors affecting patient satisfaction using techniques employed by the hospitality industry. Such factors can be used to measure and improve the patient experience. Copyright © 2015 American College of Radiology. Published by Elsevier Inc. All rights reserved.

  9. Study of physical, chemical and radiological characteristic of thermal water

    International Nuclear Information System (INIS)

    Labidi, Saleem

    2004-01-01

    Hydrotherapy is an activity during which the practitioner is exposed to natural ionising radiation. Radon from deep geological layers constitutes the praincipal irradiation factor for the worker and the patient. The study of radiological impact requires specific measurements that should be compared with international commission of radiological protection (ICRP) recommendations. The objective of this study is to estimate the health risk for employees and patients in hydrotherapy spas in tunisia, by calculating the annual effective dose within the diffrent sites, to identify the sites that could present a hasard from radon and to establish a protection scheme for on workers in these spas. This study is performed inside of the tunisian thermal spas. It consists in separating 226 Ra and measuring its concentration in the thermal water of each spa and then, determining the radon concentration with solid state track detectors (SSTD) chosen for their sensitivity to alpha particles. The dose assessment results show that the estimates values were lower than the ICRP recommendations. In addition, the effective doses received by the workers are greater than those received by the patients due to the longer exposure time for the workers. (author). 79 refs 6)

  10. Sensitivity analysis of reactor safety parameters with automated adjoint function generation

    International Nuclear Information System (INIS)

    Kallfelz, J.M.; Horwedel, J.E.; Worley, B.A.

    1992-01-01

    A project at the Paul Scherrer Institute (PSI) involves the development of simulation models for the transient analysis of the reactors in Switzerland (STARS). This project, funded in part by the Swiss Federal Nuclear Safety Inspectorate, also involves the calculation and evaluation of certain transients for Swiss light water reactors (LWRs). For best-estimate analyses, a key element in quantifying reactor safety margins is uncertainty evaluation to determine the uncertainty in calculated integral values (responses) caused by modeling, calculational methodology, and input data (parameters). The work reported in this paper is a joint PSI/Oak Ridge National Laboratory (ORNL) application to a core transient analysis code of an ORNL software system for automated sensitivity analysis. The Gradient-Enhanced Software System (GRESS) is a software package that can in principle enhance any code so that it can calculate the sensitivity (derivative) to input parameters of any integral value (response) calculated in the original code. The studies reported are the first application of the GRESS capability to core neutronics and safety codes

  11. Development of Multipurpose PLC trainer for the simulator of reactor safety system

    International Nuclear Information System (INIS)

    Syaiful Bakhri; Deswandri; Ahmad Abtokhi

    2014-01-01

    PLC becomes one of the essential components for the current type of reactor which based on digital instrumentation and control. Several studies have demonstrated the promising results including the implementation of PLC's for RSG-GAS research reactor. However, research for the safety and reliability analysis can not be carried out freely in the existing systems.Therefore, this research aims to develop a PLC trainer employing micro PLC OMRON CP1MA which can be useful for simulator of various topics in reactor safety. Two experimental tests were carried out to show the PLC’s performances. The first experimental testing implementing reactor protection system of research reactor RSG-GAS shows the capacity of PLC system to identify the initiator of the SCRAM logic as well as giving a promptly response. Secondly, the application of PLC to controls the water level in dual reservoir system simulation, demonstrates the simplicity of the operation and design while maintaining the best performances. (author)

  12. Reactor safety issues resolved by the 2D/3D program

    International Nuclear Information System (INIS)

    1995-09-01

    The 2D/3D Program studied multidimensional thermal-hydraulics in a PWR core and primary system during the end-of-blowdown and post-blowdown phases of a large-break LOCA (LBLOCA), and during selected small-break LOCA (SBLOCA) transients. The program included tests at the Cylindrical Core Test Facility (CCTF), the Slab Core Test Facility (SCTF), and the Upper Plenum Test Facility (UPTF), and computer analyses using TRAC. Tests at CCTF investigated core thermal-hydraulics and overall system behavior while tests at SCTF concentrated on multidimensional core thermal-hydraulics. The UPTF tests investigated two-phase flow behavior in the downcomer, upper plenum, tie plate region, and primary loops. TRAC analyses evaluated thermal-hydraulic behavior throughout the primary system in tests as well as in PWRs. This report summarizes the test and analysis results in each of the main areas where improved information was obtained in the 2D/3D Program. The discussion is organized in terms of the reactor safety issues investigated. This report was prepared in a coordination among US, Germany and Japan. US and Germany have published the report as NUREG/IA-0127 and GRS-101 respectively. (author)

  13. Reactor safety issues resolved by the 2D/3D Program

    International Nuclear Information System (INIS)

    Damerell, P.S.; Simons, J.W.

    1993-07-01

    The 2D/3D Program studied multidimensional thermal-hydraulics in a PWR core and primary system during the end-of-blowdown and post-blowdown phases of a large-break LOCA (LBLOCA), and during selected small-break LOCA (SBLOCA) transients. The program included tests at the Cylindrical Core Test Facility (CCTF), the Slab Core Test Facility (SCTF), and the Upper Plenum Test Facility (UPTF), and computer analyses using TRAC. Tests at CCTF investigated core thermal-hydraulics and overall system behavior while tests at SCTF concentrated on multidimensional core thermal-hydraulics. The UPTF tests investigated two-phase flow behavior in the downcomer, upper plenum, tie plate region, and primary loops. TRAC analyses evaluated thermal-hydraulic behavior throughout the primary system in tests as well as in PWRs. This report summarizes the test and analysis results in each of the main areas where improved information was obtained in the 2D/3D Program. The discussion is organized in terms of the reactor safety issues investigated

  14. Reactor safety issues resolved by the 2D/3D program

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The 2D/3D Program studied multidimensional thermal-hydraulics in a PWR core and primary system during the end-of-blowdown and post-blowdown phases of a large-break LOCA (LBLOCA), and during selected small-break LOCA (SBLOCA) transients. The program included tests at the Cylindrical Core Test Facility (CCTF), the Slab Core Test Facility (SCTF), and the Upper Plenum Test Facility (UPTF), and computer analyses using TRAC. Tests at CCTF investigated core thermal-hydraulics and overall system behavior while tests at SCTF concentrated on multidimensional core thermal-hydraulics. The UPTF tests investigated two-phase flow behavior in the downcomer, upper plenum, tie plate region, and primary loops. TRAC analyses evaluated thermal-hydraulic behavior throughout the primary system in tests as well as in PWRs. This report summarizes the test and analysis results in each of the main areas where improved information was obtained in the 2D/3D Program. The discussion is organized in terms of the reactor safety issues investigated. This report was prepared in a coordination among US, Germany and Japan. US and Germany have published the report as NUREG/IA-0127 and GRS-101 respectively. (author).

  15. Fast reactor safety program. Progress report, January-March 1980

    International Nuclear Information System (INIS)

    1980-05-01

    The goal of the DOE LMFBR Safety Program is to provide a technology base fully responsive to safety considerations in the design, evaluation, licensing, and economic optimization of LMFBRs for electrical power generation. A strategy is presented that divides safety technology development into seven program elements, which have been used as the basis for the Work Breakdown Structure (WBS) for the Program. These elements include four lines of assurance (LOAs) involving core-related safety considerations, an element supporting non-core-related plant safety considerations, a safety R and D integration element, and an element for the development of test facilities and equipment to be used in Program experiments: LOA-1 (prevent accidents); LOA-2 (limit core damage); LOA-3 (maintain containment integrity); LOA-4 (attenuate radiological consequences); plant considerations; R and D integration; and facility development

  16. Nasal polyps. A clinical radiological histopathological and mycological study

    Energy Technology Data Exchange (ETDEWEB)

    Babiker, Babiker Eltayeb [Faculty of Medicine, University of Khartoum, Khartoum (Sudan)

    1997-12-01

    Forty patients with nasal polyposis were studied. This study included clinical, haematological and mycological aspects. There were 24 females (60% of patients) and 16 males (40%). We found that all patients presented with nasal obstruction and nasal tone and the majority of them had allergic nasal symptoms such as sneezing and watery discharge. Thirty five percent of the patients were recurrent cases, being operated before for nasal polyps. Radiological investigations showed high of sinusitis and that 10% of the patients had complicated disease with orbital or intracranial extensions. Mycological studies revealed the presence of fungal infection in 4 patient (10%) and it was caused by Aspergillus flavus. Histological studies identified the allergic nature of the polyps in all patients. Surgical treatment was carried out in all patients and operations varied from simple intranasal polypectomy, intranasal ethmiodectomy, external ethmoidectomy to Caldwell-Luc operation for patients with antrochanal polyps.(Author)

  17. The clinical and radiological study of near drowning

    International Nuclear Information System (INIS)

    Reinhardt, K.

    1982-01-01

    A survey is given of the literature on near drowning, discussing the aspects for all disciplines emphasising the radiological features. The radological pictures are demonstrated and case descriptions containing radiological features are cited extensively out of the literature. This survey should be of great value for the clinician in therapy and control of course. The correlation of the clinical and radiological features should promote a better interpretation of pathogenetic mechanisms. (orig.) [de

  18. Fail-safe logic elements for use with reactor safety systems

    International Nuclear Information System (INIS)

    Bobis, J.P.; McDowell, W.P.

    1976-01-01

    A complete fail-safe trip circuit is described which utilizes fail-safe logic elements. The logic elements used are analog multipliers and active bandpass filter networks. These elements perform Boolean operations on a set of AC signals from the output of a reactor safety-channel trip comparator

  19. Thermohydraulic tests in the area of reactor safety done in CDTN

    International Nuclear Information System (INIS)

    Ladeira, L.C.D.

    1990-01-01

    The main experimental works performed in the last five years at the Thermohydraulics Laboratory of the Nuclear Technology Development Center, in the field of reactor safety are briefly described. This paper cover the performing and analysis of pressure drop, heat transfer and mixing tests in 3X3 rod bundle and rewetting tests in single tube section. (autor) [pt

  20. Two-field and drift-flux models with application to nuclear reactor safety

    International Nuclear Information System (INIS)

    Travis, J.R.

    1986-01-01

    The ideas of the two-field (6 equation model) and drift-flux (4 equation model) description of two-phase flows are presented. Several example calculations relating to reactor safety are discussed and comparisons of the numerical results and experimental data are shown to be in good agreement. 16 refs., 32 figs

  1. The action of the project coordinator with respect to reactor safety

    International Nuclear Information System (INIS)

    Leclercq, Jacques

    1981-01-01

    Before describing the various actions of the project coordinator (EDF) entrusted with the building of nuclear power stations, with respect to reactor safety in France, the definition of reactor safety and the various participants are mentioned first. These participants are: the Government Departments and the Experts involved (the Department of Nuclear Safety of the 'Institut de Protection et de Surete Nucleaire' forming the first technical support) and the applicant, namely the EDF. The reactor safety actions of the project coordinator are defined as from the following components: 1 - The targets laid down with respect to safety, the final objective being the protection of workers and the public against the potential dangers of the installations, principally against radiation. 2 - The safety methodology at the design stage of the power station: 'barrier' method, defence method in depth at three levels, lines of assurance method, and probabilistic method. 3 - Safety actions at the construction stage within the context of an assurance of quality programe. 4 - Safety at the trials, commissioning and operating stage, with the backing of the 'Groupe Operationnel de Demarrage (G.O.D.)' and the 'Commission d'Essais sur Site (C.E.S.)'. An initial balance sheet of the reactor safety actions for the PWR units built by the EDF is presented [fr

  2. VVER Reactor Safety in Eastern Europe and Former Soviet Union

    Science.gov (United States)

    Papadopoulou, Demetra

    2012-02-01

    VVER Soviet-designed reactors that operate in Eastern Europe and former Soviet republics have heightened international concern for years due to major safety deficiencies. The governments of countries with VVER reactors have invested millions of dollars toward improving the safety of their nuclear power plants. Most of these reactors will continue to operate for the foreseeable future since they provide urgently-needed electrical power. Given this situation, this paper assesses the radiological consequences of a major nuclear accident in Eastern Europe. The paper also chronicles the efforts launched by the international nuclear community to improve the safety of the reactors and notes the progress made so far through extensive collaborative efforts in Armenia, Bulgaria, the Czech Republic, Hungary, Kazakhstan, Lithuania, Russia, Slovakia, and Ukraine to reduce the risks of nuclear accidents. Western scientific and technical staff collaborated with these countries to improve the safety of their reactor operations by strengthening the ability of the regulator to perform its oversight function, installing safety equipment and technologies, investing time in safety training, and working diligently to establish an enduring safety culture. Still, continued safety improvement efforts are necessary to ensure safe operating practices and achieve timely phase-out of older plants.

  3. Proceedings of the international symposium on research reactor safety operations and modifications

    International Nuclear Information System (INIS)

    1990-03-01

    The International Symposium on Research Reactor Safety, Operations and Modifications was organized by the International Atomic Energy Agency in cooperation with Atomic Energy of Canada Limited-Research Company. The main objectives of this Symposium were: (1) to exchange information and to discuss current perspectives and concerns relating to all aspects to research reactor safety, operations, and modifications; and, (2) to present views and to discuss future initiatives and directions for research reactor design, operations, utilization, and safety. The symposium topics included: research reactor programmes and experience; research reactor design safety and analysis; research reactor modifications and decommissioning; research reactor licensing; and new research reactors. These topics were covered during eight oral sessions and three poster sessions. These Proceedings include the full text of the 93 papers presented. The subject of Symposium was quite wide-ranging in that it covered essentially all aspects of research reactor safety, operations, and modifications. This was considered to be appropriate and timely given the 326 research reactors currently in operation in some 56 countries; given the degree of their utilization which ranges from pure and applied research to radioisotopes production to basic training and manpower development; and given that many of these reactors are undergoing extensive modifications, core conversions, power upratings, and are becoming the subject of safety reassessment and regulatory reviews. Although the Symposium covered many topics, the majority of papers and discussions tended to focus mainly on research reactor safety. This was seen as a clear sign of the continuing recognition of the fundamental importance of identifying and addressing, particularly through international cooperation, issues and concerns associated with research reactor safety

  4. Study of criteria for foodstuffs control following a radiological emergency

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Min; Park, Sang Hyun; Jeong, Seung Young; Kim, Dong Il [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-04-15

    The foodstuff control standards on APPRE should be applied to emergency situation only, while the Korean Food Stands Codex standards of the Korea Food and Drug Administration (KFDA) should be applied in normal situation. To reflect the lessons learned form the Fukushima accident, the standards of foodstuff control has been studied by surveying newly recommended systems of radiological protection based on reference level commensurated with exposure situations and international trends. Existing standards for restriction on ingestion of foodstuff is based on simple cost-benefit approach and it is confirmed that the projected doses is contributed excessively on the specific food categories. In future, the standards will be revised considering domestic diet feature, nuclide analysis procedure, international standard and the latest recommendation of radiation protection. Also, modification of provisions and standards for foodstuff control of related departments are needed for well integrated national EPR framework.

  5. Dental diseases of dogs: a retrospective study of radiological data

    International Nuclear Information System (INIS)

    Butkovic, V.; Sehic, M.; Stanin, D.; Simpraga, M.; Susic, V.; Capak, D.; Kos, J.

    2001-01-01

    The purpose of the present study was to assess the number of pathological dental changes and anomalies in dogs. The incidence of dental diseases was investigated in radiologically examined 139 males and 120 females, aged from 7 months to 15 years. The incidence of oligodontia equalled to 45.17 %, peridontitis 44.40 %, fracture 19.30 %, tooth rotation 11.5 %, persisting deciduous teeth 5.40 % and supernumerary teeth 3.86 %. Incidence of dental changes and anomalies differed significantly between dogs of different age groups. Considering the hereditary nature of the anomalies such as congenital oligodontia, tooth rotation and retained deciduous teeth, dog breeders should provide for a timely X-ray examination and, in case of these anomalies, exclude the affected dogs from further breeding

  6. Rock siting of nuclear power plants from a reactor safety standpoint

    International Nuclear Information System (INIS)

    1975-11-01

    The study has aimed at surveying the advantages and disadvantages of a rock sited nuclear power plant from a reactor safety standpoint. The studies performed are almost entirely concentrated on the BWR alternative. The design of a nuclear power plant in rock judged most appropriate has been studied in greater detail, and a relatively extensive safety analysis has been made. It is found that the presented technical design of the rock sited alternative is sufficiently advanced to form a basis for further projecting treatment. The chosen technical design of the reactor plant demands a cavern with a 45-50 metre span. Caverns without strengthening efforts with such spans are used in mines, but have no previously been used for industrial plants. Studies of the stability of such caverns show that a safety level is attainable corresponding to the safety required for the other parts of the nuclear power plant. The conditions are that the rock is of high quality, that necessary strengthening measures are taken and that careful studies of the rock are made before and during the blasting, and also during operation of the plant. When locating a rock sited nuclear power plant, the same criteria must be considered as for an above ground plant, with additional stronger demands for rock quality. The presented rock sited nuclear power plant has been assessed to cost 20 % more in total construction costs than a corresponding above ground plant. The motivations for rock siting also depend on whether a condensing plant for only electricity production, or a plant for combined power production and district heating, is considered. The latter would under certain circumstances make rock siting look more attractive. (author)

  7. Study on development in professional work of radiological technologists

    International Nuclear Information System (INIS)

    Choi, Jong Hak; Kim, Chang Kyun; Kim, Won Chul; Kim, Seung Chul

    2006-01-01

    This study explored several agenda related to license system, education, professional work of radiological technologists (RTs) and a transition process of law for them to investigate a developmental strategy of RTs as a professional career. The results are as followings: 1. The national license system for RTs was started from 1965, 1965-1972 x-ray technicians (medical assistance), 1973-present (2006) radiotechnologist (medical technologist) since then. 2. The average pass ratio of national license examination (1965-2006) for RTs was 46.6%. The method, subjects and level of the examination should be improved. 3. The education term for RTs has been changed since 1963; 1963-1990 two year college. 1991-1999 three year college, 2000-2006 four year and three year college depending on universities and colleges. As of 2006, there are twelve 4-year universities and eighteen 3-year colleges. The total number of new students were 1,965. 4. The new developmental paradigm should be made for technology education of RTs corresponding to the development of medicine and science. 5. The qualification system of clinical specialists in radio-technology field needs to be operated not by the non-governmental body (The-Korean Radiological Technologists Association) but by the governmental body. 6. The vertical relationship among RTs, doctors and other medical workers should be rebuilt through the revision of law. Especially, doctors and dentists 'guidance authority' for RTs should be changed to 'request authority'. 7. The service extent of RTs should be extended in medical fields corresponding to professional work of RTs and a revision of the law needed for this situation

  8. A clinical and radiological study on spontaneous pneumothorax

    International Nuclear Information System (INIS)

    Jang, Kyung Jae; Kim, Jin Wook; Kim, Byung Soo; Choi, Myung Gwon

    1982-01-01

    A clinical and radiological study was done on 96 cases of spontaneous pneumothorax, encountered in the Dept. of Radiology, Busan National University Hospital during last 3 years from March 1979 to March 1982. The result were summarized as follows: 1. In the age distribution, the ages between 20 and 39 years were most highest, as 54 cases (56.3%). In the sex distribution, the ratio of male to female was 5 : 1 in male predominance. 2. The underlying pathology of the total 96 cases of spontaneous pneumothorax were of tuberculous origin in 33.3 % and non-tuberculous origin in 66.7%. And below 20 years, most were of non- tuberculous origin. 3. In the cases of lung collapse over 2/3, non-tuberculous origin was more than tuberculous origin and had characteristics of significant mediastinal shifting, in contrast to lower percentage of fluid level by chest radiography. 4. The rupture of biebs or bullae was the main immediate causes of spontaneous pneumothorax, independent of the underlying pathology. 5. In only 27 cases (28.1%) among total 96 cases, bullae or biebs could be detected on the chest radiography. 6. In treatment of spontaneous pneumothorax, the closed thoracotomy with under water seal drainage is accepted to be the general method of treatment. But open thoracotomy is considered as the best useful therapeutic procedure to prevent the recurrence, whenever bullae or blebs are found on the chest radiography. 7. In the cases of closed thoracotomy, the recurrent rate was 25.0% and most cases were found at the ipsilateral side of the first attack. 8. Within a week, the collapsed lung were well expanded in most cases of total 96 cases, after closed thoracotomy

  9. RETU The Finnish research programme on reactor safety 1995-1998. Final Symposium

    International Nuclear Information System (INIS)

    Vanttola, T.

    1998-01-01

    The Reactor Safety (RETU, 1995-1998) research programme concentrated on search of safe limits for nuclear fuel and the reactor core, accident management methods and risk management of nuclear power plants. The total volume of the programme was 100 person years and funding FIM 58 million. This symposium report summarises the research fields, the objectives and the main results obtained. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel was studied both in normal operation and during power transients. The static and dynamic reactor analysis codes were developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients. Advanced flow models and numerical solution methods for the dynamics codes were developed and tested. Research on accident management developed and validated calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Efforts were made to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. The programme included experimental work, but also participation in large international tests. The Finnish thermal-hydraulic test facility PACTEL was used extensively for the evaluation of the VVER-440 plant accident behaviour, for the validation of the accident analysis computer codes and for the testing of passive safety system concepts for future plant designs. In risk management probabilistic methods were developed for safety related decision making and for complex event sequences. Effects of maintenance on safety were studied and effective methods for assessment of human reliability and safety critical organisations were searched. To enhance human competencies in control of complex environments, practical tools for training and continuous learning were worked out, and methods to evaluate appropriateness of control room design were developed. (orig)

  10. Characterization of mammographic findings radiological studies, in radiology service Hospital Doctor Rafael Angel Calderon Guardia during the year 2012

    International Nuclear Information System (INIS)

    Ugalde Gatjens, Mauricio

    2013-01-01

    The radiological findings are determined in reading mammography studies between the months of May and June 2012 in the radiology service of Hospital Calderon Guardia. The association of pathologies is determined between breast pathology, age group and sex. A control allowing identification of geographic areas with higher reference is established for realization of mammograms. The pathologies resulting from the reading of mammographic studies are quantified and classified. The patients have presented 42% of risk factors with the potential predisposition to develop breast cancer. Mammography applications have been coming in 22% of Montes de Oca EBAIS and Curridabat, being presented in most lesions in women between 45 and 74 years old. Mammograms analyzed are classified as BIRADS 2 and to a lesser extent as BIRADS 0 [es

  11. Radiological study of the calcanean ossification secondary nucleus development

    International Nuclear Information System (INIS)

    Carvalho Filho, Guaracy.

    1994-01-01

    This work describes the normal aspects of the calcanean ossification secondary nucleus radiological development, the appearing time, his form, localization, fragmentation and evolution of area, from a sample of normal individuals. (author). 14 refs., 16 figs., 8 tabs

  12. Central neurocytoma: a histopathological and radiologic study of six cases

    International Nuclear Information System (INIS)

    Fugita, Dalton Yukio Araujo; Souza, Andrea Silveira de; Monteiro, Soraya Silveira; Lederman, Henrique M.; Caldas, Jose Guilherme Pereira; Frudit, Michel; Stavale, Jose Norberto

    1998-01-01

    Central neurocytoma is a rare intraventricular tumor with benign behavior which affects young adults. We describe six cases of central neurocytoma, discussing the histopathological and radiologic diagnosis, and briefly comment some aspects about treatment. (author)

  13. Creating a comprehensive customer service program to help convey critical and acute results of radiology studies.

    Science.gov (United States)

    Towbin, Alexander J; Hall, Seth; Moskovitz, Jay; Johnson, Neil D; Donnelly, Lane F

    2011-01-01

    Communication of acute or critical results between the radiology department and referring clinicians has been a deficiency of many radiology departments. The failure to perform or document these communications can lead to poor patient care, patient safety issues, medical-legal issues, and complaints from referring clinicians. To mitigate these factors, a communication and documentation tool was created and incorporated into our departmental customer service program. This article will describe the implementation of a comprehensive customer service program in a hospital-based radiology department. A comprehensive customer service program was created in the radiology department. Customer service representatives were hired to answer the telephone calls to the radiology reading rooms and to help convey radiology results. The radiologists, referring clinicians, and customer service representatives were then linked via a novel workflow management system. This workflow management system provided tools to help facilitate the communication needs of each group. The number of studies with results conveyed was recorded from the implementation of the workflow management system. Between the implementation of the workflow management system on August 1, 2005, and June 1, 2009, 116,844 radiology results were conveyed to the referring clinicians and documented in the system. This accounts for more than 14% of the 828,516 radiology cases performed in this time frame. We have been successful in creating a comprehensive customer service program to convey and document communication of radiology results. This program has been widely used by the ordering clinicians as well as radiologists since its inception.

  14. Study of graduate curriculum in the radiological science: problems and suggestions

    International Nuclear Information System (INIS)

    Ko, Seong Jin; Kim, Hwa Gon; Kang, Se Sik; Park, Byeong Rae; Kim, Chang Soo

    2006-01-01

    Currently, Educational program of radiological science is developed in enormous growth, our educational environments leading allied health science education program in the number of super high speed medical industry. Radiological science may be the fastest growing technologies in our medical department today. In this way, Medical industry fields converged in the daily quick, the fact that department of radiological science didn't discharged ones duties on current educational environments. The curriculum of radiological technologists that play an important part between skill and occupation's education as major and personality didn't performed one's part most effectively on current medical environments and digital radiological equipment interface. We expect improvement and suggestion to grow natural disposition as studies in the graduate of radiological science. Therefore, in this paper, current curriculum of radiological science are catched hold of trend and problems on digital radiology environments, on fact the present state of problems, for Graduate program of radiological science, graduate courses of MS and ph.D. are suggested a reform measure of major education curriculum introduction

  15. A study on four-year college curriculum for the education of radiological technology in Korea

    International Nuclear Information System (INIS)

    Choi, Jong Hak; Lee, Sang Suk; Kim, Young Il; Kwon, Dal Gwan; Kim, Heung Tae; Lim, Han Young

    1995-01-01

    The education of radiologic technology began in the regular institute of higher education in Korea in 1963. Up to now from then, our education to bring up the radiologic technologists has developed greatly in quality and quantity, and now departments of radio-technology are founded in the 16 junior colleges in March, 1995. This study was done to verify the necessity and propriety to reform the education system of radiologic technology which was run as two or three year system of college curriculum for 32 years since 1963, and to search for the method to reform in the future. We got the following results from this research. 1. In the survey, on the desirable education year for radiologic technologists, 63.9 % of professors of department of radio-technology and 63.0 % of radiologic technologists chose the 4 year system, 27.9 % of professors and 34.6 % of radiologic technologists chose the 4 year system added to graduate school. 2. In the survey, on the future development of radiologic equipment and technique, 67.2 % of professors of department of radiologic technology and 86.4 % of radiologic technologists have a view of 'revolutional development'. Also, on the future tasks or roles

  16. Radiology Residents' Awareness about Ionizing Radiation Doses in Imaging Studies and Their Cancer Risk during Radiological Examinations

    Energy Technology Data Exchange (ETDEWEB)

    Goekce, Senem Divrik [I. Ikad Community Health Center, Health Directorate, Samsun (Turkmenistan); Gekce, Erkan [Samsun Maternity and Women' s Disease and Pediatrics Hospital, Samsun (Turkmenistan); Coskun, Melek [Faculty of Medicine, Ondokuz May' s University, Samsun (Turkmenistan)

    2012-03-15

    Imaging methods that use ionizing radiation have been more frequent in various medical fields with advances in imaging technology. The aim of our study was to make residents be aware of the radiation dose they are subjected to when they conduct radiological imaging methods, and of cancer risk. A total of 364 residents participated in this descriptive study which was conducted during the period between October, 2008 and January, 2009. The questionnaires were completed under strict control on a one-to-one basis from each department. A X{sup 2}-test was used for the evaluation of data obtained. Only 7% of residents correctly answered to the question about the ionizing radiation dose of a posteroanterior (PA) chest X-ray. The question asking about the equivalent number of PA chest X-rays to the ionizing dose of a brain CT was answered correctly by 24% of residents; the same question regarding abdominal CT was answered correctly by 16% of residents, thorax CT by 16%, thyroid scintigraphy by 15%, intravenous pyelography by 9%, and lumbar spine radiography by 2%. The risk of developing a cancer throughout lifetime by a brain and abdominal CT were 33% and 28%, respectively. Radiologic residents should have updated knowledge about radiation dose content and attendant cancer risks of various radiological imaging methods during both basic medical training period and following practice period.

  17. Radiology Residents' Awareness about Ionizing Radiation Doses in Imaging Studies and Their Cancer Risk during Radiological Examinations

    Science.gov (United States)

    Divrik Gökçe, Senem; Coşkun, Melek

    2012-01-01

    Objective Imaging methods that use ionizing radiation have been more frequent in various medical fields with advances in imaging technology. The aim of our study was to make residents be aware of the radiation dose they are subjected to when they conduct radiological imaging methods, and of cancer risk. Materials and Methods A total of 364 residents participated in this descriptive study which was conducted during the period between October, 2008 and January, 2009. The questionnaires were completed under strict control on a one-to-one basis from each department. A χ2-test was used for the evaluation of data obtained. Results Only 7% of residents correctly answered to the question about the ionizing radiation dose of a posteroanterior (PA) chest X-ray. The question asking about the equivalent number of PA chest X-rays to the ionizing dose of a brain CT was answered correctly by 24% of residents; the same question regarding abdominal CT was answered correctly by 16% of residents, thorax CT by 16%, thyroid scintigraphy by 15%, intravenous pyelography by 9%, and lumbar spine radiography by 2%. The risk of developing a cancer throughout lifetime by a brain and abdominal CT were 33% and 28%, respectively. Conclusion Radiologic residents should have updated knowledge about radiation dose content and attendant cancer risks of various radiological imaging methods during both basic medical training period and following practice period. PMID:22438688

  18. Radiology Residents' Awareness about Ionizing Radiation Doses in Imaging Studies and Their Cancer Risk during Radiological Examinations

    International Nuclear Information System (INIS)

    Goekce, Senem Divrik; Gekce, Erkan; Coskun, Melek

    2012-01-01

    Imaging methods that use ionizing radiation have been more frequent in various medical fields with advances in imaging technology. The aim of our study was to make residents be aware of the radiation dose they are subjected to when they conduct radiological imaging methods, and of cancer risk. A total of 364 residents participated in this descriptive study which was conducted during the period between October, 2008 and January, 2009. The questionnaires were completed under strict control on a one-to-one basis from each department. A X 2 -test was used for the evaluation of data obtained. Only 7% of residents correctly answered to the question about the ionizing radiation dose of a posteroanterior (PA) chest X-ray. The question asking about the equivalent number of PA chest X-rays to the ionizing dose of a brain CT was answered correctly by 24% of residents; the same question regarding abdominal CT was answered correctly by 16% of residents, thorax CT by 16%, thyroid scintigraphy by 15%, intravenous pyelography by 9%, and lumbar spine radiography by 2%. The risk of developing a cancer throughout lifetime by a brain and abdominal CT were 33% and 28%, respectively. Radiologic residents should have updated knowledge about radiation dose content and attendant cancer risks of various radiological imaging methods during both basic medical training period and following practice period.

  19. Part I. Fuel-motion diagnostics in support of fast-reactor safety experiments. Part II. Fission product detection system in support of fast reactor safety experiments

    International Nuclear Information System (INIS)

    Devolpi, A.; Doerner, R.C.; Fink, C.L.; Regis, J.P.; Rhodes, E.A.; Stanford, G.S.; Braid, T.H.; Boyar, R.E.

    1986-05-01

    In all destructive fast-reactor safety experiments at TREAT, fuel motion and cladding failure have been monitored by the fast-neutron/gamma-ray hodoscope, providing experimental results that are directly applicable to design, modeling, and validation in fast-reactor safety. Hodoscope contributions to the safety program can be considered to fall into several groupings: pre-failure fuel motion, cladding failure, post-failure fuel motion, steel blockages, pretest and posttest radiography, axial-power-profile variations, and power-coupling monitoring. High-quality results in fuel motion have been achieved, and motion sequences have been reconstructed in qualitative and quantitative visual forms. A collimated detection system has been used to observe fission products in the upper regions of a test loop in the TREAT reactor. Particular regions of the loop are targeted through any of five channels in a rotatable assembly in a horizontal hole through the biological shield. A well-type neutron detector, optimized for delayed neutrons, and two GeLi gamma ray spectrometers have been used in several experiments. Data are presented showing a time history of the transport of Dn emitters, of gamma spectra identifying volatile fission products deposited as aerosols, and of fission gas isotopes released from the coolant

  20. Radiological study of Mururoa and Fangataufa : progress report

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    The IAEA-coordinated study of the radiological situation at the Atolls of Mururoa and Fangataufa arose from a request from the French government for an independent review. The request was considered at an informal technical consultation meeting between scientists from several Member States and representatives of intergovernmental organizations at the Agency in Vienna in January 1996. The meeting discussed the objectives of the Study and matters that should be included in its terms of reference and considered the Task and Working Group structure needed to carry out the assessments. The Task and Working Groups have nearly completed their work. Drafts of the Working Groups' technical reports were considered at a coordination and review meeting of Task and Working Group Chairmen and Agency Project Management Office representatives on 17-19 September 1997. Final drafts of the technical reports of the Task and Working Groups are due to be completed before the end of November 1997, and the penultimate draft of the Study report is to be circulated to International Advisory Committee members in December. (author)

  1. A histological study of scala communis with radiological implications.

    Science.gov (United States)

    Makary, Chadi; Shin, Jennifer; Caruso, Paul; Curtin, Hugh; Merchant, Saumil

    2010-01-01

    Scala communis or interscalar septum (IS) defect is a developmental abnormality of the inner ear characterized by a dehiscence in the partition separating the turns of the cochlea. The goals of the present study were to (1) study this anomaly and describe its characteristics compared to control ears using a histological analysis of temporal bones, (2) discuss radiological implications regarding its diagnosis, and (3) describe its embryological derivation. Out of 1775 temporal bones assessed, 22 specimens were found to have scala communis in cochleae containing all 3 turns (basal, middle and apical). These 22 ears were studied in detail by qualitative and quantitative methods using light microscopy. Scala communis occurred as an isolated inner ear anomaly, or in association with other congenital cochlear and/or vestibular anomalies. The defect occurred most often between the middle and apical turns of the cochlea. Compared to control ears, scala communis ears were found to have a smaller modiolar area (p Scala communis was compatible with normal hearing. Flattening of the interscalar ridge has the potential to improve the diagnosis of scala communis in patients using CT scanning. The anomaly may result from a mesodermal defect such as excessive resorption of mesenchyme during the formation of the scalae, an error in the formation of bone, or both. Copyright © 2010 S. Karger AG, Basel.

  2. A comparative study of quality control in diagnostic radiology

    International Nuclear Information System (INIS)

    Kharita, M. H.; Khedr, M.S.; Wannus, K.M.

    2008-01-01

    The main objective of this comparative study was to evaluate the national quality assurance program for X-ray diagnostic radiology in Syrian governmental hospitals. Two periods were covered in this study, the first period was from 1986 to 1998 (52 hospitals and 149 X-ray machines were considered) and the second period from 1999 to 2005 (41 hospitals and 95 X-ray machines were considered). Most of the X-ray machines studied were within the acceptable performance, but few machines needed recalibration for some parameters. Considerable improvement of about 50% was reported in the second period. This improvement could be attributed to the establishment of an effective National Regulatory Authority in Syria in 1998 that introduced and gradually enforced the quality assurance requirement for X-ray equipment as part of the licensing process and to the relatively newer X-ray machines covered in the second period. The Author 2008. Published by Oxford Univ. Press. All rights reserved. (authors)

  3. Radiology workstation for mammography: preliminary observations, eyetracker studies, and design

    Science.gov (United States)

    Beard, David V.; Johnston, Richard E.; Pisano, Etta D.; Hemminger, Bradley M.; Pizer, Stephen M.

    1991-07-01

    For the last four years, the UNC FilmPlane project has focused on constructing a radiology workstation facilitating CT interpretations equivalent to those with film and viewbox. Interpretation of multiple CT studies was originally chosen because handling such large numbers of images was considered to be one of the most difficult tasks that could be performed with a workstation. The authors extend the FilmPlane design to address mammography. The high resolution and contrast demands coupled with the number of images often cross- compared make mammography a difficult challenge for the workstation designer. This paper presents the results of preliminary work with workstation interpretation of mammography. Background material is presented to justify why the authors believe electronic mammographic workstations could improve health care delivery. The results of several observation sessions and a preliminary eyetracker study of multiple-study mammography interpretations are described. Finally, tentative conclusions of what a mammographic workstation might look like and how it would meet clinical demand to be effective are presented.

  4. List of reactor safety research reports from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1982-07-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special Problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these Reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  5. List of reports from reactor safety research of BMFT, USNRC, EPRI and JSTA

    International Nuclear Information System (INIS)

    1979-01-01

    This list reviews reports from the Federal Republic of Germany, from the USA and from Japan concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the USNRC, the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. Requests for reports should be adressed to GRS, Forschungsbetreuung. Contractual view points have to be considered for the distribution of the reports. (orig./HP) [de

  6. List of reports on reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1985-01-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special Problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l' Energie Atomique (CEA), the Japan Science and Technologie Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these Reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  7. List of reports on reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1984-07-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. Requests for reports should be addressed to GRS, Forschungsbetreuung. Contractual points of view have to be considered for the distribitution of the reports. (orig.) [de

  8. List of reports from reactor safety research of BMFT, USNRC, EPRI and JSTA

    International Nuclear Information System (INIS)

    1978-12-01

    This list reviews reports from the Federal Republic of Germany, from the USA and from Japan concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the USNRC, the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. Requests for reports should be addressed to GRS, Forschungsbetreuung. Contractual view points have to be considered for the distribution of the reports. (orig./HP) [de

  9. Transactions of the Twenty-First Water Reactor Safety Information Meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1993-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 21st Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 25--27, 1993. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session

  10. Transactions of the twenty-fifth water reactor safety information meeting

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.

    1997-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 25th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 20--22, 1997. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion of information exchanged during the course of the meeting, and are given in order of their presentation in each session.

  11. Transactions of the twenty-fifth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1997-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 25th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 20--22, 1997. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion of information exchanged during the course of the meeting, and are given in order of their presentation in each session

  12. List of reports concerning reactor safety research from BMFT, CEA, EPRI, JSTA, and USNRC

    International Nuclear Information System (INIS)

    1982-12-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these Reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  13. Transactions of the twenty-second water reactor safety information meeting

    International Nuclear Information System (INIS)

    1994-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 22nd Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 24--26, 1994. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session. Individual papers have been cataloged separately

  14. Transactions of the Twenty-First Water Reactor Safety Information Meeting

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.

    1993-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 21st Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 25--27, 1993. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session.

  15. Research of bone metastases in prostate cancer: scintigraphy and radiological study

    International Nuclear Information System (INIS)

    Seibel, I.; Monteiro, T.S.

    1981-01-01

    This paper analyses the results of bone scan and radiologic study of the bones on the search of metastases of prostate cancer seen in the last two years. In 44 patients with prostatic cancer the diagnostic of metastatic disease was made by the 99m Tc scan in 52%, and by the metastatic radiologic survey in only 25%. (author)

  16. Study on the radiological Impact of Coal Fired Power Plants

    International Nuclear Information System (INIS)

    Cancio, D.; Robles, B.; Mora, J. C.; Baeza, A.; Corbacho, J. A.; Vasco, J.; Guillen, J.

    2008-01-01

    The study is part of the goal set forth in Title VII of the European Basic Safety Standards and the Spanish regulations on radiation protection related to work activities that may involve a significant increase in exposure of workers and the public to natural radiation. Coal contains small quantities of radionuclides in the series of uranium, thorium and potassium which in the industrial process can lead to radiological exposure. This work presents the measurements and evaluations conducted in one of the power plants object of study: The Unidad Termica de Produccion de Litoral in the Almeria Province. The maximum dose assessed for workers are in the order of 0.14 mSv per year and in the order of 0.05 mSv per year for the public in the realistic scenarios considered. These values are well below the 1mSv per year reference levels, recommended in Europe to have some interest from the radiation protection point of view. (Author) 52 refs

  17. A comprehensive examination of heat transfer correlations suitable for reactor safety analysis

    International Nuclear Information System (INIS)

    Groeneveld, D.C.; Snoek, C.W.

    1986-01-01

    Due to the inadequate understanding of heat transfer mechanisms, an empirical approach is often necessary. This approach requires the derivation of empirical heat transfer correlations for each heat transfer configuration, resulting in numerous correlations for each heat transfer mode. A simplification that is frequently used is to combine these heat transfer correlations using some suitably defined local parameters to characterize the heat transfer process. These local condition correlations, usually encountered in reactor safety codes are discussed in this paper

  18. Proceedings of the US Nuclear Regulatory Commission twentieth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1993-03-01

    This three-volume report contains papers presented at the Twentieth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 21--23, 1992. The papers describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 10 different papers presented by researchersfrom CEC, China, Finland, France, Germany, Japan, Spain and Taiwan

  19. RELAP5 - a new tool for pressurized water reactor safety analysis

    International Nuclear Information System (INIS)

    Perneczky, L.

    1988-11-01

    The RELAP type pressurized water reactor safety system codes are used world wide for the loss of coolant accident analyses. In this paper the RELAP5, the advanced generation of the code family is presented. The relationship to RELAP4/mod6 version is discussed. The capability of the RELAP5/mod1-EUR version for small, medium and large break LOCA is investigated based on international user experience. (author) 30 refs

  20. Application of software engineering to development of reactor-safety codes

    International Nuclear Information System (INIS)

    Wilburn, N.P.; Niccoli, L.G.

    1980-11-01

    As a result of the drastically increasing cost of software and the lack of an engineering approach, the technology of Software Engineering is being developed. Software Engineering provides an answer to the increasing cost of developing and maintaining software. It has been applied extensively in the business and aerospace communities and is just now being applied to the development of scientific software and, in particular, to the development of reactor safety codes at HEDL

  1. List of the reports from reactor safety research of the BMFT and USNRC

    International Nuclear Information System (INIS)

    1977-02-01

    This list presents a survey of reports from the FRG and USA issued on special problems of reactor safety research. The problems include emergency core cooling, the containment during loss of coolant, core meltdown, component safety, external impacts, risk and reliability, quality assurance, fission product transport, radiation exposure, as well as the LWR, HTR and the fast sodium-cooled reactor in general. (orig./HK) [de

  2. Performance improvement of the Annular Core Pulse Reactor for reactor safety experiments

    International Nuclear Information System (INIS)

    Reuscher, J.A.; Pickard, P.S.

    1976-01-01

    The Annular Core Pulse Reactor (ACPR) is a TRIGA type reactor which has been in operation at Sandia Laboratories since 1967. The reactor is utilized in a wide variety of experimental programs which include radiation effects, neutron radiography, activation analysis, and fast reactor safety. During the past several years, the ACPR has become an important experimental facility for the United States Fast Reactor Safety Research Program and questions of interest to the safety of the LMFBR are being addressed. In order to enhance the capabilities of the ACPR for reactor safety experiments, a project to improve the performance of the reactor was initiated. It is anticipated that the pulse fluence can be increased by a factor of 2.0 to 2.5 utilizing a two-region core concept with high heat capacity fuel elements around the central irradiation cavity. In addition, the steady-state power of the reactor will be increased by about a factor of two. The new features of the improvements are described

  3. Contrast reaction training in US radiology residencies: a COARDRI study.

    Science.gov (United States)

    LeBedis, Christina A; Rosenkrantz, Andrew B; Otero, Hansel J; Decker, Summer J; Ward, Robert J

    To perform a survey-based assessment of current contrast reaction training in US diagnostic radiology residency programs. An electronic survey was distributed to radiology residency program directors from 9/2015-11/2015. 25.7% of programs responded. 95.7% of those who responded provide contrast reaction management training. 89.4% provide didactic lectures (occurring yearly in 71.4%). 37.8% provide hands-on simulation training (occurring yearly in 82.3%; attended by both faculty and trainees in 52.9%). Wide variability in contrast reaction education in US diagnostic radiology residency programs reveals an opportunity to develop and implement a national curriculum. Copyright © 2017 Elsevier Inc. All rights reserved.

  4. List of reports of BMFT, CEA, EPRI, JSTA and USNRC in the field of reactor safety research

    International Nuclear Information System (INIS)

    1984-04-01

    The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  5. Annual technical progress report: reactor safety, Government fiscal year 1978

    International Nuclear Information System (INIS)

    1978-01-01

    Progress in LMFBR safety studies on accident debris behavior is reported under the following subtask titles: high-temperature-concentration aerosols, large-scale molten fuel tests, sodium release tests, and risk analysis

  6. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1986-04-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  7. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1986-02-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  8. Neutron flux shape effects in large fast reactor safety calculations

    International Nuclear Information System (INIS)

    Galati, A.; Loizzo, P.; Musco, A.

    1978-01-01

    Three classes of accidents in a large fast reactor were studied by the two-dimensional core dynamics code NADYP-2. A Modified version of the code, including a point kinetics module, allowed comparison between 2D and 0D power, reactivity and temperature histories. A strong shape effect was evidenced by these calculations in the boiling phase of LOF accidents as well as in the accident generated by control rod removal. Some future possibilities of by passing the consequences of this effect are indicated

  9. Thermochemical data acquisition - Reactor safety programme 1988-1991

    International Nuclear Information System (INIS)

    Ball, R.G.J.; Rand, M.H.; Cordfunke, E.H.P.; Konings, R.J.M.

    1991-10-01

    Thermochemical data are required for specific fission product and reactor materials compounds in order to quantify the consequences of a severe accident within a light water reactor. Approximately 40 important compounds/systems have been identified for study for which thermodynamic data did not exist or were inadequate. Work is described on the analysis of approximately half of these systems. Experimental studies have been undertaken to determine the thermodynamic quantities of the following compounds : Cs 2 MoO 4 , CsBO 2 , Cs 2 RuO 4 , Cs 2 RuO 4 , Cs 2 Mno 4 , Cs 2 CrO 4 , Cs 2 TeO 3 ,Cs 2 Te, InI, InI 3 , In 2 I 6 , In 2 Te, Cd(OH) 2 , Cd(OH) 2 , TeO(OH) 2 ,CdI 2 , Cd 2 I 4 , Cs 2 CdI 4 , CsCdI 3 , Cs 2 CdI 4 , Cs 3 PO 4 and Cd-In-Ag. Critical assessments have been made on the following systems : In-I, In-Te, Cd-I, Sr-B-O and Ba-B-O. The thermodynamic quantities of these compounds have been calculated over the temperature range from 298 to 3000 K. The adoption of these data within appropriate modelling codes will allow the fission product species and transport to be predicted with greater confidence, thus providing more accurate assessments of the consequences of severe reactor accidents

  10. Cost/benefit analyses of reactor safety systems

    International Nuclear Information System (INIS)

    1988-01-01

    The study presents a methodology for quantitative assessment of the benefit yielded by the various engineered safety systems of a nuclear reactor containment from the standpoint of their capacity to protect the environment compared to their construction costs. The benefit is derived from an estimate of the possible damage from which the environment is protected, taking account of the probabilities of occurrence of malfunctions and accidents. For demonstration purposes, the methodology was applied to a 1 300-MWe PWR nuclear power station. The accident sequence considered was that of a major loss-of-coolant accident as investigated in detail in the German risk study. After determination of the benefits and cost/benefit ratio for the power plant and the containment systems as designed, the performance characteristics of three subsystems, the leakoff system, annulus exhaust air handling system and spray system, were varied. For this purpose, the parameters which describe these systems in the activity release programme were altered. The costs were simultaneously altered in order to take account of the performance divergences. By varying the performance of the individual sub-systems an optimization in design of these systems can be arrived at

  11. Improvement and verification of fast reactor safety analysis techniques

    International Nuclear Information System (INIS)

    Jackson, J.F.

    1975-01-01

    An initial analysis of the KIWI-TNT experiment using the VENUS-II disassembly code has been completed. The calculated fission energy release agreed with the experimental value to within about 3 percent. An initial model for analyzing the SNAPTRAN-2 core disassembly experiment was also developed along with an appropriate equation-of-state. The first phase of the VENUS-II/PAD comparison study was completed through the issuing of a preliminary report describing the results. A new technique to calculate a P-V-work curve as a function of the degree of core expansion following a disassembly excursion has been developed. The technique provides results that are consistent with the ANL oxide-fuel equation-of-state in VENUS-II. Evaluation and check-out of this new model are currently in progress

  12. Fusion Reactor Safety Research program. Annual report, FY-80

    International Nuclear Information System (INIS)

    Crocker, J.G.; Cohen, S.

    1981-06-01

    The report is in three sections. Outside contracts includes a report of newly-started study at the General Atomic Company to consider safety implications of low-activation materials, portions of two papers from ongoing work at PNL and ANL, reports of the lithium spill work at HEDL, the LITFIRE code development at MIT, and risk assessment at MIT, all of which are an expansion of FY-79 outside contracts. EG and G Activities includes adaptations of four papers of ongoing work in transient code development, tritium system risk assessment, heat transfer and fluid flow analysis, and fusion safety data base. Program Plan Development includes the Executive Summary of the Plan, which was completed in FY-80, and is accompanied by a list of publications and a brief outline of proposed FY-81 activities to be based on the Program Plan

  13. Handling and feeding of biomass to pressurized reactors: safety engineering

    Energy Technology Data Exchange (ETDEWEB)

    Wilen, Carl; Rautalin, Aimo (Valtion Teknillinen Tutkimuskeskus, Espoo (Finland). Lab. of Fuel and Process Technology)

    1993-01-01

    There are rather few literature references to or experience of the feed of biomass into a pressurized space. Alternatives given in the literature usually concern handling and feeding technology for coal. Some screw- or piston-operated plug feeders and coal and concrete pump equipment have, however, also been tested with biomasses. Explosion characteristics of fuels and their susceptibility to spontaneous ignition have been studied at both atmospheric and elevated pressures. The maximum explosion pressure and maximum rate of pressure rise, being critical factors in the process design and in the choice of safety equipment, have been determined under these conditions. In pressurized processes, the maintenance of sufficient inertization in fuel-feed systems is an especially critical factor. Peat, bark, and forest residues were used as biofuels, and lignite was used as reference fuel. The results obtained with a dynamic method for spontaneous ignition were compared with experience obtained from the operation of a commercial pressurized peat gasifier of 140 MW. (author)

  14. Efficient algorithms for flow simulation related to nuclear reactor safety

    International Nuclear Information System (INIS)

    Gornak, Tatiana

    2013-01-01

    Safety analysis is of ultimate importance for operating Nuclear Power Plants (NPP). The overall modeling and simulation of physical and chemical processes occuring in the course of an accident is an interdisciplinary problem and has origins in fluid dynamics, numerical analysis, reactor technology and computer programming. The aim of the study is therefore to create the foundations of a multi-dimensional non-isothermal fluid model for a NPP containment and software tool based on it. The numerical simulations allow to analyze and predict the behavior of NPP systems under different working and accident conditions, and to develop proper action plans for minimizing the risks of accidents, and/or minimizing the consequences of possible accidents. A very large number of scenarios have to be simulated, and at the same time acceptable accuracy for the critical parameters, such as radioactive pollution, temperature, etc., have to be achieved. The existing software tools are either too slow, or not accurate enough. This thesis deals with developing customized algorithm and software tools for simulation of isothermal and non-isothermal flows in a containment pool of NPP. Requirements to such a software are formulated, and proper algorithms are presented. The goal of the work is to achieve a balance between accuracy and speed of calculation, and to develop customized algorithm for this special case. Different discretization and solution approaches are studied and those which correspond best to the formulated goal are selected, adjusted, and when possible, analysed. Fast directional splitting algorithm for Navier-Stokes equations in complicated geometries, in presence of solid and porous obstacles, is in the core of the algorithm. Developing suitable pre-processor and customized domain decomposition algorithms are essential part of the overall algorithm amd software. Results from numerical simulations in test geometries and in real geometries are presented and discussed.

  15. Study of the performance of diagnostic radiology instruments during calibration

    International Nuclear Information System (INIS)

    Freitas, Rodrigo N. de; Vivolo, Vitor; Potiens, Maria da Penha A.

    2008-01-01

    Full text: The instruments used in diagnostic radiology measurements represent 8 % of the tested instruments by the calibration laboratory of IPEN annually (approximately 1600 in 2007). Considering that the calibration of this kind of instrument is performed biannually it is possible to conclude that almost 300 instruments are being used to measure the air kerma in diagnostic radiology clinics to determine the in beam values (in front of the patient), attenuated measurements (behind the patient) and scattered radiation. This work presents the results of the calibration of the instruments used in mammography, computed tomography, dental and conventional diagnostic radiology dosimetry, performed during the period of 2005 to 2007. Their performances during the calibrations measurements were evaluated. Although at the calibration laboratory there are three available series of radiation quality to this type of calibration (RQR, N and M, according to standards IEC 61267 and ISO 4037-1.), the applications can be assorted (general radiology, computed tomography, mammography, radiation protection and fluoroscopy). Depending on its design and behaviour , one kind of instrument can be used for one or more type of applications. The instruments normally used for diagnostic radiology measurements are ionization chambers with volumes varying from 3 to 1800 cm 3 , and can be cylindrical, spherical or plane parallel plates kind. They usually are sensitive to photon particles, with energies greater than 15 keV and can be used up to 1200 keV. In this work they were tested in X radiation fields from 25 to 150 kV, in specific qualities depending on the utilization of the instrument. The calibration results of 390 instruments received from 2005 to 2007 were analyzed. About 20 instruments were not able to be calibrated due to bad functioning. The calibration coefficients obtained were between 0.88 and 1.24. The uncertainties were always less than ± 3.6% to instruments used in scattered

  16. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1975

    International Nuclear Information System (INIS)

    1976-05-01

    Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T

  17. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1975

    Energy Technology Data Exchange (ETDEWEB)

    1976-05-01

    Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T.

  18. Current state of research on pressurized water reactor safety

    International Nuclear Information System (INIS)

    Couturier, Jean; Schwarz, Michel; Roubaud, Sebastien; Lavarenne, Caroline; Mattei, Jean-Marie; Rigollet, Laurence; Scotti, Oona; Clement, Christophe; Lancieri, Maria; Gelis, Celine; Jacquemain, Didier; Bentaib, Ahmed; Nahas, Georges; Tarallo, Francois; Guilhem, Gilbert; Cattiaux, Gerard; Durville, Benoit; Mun, Christian; Delaval, Christine; Sollier, Thierry; Stelmaszyk, Jean-Marc; Jeffroy, Francois; Dechy, Nicolas; Chanton, Olivier; Tasset, Daniel; Pichancourt, Isabelle; Barre, Francois; Bruna, Gianni; Evrard, Jean-Michel; Gonzalez, Richard; Loiseau, Olivier; Queniart, Daniel; Vola, Didier; Goue, Georges; Lefevre, Odile

    2018-03-01

    For more than 40 years, IPSN then IRSN has conducted research and development on nuclear safety, specifically concerning pressurized water reactors, which are the reactor type used in France. This publication reports on the progress of this research and development in each area of study - loss-of-coolant accidents, core melt accidents, fires and external hazards, component aging, etc. -, the remaining uncertainties and, in some cases, new measures that should be developed to consolidate the safety of today's reactors and also those of tomorrow. A chapter of this report is also devoted to research into human and organizational factors, and the human and social sciences more generally. All of the work is reviewed in the light of the safety issues raised by feedback from major accidents such as Chernobyl and Fukushima Daiichi, as well as the issues raised by assessments conducted, for example, as part of the ten-year reviews of safety at French nuclear reactors. Finally, through the subjects it discusses, this report illustrates the many partnerships and exchanges forged by IRSN with public, industrial and academic bodies both within Europe and internationally

  19. Steam explosion - physical foundations and relation to nuclear reactor safety

    International Nuclear Information System (INIS)

    Schumann, U.

    1982-08-01

    'Steam explosion' means the sudden evaporation of a fluid by heat exchange with a hotter material. Other terms are 'vapour explosion', 'thermal explosion', and 'energetic fuel-coolant interaction (FCI)'. In such an event a large fraction of the thermal energy initially stored in the hot material may possibly be converted into mechanical work. For pressurized water reactors one discusses (e.g. in risk analysis studies) a core melt-down accident during which molten fuel comes into contact with water. In the analysis of the consequences one has to investigate steam explosions. In this report an overview over the state of the knowledge is given. The overview is based on an extensive literature review. The objective of the report is to provide the basic knowledge which is required for understanding of the most important theories on the process of steam explosions. Following topics are treated: overview on steam explosion incidents, work potential, spontaneous nucleation, concept of detonation, results of some typical experiments, hydrodynamic fragmentation of drops, bubbles and jets, coarse mixtures, film-boiling, scenario of a core melt-down accident with possible steam-explosion in a pressurized water reactor. (orig.) [de

  20. Methodology development for statistical evaluation of reactor safety analyses

    International Nuclear Information System (INIS)

    Mazumdar, M.; Marshall, J.A.; Chay, S.C.; Gay, R.

    1976-07-01

    In February 1975, Westinghouse Electric Corporation, under contract to Electric Power Research Institute, started a one-year program to develop methodology for statistical evaluation of nuclear-safety-related engineering analyses. The objectives of the program were to develop an understanding of the relative efficiencies of various computational methods which can be used to compute probability distributions of output variables due to input parameter uncertainties in analyses of design basis events for nuclear reactors and to develop methods for obtaining reasonably accurate estimates of these probability distributions at an economically feasible level. A series of tasks was set up to accomplish these objectives. Two of the tasks were to investigate the relative efficiencies and accuracies of various Monte Carlo and analytical techniques for obtaining such estimates for a simple thermal-hydraulic problem whose output variable of interest is given in a closed-form relationship of the input variables and to repeat the above study on a thermal-hydraulic problem in which the relationship between the predicted variable and the inputs is described by a short-running computer program. The purpose of the report presented is to document the results of the investigations completed under these tasks, giving the rationale for choices of techniques and problems, and to present interim conclusions

  1. Small nuclear reactor safety design requirements for autonomous operation

    International Nuclear Information System (INIS)

    Kozier, K.S.; Kupca, S.

    1997-01-01

    Small nuclear power reactors offer compelling safety advantages in terms of the limited consequences that can arise from major accident events and the enhanced ability to use reliable, passive means to eliminate their occurrence by design. Accordingly, for some small reactor designs featuring a high degree of safety autonomy, it may be-possible to delineate a ''safety envelope'' for a given set of reactor circumstances within which safe reactor operation can be guaranteed without outside intervention for time periods of practical significance (i.e., days or weeks). The capability to operate a small reactor without the need for highly skilled technical staff permanently present, but with continuous remote monitoring, would aid the economic case for small reactors, simplify their use in remote regions and enhance safety by limiting the potential for accidents initiated by inappropriate operator action. This paper considers some of the technical design options and issues associated with the use of small power reactors in an autonomous mode for limited periods. The focus is on systems that are suitable for a variety of applications, producing steam for electricity generation, district heating, water desalination and/or marine propulsion. Near-term prospects at low power levels favour the use of pressurized, light-water-cooled reactor designs, among which those having an integral core arrangement appear to offer cost and passive-safety advantages. Small integral pressurized water reactors have been studied in many countries, including the test operation of prototype systems. (author)

  2. The need for a new approach to reactor safety

    International Nuclear Information System (INIS)

    Cave, L.; Holmes, R.E.; Holmes, P.J.

    1981-01-01

    The public's acceptance of nuclear power appears to be decreasing in many countries, partly owing to fears about the safety of reactors. In the paper the usefulness of an approach based on comparative risks is examined in the light of the view, expressed by behavioural scientists, that the public find the concept of risk difficult to understand and are more concerned with the possible consequences and benefits of nuclear power. On the premise that this view is correct, its implications in relation to reactor siting, reactor design, choice of reactor system and the economics of nuclear power are examined. This examination leads to some specific suggestions for future action in relation to the reduction of the possible consequences of nuclear accidents. It leads also to the view that there appears to be a close correlation between the public's perception of the strength of the national economy, the extent of its indigenous fuel resources and the degree of public hostility to nuclear power in any one country, although this concept requires further detailed study. (author)

  3. A radiological study on the velopharyngeal movement of dysarthric patients

    Energy Technology Data Exchange (ETDEWEB)

    Kim, M. J.; Oh, K. K.; Park, C. Y. [Yonsei University College of Medicine, Seoul (Korea, Republic of)

    1984-03-15

    Velopharyngeal incompetency may be the main cause of dysarthria. Velopharyngeal incompetency can be induced by congenital anomalies, such as cleft palate and short soft palate and deformity of soft palte, or complication of adenoidectomy, and neuromuscular disorders affecting the velopharyngeal movement. The present study is aimed to evaluate the velopharyngeal movement in dysarthric patients. The material consisted of 38 cases of dysarthric patients and 30 cases of non-dysarthric control persons examined at the Department of Radiology, Yonsei University College of Medicine from September, 1982 through August, 1983. The radiologic examinations of the soft palate and pharynx were done at neutral and phonation state using Toshiba 500mA Imaging Intensifier. All cases were subjected to morphometric analysis by measuring the soft palate and pharynx. Results obtained were as follows: 1. In control group, the length of the soft palate was 40.7{+-}0.71mm in neutral state and increased 11% in vowel sound, 13% in consonant sound. The thickness of the soft palate was 9.4{+-}0.19mm in neutral state and increased 17% in vowel sound, 16% in consonant sound. The distance between the lateral pharyngeal walls was 36.2{+-}0.92mm in neutral state and decreased 8% in vowel sound, 11% consonant sound. The gap between the soft palate and posterior pharyngeal walla was not present and the levator eminence was higher than the level of the hard palate in phonation. 2. Among the dysarthric patients, 1) In group of dysarthric patients patients with morphological abnormality, the thickness of soft palate was minimally changed in relation to the control group, while the distance between the lateral pharyngeal walls was more decreased than the control group. The gap between the soft palate and posterior pharyngeal wall was more than 3 mm in 90.9% of these cases, and the levator eminence was at or below the level of hard palate. 2) In group of dysarthric patients with functional abnormality, the

  4. A radiological study on the velopharyngeal movement of dysarthric patients

    International Nuclear Information System (INIS)

    Kim, M. J.; Oh, K. K.; Park, C. Y.

    1984-01-01

    Velopharyngeal incompetency may be the main cause of dysarthria. Velopharyngeal incompetency can be induced by congenital anomalies, such as cleft palate and short soft palate and deformity of soft palte, or complication of adenoidectomy, and neuromuscular disorders affecting the velopharyngeal movement. The present study is aimed to evaluate the velopharyngeal movement in dysarthric patients. The material consisted of 38 cases of dysarthric patients and 30 cases of non-dysarthric control persons examined at the Department of Radiology, Yonsei University College of Medicine from September, 1982 through August, 1983. The radiologic examinations of the soft palate and pharynx were done at neutral and phonation state using Toshiba 500mA Imaging Intensifier. All cases were subjected to morphometric analysis by measuring the soft palate and pharynx. Results obtained were as follows: 1. In control group, the length of the soft palate was 40.7±0.71mm in neutral state and increased 11% in vowel sound, 13% in consonant sound. The thickness of the soft palate was 9.4±0.19mm in neutral state and increased 17% in vowel sound, 16% in consonant sound. The distance between the lateral pharyngeal walls was 36.2±0.92mm in neutral state and decreased 8% in vowel sound, 11% consonant sound. The gap between the soft palate and posterior pharyngeal walla was not present and the levator eminence was higher than the level of the hard palate in phonation. 2. Among the dysarthric patients, 1) In group of dysarthric patients patients with morphological abnormality, the thickness of soft palate was minimally changed in relation to the control group, while the distance between the lateral pharyngeal walls was more decreased than the control group. The gap between the soft palate and posterior pharyngeal wall was more than 3 mm in 90.9% of these cases, and the levator eminence was at or below the level of hard palate. 2) In group of dysarthric patients with functional abnormality, the

  5. European in-pile investigations on fast breeder reactor safety

    International Nuclear Information System (INIS)

    Bailly, J.; Penet, F.; Teague, H.J.

    1977-01-01

    Because of the difficulties faced by the various organisations responsible for the design and safety analysis of fast reactors, in the conception and execution of perfectly representative experiments corresponding to the various hypothetical accidents considered, the European experts in this field have chosen to adopt a more fundamental approach. By the coordination of the efforts in the different countries and pooling the results, it appears that sufficient data can be assembled to permit them to: isolate the influence of the principle parameters on the course of an accident and to have an appreciation of the possibilities for detection and propagation; and validate calculational models of the essential phenomena, and determine the values of the adjustable parameters used in accident codes. The present paper does not propose to give an exhaustive description of the European experimental programmes, nor of the possibilities for exploiting the results in safety analysis. The aim is simply to show with the aid of results already obtained or expected from the immediate programme, that it should be possible to answer certain fundamental questions concerning those accidents at present considered most important. Particular consideration is given to local blockages (SCARABEE, DFR and MOL 7C programmes), unprotected loss of pumps leading to cooling failure, and inlet blockage (SCARABEE and CABRI), and reactivity excursions (CABRI and VIPER). In addition it is planned to study, as part of the SCARABEE programme, the long-term post-accident behaviour of fuel in some simple configurations. It is shown that these various results should lead to a great improvement in our understanding of the progress of the hypothetical accidents taken into account in the design of fast breeder reactors [fr

  6. Radiologic and clinical study of mycoplasam pneumonia in children

    Energy Technology Data Exchange (ETDEWEB)

    Baik, Seung Kug; Yoon, Young Woon; Yang, Dae Dong; Lee, Jong Yul; Choi, Hang Yong; Kim, Bong Ki [College of Medicine, Wallace Memorial Baptist Hospital, Pusan (Korea, Republic of)

    1990-10-15

    We studied 143 cases of serologically proven (cold agglutinin or 1HA test) M. Pneumonia in children below 15 year of age who admitted to Wallace Memorial Baptist Hospital between March 1986 and August 1988. The following results were noted : 1. Radiologic findings {center_dot} The patterns of lung infiltration were bronchopneumonic in 52.6%, interstitial in 24.5%, lobar in 3.5%, mixed in 1.3%, and normal or slightly increased bronchovascular markings in 18.1%. {center_dot} The degree of pulmonary involvement were minimal in 49.2%, moderate in 24.5% and extensive in 8.3%. {center_dot} The distribution of infiltration in the minimal and moderate pulmonary involvement were upper lobe in 28.6%, middle lobe in 17.2% and lower lobe in 54.3%. {center_dot} Other findings were bilateral involvement in 31.5%, pleural involvement in 15.8%, new area of consolidation in 3.5% and hilar lymph node involvement in 34.2%. 2. The most common duration of the period between the onset of symptom and confirmation of the diagnosis was 7-14 days. 3. The sex distribution was 1.3 : 1 in male to female ratio. 4. The most peak age incidence was seen in 10-13, and the second one in 4 - 7 year. 5. As for the concomitant illness and complication, asthmatic bronchitis was most common (23 cases, 16.1%) followed by pharyngitis, sinusitis, skin rash and gastroenteritis, etc.

  7. Full scale reactor safety experiments performed in the Marviken Power Station Sweden

    International Nuclear Information System (INIS)

    Thoren, H.G.; Ericson, L.

    1977-01-01

    Since 1972 experiments oriented towards increasing the understanding of reactor safety processes have been performed at the Marviken Power Station. This was originally built as a direct cycle BHWR but was never taken into nuclear operation. In addition to Sweden, the countries represented in these experiments are Denmark, the Federal Republic of Germany, Finland, Norway, the United States, the Netherlands, France and Japan. The first series of sixteen experiments included studies of the response of the PS-containment to simulated ruptures in the pipe systems that are connected to the pressure vessel. These tests were completed in 1973 and also included experimental studies of iodine transport, containment leakage, the behaviour of auxiliary components under accident conditions and pressure fluctuations in the wetwell water pool. One of the more essential findings of the tests was that the containment performance was in accordance with the pre-test calculations. A second series of eight blowdown tests was begun in February 1976. The main purpose of these tests is to provide additional information as to the characteristics of the pressure oscillations inside the containment and primarily in the wetwell water pool under different conditions. These oscillations were observed in the first series of blowdowns but only low frequencies could then be detected due to limitations in the measurement system. The measurement system was therefore substantially extended for this second series of experiments. A summary of the results from these two sets of blowdown tests are given in the paper. In 1976 preparations for a new test program were initiated. The objective of these tests is to improve the understanding of critical flow in the low quality and subcooled flow regions through short length, large diameter pipes. Extensive modifications of the test facility will be necessary in order to allow a discharge flow through openings which are up to 500 mm in diameter. Advanced plans

  8. A study on the civil liability of radiological technologist in medical malpractice

    International Nuclear Information System (INIS)

    Lim, Chang Seon

    1995-01-01

    Recently the suits for medical malpractice are gradually increasing in this country. The main purpose of this study is to excavate the most suitable theories about civil liabilities on medical malpractice by radiological technologist. To solve the above-mentioned problems in medical malpractice, I have proceeded to make a survey of traditional theories and tried to excavate the most suitable theories for our medical circumstances among those theories. Both domestic and foreign relevant professional literatures and legal cases were investigated in this study. Several important findings of this study are as follows. First, the nature of legal interrelationship between radiological technologist and physician(or the representative of a hospital) is to define the content of employment. But in the eye of medical law, the interrelationship between radiological technologist and physician is written that radiological technologist should be directed by physician. Second, the nature of legal interrelationship between patient and physician(or the representative of a hospital) is to define the content of legal obligation of physician(or the representative of a hospital), and radiological technologist execute his obligation as proxy for physician. Therefore, patient can not clame any legal right to radiological technologist. Third, radiological technologist has the obligation of Due Care in medical practice. Fourth, on the medical malpractice by radiological technologist the civil liability can be treated as either tortious liability or contractual liability, and physician (or the representative of hospital) take the responsibility for the damage compensation. In this case, physician has the right of indemnity to radiological technologist. But it should be dinied or extremely limited

  9. The radiologic technologists' health study in South Korea. Study design and baseline results

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Won Jin [Korea Univ. College of Medicine, Seoul (Korea, Republic of). Dept. of Preventive Medicine; Ha, Mina [Dankook Univ. College of Medicine, Cheonan (Korea, Republic of). Dept. of Preventive Medicine; Hwang, Seung-sik [Inha Univ. School of Medicine, Incheon (Korea, Republic of). Dept. of Social and Preventive Medicine; and others

    2015-08-15

    To describe the study design, methods, and baseline results of a prospective cohort of radiologic technologists which we have initiated in South Korea. The cohort participants were enrolled through a self-administered questionnaire survey administered from April 2012 to May 2013. Survey data were linked with radiation dosimetry, a cancer registry, and health insurance data by personal identification numbers. A nationwide representative survey was also conducted using a stratified random sampling design with face-to-face interviews. A total of 12,387 radiologic technologists were enrolled, which accounted for approximately 63 % of all diagnostic radiologic technologists working in South Korea. For nationwide survey, 585 workers were interviewed using the detailed questionnaire, and buccal cells were also collected by scraping the inside of the cheek. The majority of study subjects were under 50-year-old and male workers. The average annual effective dose of radiation declined both men (from 2.75 to 1.43 mSv) and women (from 1.34 to 0.95 mSv) over the period of 1996-2011. A total of 99 cancers (66 cancers in men and 33 in women) were reported from 1992 to 2010. The standardized incidence ratio of all cancer combined was significantly lower in men (SIR = 0.75, 95 % CI 0.58-0.96) than general population, but the ratios for thyroid cancer were significantly higher than expected among both men and women. This cohort provides comprehensive information on work activities and health status of diagnostic radiologic technologists. In addition, the nationwide representative sample provides unique opportunities compared with previous radiologic technologist studies.

  10. The radiologic technologists' health study in South Korea: study design and baseline results.

    Science.gov (United States)

    Lee, Won Jin; Ha, Mina; Hwang, Seung-sik; Lee, Kyoung-Mu; Jin, Young-Woo; Jeong, Meeseon; Jun, Jae Kwan; Cha, Eun Shil; Ko, Yousun; Choi, Kyung-Hwa; Lee, Jung-Eun

    2015-08-01

    To describe the study design, methods, and baseline results of a prospective cohort of radiologic technologists which we have initiated in South Korea. The cohort participants were enrolled through a self-administered questionnaire survey administered from April 2012 to May 2013. Survey data were linked with radiation dosimetry, a cancer registry, and health insurance data by personal identification numbers. A nationwide representative survey was also conducted using a stratified random sampling design with face-to-face interviews. A total of 12,387 radiologic technologists were enrolled, which accounted for approximately 63% of all diagnostic radiologic technologists working in South Korea. For nationwide survey, 585 workers were interviewed using the detailed questionnaire, and buccal cells were also collected by scraping the inside of the cheek. The majority of study subjects were under 50-year-old and male workers. The average annual effective dose of radiation declined both men (from 2.75 to 1.43 mSv) and women (from 1.34 to 0.95 mSv) over the period of 1996-2011. A total of 99 cancers (66 cancers in men and 33 in women) were reported from 1992 to 2010. The standardized incidence ratio of all cancer combined was significantly lower in men (SIR = 0.75, 95% CI 0.58-0.96) than general population, but the ratios for thyroid cancer were significantly higher than expected among both men and women. This cohort provides comprehensive information on work activities and health status of diagnostic radiologic technologists. In addition, the nationwide representative sample provides unique opportunities compared with previous radiologic technologist studies.

  11. The radiologic technologists' health study in South Korea. Study design and baseline results

    International Nuclear Information System (INIS)

    Lee, Won Jin; Ha, Mina; Hwang, Seung-sik

    2015-01-01

    To describe the study design, methods, and baseline results of a prospective cohort of radiologic technologists which we have initiated in South Korea. The cohort participants were enrolled through a self-administered questionnaire survey administered from April 2012 to May 2013. Survey data were linked with radiation dosimetry, a cancer registry, and health insurance data by personal identification numbers. A nationwide representative survey was also conducted using a stratified random sampling design with face-to-face interviews. A total of 12,387 radiologic technologists were enrolled, which accounted for approximately 63 % of all diagnostic radiologic technologists working in South Korea. For nationwide survey, 585 workers were interviewed using the detailed questionnaire, and buccal cells were also collected by scraping the inside of the cheek. The majority of study subjects were under 50-year-old and male workers. The average annual effective dose of radiation declined both men (from 2.75 to 1.43 mSv) and women (from 1.34 to 0.95 mSv) over the period of 1996-2011. A total of 99 cancers (66 cancers in men and 33 in women) were reported from 1992 to 2010. The standardized incidence ratio of all cancer combined was significantly lower in men (SIR = 0.75, 95 % CI 0.58-0.96) than general population, but the ratios for thyroid cancer were significantly higher than expected among both men and women. This cohort provides comprehensive information on work activities and health status of diagnostic radiologic technologists. In addition, the nationwide representative sample provides unique opportunities compared with previous radiologic technologist studies.

  12. Radiologic study on measurement of lumbosacral angel in backache patients

    International Nuclear Information System (INIS)

    Lee, Jin Woo; Chung, Jin Heung; Kwon, Oh Chung; Rhee, Byung Chull

    1982-01-01

    The radiologic findings of lumbosacral spline and measurement of lumbosacral angle were analysed in 238 with backache and 102 without backache which were visited Chung Nam University from Mach 1980 to July 1981. The measurement of lumbosacral angle was based on a method of Fergson. The results obtained were as follows: 1. The age group of 18 to 29 years was most common in backache group and the male was affected more frequently than the female with the ratio of 1.9 : 1. 2. The patients with backache, the overall mean lumbosacral angles were 44.2 ±2.6 .deg. in male and 35.8 ± 2.0.deg. in female. In patients without backache, in control group, the overall mean lumbosacral angles were 32.6 ± 0.7 .deg. in male and 33.4 ± 1.4 .deg. in female. 3. In control group, difference of means between male and female was about 1 .deg. in patients with backache, the overall mean lumbosacral angles were increased about 12 .deg. in male and 2 .deg. in female than control group. In patients with and without backache, no significant difference of lumbosacral angle between the 4 age groups was present. 4. In backache group, increased lordosis was more common and increased lumbosacral angle than the decreased lordosis. 5. In backache group, lumbosacral angle of abnormal radiologic findings in lumbosacral spline was significantly increased than control group. 6. In patients with backache, radiologic findings and its lumbosacral angles were a lumbosacral anomaly 56 cases (23.5%): 46.9 .deg., increased lumbar lordosis 46 cases (19.2%): 48.1 .deg., osteoarthritis 44 cases (18.5%): 40.8 .deg., decreased lumbar lordosis 30 cases (12.6%): 29.9 .deg., in order, and these radiologic findings were similar with many other authors

  13. Radiologic study on measurement of lumbosacral angel in backache patients

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jin Woo; Chung, Jin Heung; Kwon, Oh Chung; Rhee, Byung Chull [Chung Nam National University College of Medicine, Deajeon (Korea, Republic of)

    1982-06-15

    The radiologic findings of lumbosacral spline and measurement of lumbosacral angle were analysed in 238 with backache and 102 without backache which were visited Chung Nam University from Mach 1980 to July 1981. The measurement of lumbosacral angle was based on a method of Fergson. The results obtained were as follows: 1. The age group of 18 to 29 years was most common in backache group and the male was affected more frequently than the female with the ratio of 1.9 : 1. 2. The patients with backache, the overall mean lumbosacral angles were 44.2 {+-}2.6 .deg. in male and 35.8 {+-} 2.0.deg. in female. In patients without backache, in control group, the overall mean lumbosacral angles were 32.6 {+-} 0.7 .deg. in male and 33.4 {+-} 1.4 .deg. in female. 3. In control group, difference of means between male and female was about 1 .deg. in patients with backache, the overall mean lumbosacral angles were increased about 12 .deg. in male and 2 .deg. in female than control group. In patients with and without backache, no significant difference of lumbosacral angle between the 4 age groups was present. 4. In backache group, increased lordosis was more common and increased lumbosacral angle than the decreased lordosis. 5. In backache group, lumbosacral angle of abnormal radiologic findings in lumbosacral spline was significantly increased than control group. 6. In patients with backache, radiologic findings and its lumbosacral angles were a lumbosacral anomaly 56 cases (23.5%): 46.9 .deg., increased lumbar lordosis 46 cases (19.2%): 48.1 .deg., osteoarthritis 44 cases (18.5%): 40.8 .deg., decreased lumbar lordosis 30 cases (12.6%): 29.9 .deg., in order, and these radiologic findings were similar with many other authors.

  14. Anismus, Physiology, Radiology: Is It Time for Some Pragmatism? A Comparative Study of Radiological and Anorectal Physiology Findings in Patients With Anismus.

    Science.gov (United States)

    Pisano, Umberto; Irvine, Lesley; Szczachor, Justina; Jawad, Ahsin; MacLeod, Andrew; Lim, Michael

    2016-10-01

    Anismus is a functional disorder featuring obstructive symptoms and paradoxical contractions of the pelvic floor. This study aims to establish diagnosis agreement between physiology and radiology, associate anismus with morphological outlet obstruction, and explore the role of sphincteric pressure and rectal volumes in the radiological diagnosis of anismus. Consecutive patients were evaluated by using magnetic resonance imaging proctography/fluoroscopic defecography and anorectal physiology. Morphological radiological features were associated with physiology tests. A categorical analysis was performed using the chi-square test, and agreement was assessed via the kappa coefficient. A Mann-Whitney test was used to assess rectal volumes and sphincterial pressure distributions between groups of patients. A P-value of Anismus was seen radiologically and physiologically in 18 (41.8%) and 12 patients (27.9%), respectively. The agreement between modalities was 0.298 (P = 0.04). Using physiology as a reference, radiology had positive and negative predictive values of 44% and 84%, respectively. Rectoceles, cystoceles, enteroceles and pathological pelvic floor descent were not physiologically predictive of animus (P > 0.05). The sphincterial straining pressure was 71 mmHg in the anismus group versus 12 mmHg. Radiology was likely to identify anismus when the straining pressure exceeded 50% of the resting pressure (P = 0.08). Radiological techniques detect pelvic morphological abnormalities, but lead to overdiagnoses of anismus. No proctographic pathological feature predicts anismus reliably. A stronger pelvic floor paradoxical contraction is associated with a greater likelihood of detection by proctography.

  15. Fuel-coolant interaction (FCI) phenomena in reactor safety. Current understanding and future research needs

    Energy Technology Data Exchange (ETDEWEB)

    Speis, T.P. [Maryland Univ., College Park, MD (United States); Basu, S.

    1998-01-01

    This paper gives an account of the current understanding of fuel-coolant interaction (FCI) phenomena in the context of reactor safety. With increased emphasis on accident management and with emerging in-vessel core melt retention strategies for advanced light water reactor (ALWR) designs, recent interest in FCI has broadened to include an evaluation of potential threats to the integrity of reactor vessel lower head and ex-vessel structural support, as well as the role of FCI in debris quenching and coolability. The current understanding of FCI with regard to these issues is discussed, and future research needs to address the issues from a risk perspective are identified. (author)

  16. Development of the evaluation methods in reactor safety analyses and core characteristics

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    In order to support the safety reviews by NRA on reactor safety design including the phenomena with multiple failures, the computer codes are developed and the safety evaluations with analyses are performed in the areas of thermal hydraulics and core characteristics evaluation. In the code preparation of safety analyses, the TRACE and RELAP5 code were prepared to conduct the safety analyses of LOCA and beyond design basis accidents with multiple failures. In the core physics code preparation, the functions of sensitivity and uncertainty analysis were incorporated in the lattice physics code CASMO-4. The verification of improved CASMO-4 /SIMULATE-3 was continued by using core physics data. (author)

  17. Severe accident assessment. Results of the reactor safety research project VAHTI

    International Nuclear Information System (INIS)

    Sairanen, R.

    1997-10-01

    The report provides a summary of the publicly funded nuclear reactor safety research project Severe Accident Management (VAHTI). The project has been conducted at the Technical Research Centre of Finland (VTT) during the years 1994-96. The main objective was to assist the severe accident management programmes of the Finnish nuclear power plants. The project was divided into five work packages: (1) thermal hydraulic validation of the APROS code, (2) core melt progression within a BWR pressure vessel, (3) failure mode of the BWR pressure vessel, (4) Aerosol behaviour experiments, and (5) development of a computerized severe accident training tool

  18. Status of SACRD: a data base for fast reactor safety computer codes

    International Nuclear Information System (INIS)

    Greene, N.M.; Flanagan, G.F.; Alter, H.

    1982-01-01

    In 1975 work was initiated to provide a central computerized data collection of evaluated data for use in fast reactor safety computer codes. This data base is called SACRD and is intended to encompass handbook and other nonproblem-dependent data related to LMFBR's, especially at extreme conditions where little or no experimental data are available. Version 1 of the data base was released in the latter part of 1978 and remained the standard version until Version 81, which was released in October 1981

  19. Basic researches on thermo-hydraulic non-equilibrium phenomena related to nuclear reactor safety

    International Nuclear Information System (INIS)

    Sakurai, Akira; Kataoka, Isao; Aritomi, Masanori.

    1989-01-01

    A review was made of recent developments of fundamental researches on thermo-hydraulic non-equilibrium phenomena related to light water reactor safety, in relation to problems to be solved for the improvement of safety analysis codes. As for the problems related to flow con ditions, fundamental researches on basic conservation equations and constitutive equations for transient two-phase flow were reviewed. Regarding to the problems related to thermal non-equilibrium phenomena, fundamental researches on film boiling in pool and forced convection, transient boiling heat transfer and flow behavior caused by pressure transients were reviewed. (author)

  20. Fast reactor safety testing in Transient Reactor Test (TREAT) in the 1980s

    International Nuclear Information System (INIS)

    Wright, A.E.; Dutt, D.S.; Harrison, L.J.

    1990-01-01

    Several series of fast reactor safety tests were performed in TREAT during the 1980s. These focused on the transient behavior of full-length oxide fuels (US reference, UK reference, and US advanced design) and on modern metallic fuels. Most of the tests addressed fuel behavior under transient overpower or loss-of-flow conditions. The test series were the PFR/TREAT tests; the RFT, TS, CDT, and RX series on oxide fuels; and the M series on metallic fuels. These are described in terms of their principal results and relevance to analyses and safety evaluation. 4 refs., 3 tabs

  1. An overview of FFTF [Fast Flux Test Facility] contributions to Liquid Metal Reactor Safety

    International Nuclear Information System (INIS)

    Waltar, A.E.; Padilla, A. Jr.

    1990-11-01

    The Fast Flux Test Facility has provided a very useful framework for testing the advances in Liquid Metal Reactor Safety Technology. During the licensing phase, the switch from a nonmechanistic bounding technique to the mechanistic approach was developed and implemented. During the operational phase, the consideration of new tests and core configurations led to use of the anticipated-transients-without-scram approach for beyond design basis events and the move towards passive safety. The future role of the Fast Flux Test Facility may involve additional passive safety and waste transmutation tests. 26 refs

  2. Physics constraints on the design of fast reactor safety test facilities

    International Nuclear Information System (INIS)

    Travelli, A.; Meneghetti, D.; Matos, J.; Snelgrove, J.; Shaftman, D.H.; Tzanos, C.; Lam, S.K.; Pennington, E.M.; Woodruff, W.L.

    1976-01-01

    This paper discusses the physics foundations common to all fast reactor safety test facilities and the constraints which they impose on the design. While detailed design discussions are confined to the experience with six ANL designs, available data from other designs are used to confirm the validity of the considerations and to broaden the scope of the discussion. This helps to view the various designs as a unified effort, to define their potential capabilities, and to assess how they could best complement each other

  3. Study about chemical and radiological toxicity of rare earths

    International Nuclear Information System (INIS)

    Goncalez, O.L.

    1987-02-01

    The maximum permissible concentration in workplace air for an admixture of rare earths is calculated to be 1.47 mg/m 3 of air. This value takes into account the biological mean-life of those chemical elements in human body and acute toxicological data. A simplified mathematical models is done that describes the body content of this product as a time function, for cronic intoxication by air particulate inhalation. Under the radiological point of view the limit calculated for the air concentration is about 100 mg/m 3 , showing that the chemical toxity of these products is predominant. (Author) [pt

  4. RADIOLOGY EDUCATION: A PILOT STUDY TO ASSESS KNOWLEDGE OF MEDICAL STUDENTS REGARDING IMAGING IN TRAUMA.

    Science.gov (United States)

    Siddiqui, Saad; Saeed, Muhammad Anwar; Shah, Noreen; Nadeem, Naila

    2015-01-01

    Trauma remains one of the most frequent presentations in emergency departments. Imaging has established role in setting of acute trauma with ability to identify potentially fatal conditions. Adequate knowledge of health professionals regarding trauma imaging is vital for improved healthcare. In this work we try to assess knowledge of medical students regarding imaging in trauma as well as identify most effective way of imparting radiology education. This cross-sectional pilot study was conducted at Aga Khan University Medical College & Khyber Girls Medical College, to assess knowledge of medical students regarding imaging protocols practiced in initial management of trauma patients. Only 40 & 20% respectively were able to identify radiographs included in trauma series. Very few had knowledge of correct indication for Focused abdominal sonography in trauma. Clinical radiology rotation was reported as best way of learning radiology. Change in curricula & restructuring of clinical radiology rotation structure is needed to improve knowledge regarding Trauma imaging.

  5. Study on the action guidelines for medical support team for nuclear and radiological emergency

    International Nuclear Information System (INIS)

    Liu Chang'an; Liu Ying; Geng Xiusheng

    2006-01-01

    Objective: To study the action guidelines for medical support team for nuclear and radiological emergency. Methods: It is based on the experience and lessons learned in the course of meeting the emergencies preparedness and response of nuclear and radiological emergencies in China and abroad with the reference of the relevant reports of International Atomic Energy Agency. Results: Essential requirements and practical recommendations for the roles, responsibilities, emergency preparedness, principles and procedures of medical assistance at the scene, as well as the radiological protection of medical support team were provided. Conclusion: The document mentioned above can be applied to direct the establishment, effective medical preparedness and response of the medical support team for nuclear and radiological emergency. (authors)

  6. Reconciling quality and cost: A case study in interventional radiology

    International Nuclear Information System (INIS)

    Zhang, Li; Mahnken, Andreas; Domroese, Sascha

    2015-01-01

    To provide a method to calculate delay cost and examine the relationship between quality and total cost. The total cost including capacity, supply and delay cost for running an interventional radiology suite was calculated. The capacity cost, consisting of labour, lease and overhead costs, was derived based on expenses per unit time. The supply cost was calculated according to actual procedural material use. The delay cost and marginal delay cost derived from queueing models was calculated based on waiting times of inpatients for their procedures. Quality improvement increased patient safety and maintained the outcome. The average daily delay costs were reduced from 1275 EUR to 294 EUR, and marginal delay costs from approximately 2000 EUR to 500 EUR, respectively. The one-time annual cost saved from the transfer of surgical to radiological procedures was approximately 130,500 EUR. The yearly delay cost saved was approximately 150,000 EUR. With increased revenue of 10,000 EUR in project phase 2, the yearly total cost saved was approximately 290,000 EUR. Optimal daily capacity of 4.2 procedures was determined. An approach for calculating delay cost toward optimal capacity allocation was presented. An overall quality improvement was achieved at reduced costs. (orig.)

  7. Clinical and radiologic study of odontogenic keratocyst in jaws

    International Nuclear Information System (INIS)

    Choi, Jong Ho; Park, Chang Seo

    1987-01-01

    The author has clinically and radiologically investigated 57 cases of odontogenic keratocyst in 47 patients consisted of 26 males and 21 females aged from 2 to 63 years, who were pathologically diagnosed as odontogenic keratocyst at infirmaries of dental colleges, Yonsei University and Seoul national university during 1965-1986. The results were as follows: 1. The peak incidence of the disease was on their teenagers (29.8%). The ratio of Male/Female was 1.23 : 1 and incidence rate of males showed higher than their counterpart. 2. The most frequent complains were swelling in (65.9%) followed by pus discharge, unknown mass, pain, residual root. 3. The most common site was mandibular third molar and mandibular ramus region (15.8%) followed by mandibular body and ramus, mandibular third molar, mandibular anterior teeth. Incidence of this disease in mandibule was higher than in maxilla. 4. The lesions not associated with adjacent teeth were (14.0%) and in the lesions associated with adjacent teeth (31.5%) showed root resorption, (50.9%) were without root resorption, (35.1%) showed tooth migration and (50.9%) were without tooth migration. 5. The border types of the lesions were scalloped type in (52.6%), smooth type in (47.4%) and morphological type were unilocular in (50.9%), multilocular in (49.1%). 6. The radiologic cyst type of the lesions were follicular type (42.1%) followed by primordial, unclassified odontogenic, residual, lateral periodontal, median mandibular, globulomaxillary type.

  8. Reconciling quality and cost: A case study in interventional radiology

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Li; Mahnken, Andreas [University Hospital Giessen and Marburg, Philipps University of Marburg, Department of Diagnostic and Interventional Radiology, Baldinger Strasse, Marburg (Germany); Domroese, Sascha [University Hospital Giessen and Marburg, Philipps University of Marburg, Division of Controlling, Baldinger Strasse, Marburg (Germany)

    2015-10-15

    To provide a method to calculate delay cost and examine the relationship between quality and total cost. The total cost including capacity, supply and delay cost for running an interventional radiology suite was calculated. The capacity cost, consisting of labour, lease and overhead costs, was derived based on expenses per unit time. The supply cost was calculated according to actual procedural material use. The delay cost and marginal delay cost derived from queueing models was calculated based on waiting times of inpatients for their procedures. Quality improvement increased patient safety and maintained the outcome. The average daily delay costs were reduced from 1275 EUR to 294 EUR, and marginal delay costs from approximately 2000 EUR to 500 EUR, respectively. The one-time annual cost saved from the transfer of surgical to radiological procedures was approximately 130,500 EUR. The yearly delay cost saved was approximately 150,000 EUR. With increased revenue of 10,000 EUR in project phase 2, the yearly total cost saved was approximately 290,000 EUR. Optimal daily capacity of 4.2 procedures was determined. An approach for calculating delay cost toward optimal capacity allocation was presented. An overall quality improvement was achieved at reduced costs. (orig.)

  9. Chondroblastoma: A clinical and radiological study of 104 cases

    Energy Technology Data Exchange (ETDEWEB)

    Bloem, J.L.; Mulder, J.D.

    1985-06-01

    The clinical and radiographic findings in 104 patients with chondroblastoma are presented. Pain was an almost constant presenting complaint, often accompanied in the case of para-articular lesions by impaired function of an adjacent joint. The majority (80%) were in long bones with a mean age of presentation of 16 years. The characteristic radiological image of these lesions was an eccentric radiolucency, having a sharply defined sclerotic margin and containing areas of calcification in approximately a third of cases. They were always related to a growth plate. Nearly half were confined to the affected epiphysis or apophysis itself, but most of the remainder had traversed the growth plate to involve also the adjacent metaphysis. The bones around the knee and the proximal ends of the humerus and femur were the sites of predilection. A minority (20%) affected flat bones and short tubular bones of the hand and foot, with a peculiar affinity for the calcaneus and talus. The mean age of presentation of these was 28 years. The radiological pattern was similar, except for a greater tendency to expand the affected bone. Complications included the formation of a secondary aneurysmal bone cyst in 16 cases (10 of them in long bones), one malignant chondroblastoma, and one fibrosarcoma developing after radiation of the original chondroblastoma.

  10. Clinical and radiologic study of odontogenic keratocyst in jaws

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Jong Ho; Park, Chang Seo [Dept. of Dental Radiology, Dental Science, Yonsei University, Seoul (Korea, Republic of)

    1987-11-15

    The author has clinically and radiologically investigated 57 cases of odontogenic keratocyst in 47 patients consisted of 26 males and 21 females aged from 2 to 63 years, who were pathologically diagnosed as odontogenic keratocyst at infirmaries of dental colleges, Yonsei University and Seoul national university during 1965-1986. The results were as follows: 1. The peak incidence of the disease was on their teenagers (29.8%). The ratio of Male/Female was 1.23 : 1 and incidence rate of males showed higher than their counterpart. 2. The most frequent complains were swelling in (65.9%) followed by pus discharge, unknown mass, pain, residual root. 3. The most common site was mandibular third molar and mandibular ramus region (15.8%) followed by mandibular body and ramus, mandibular third molar, mandibular anterior teeth. Incidence of this disease in mandibule was higher than in maxilla. 4. The lesions not associated with adjacent teeth were (14.0%) and in the lesions associated with adjacent teeth (31.5%) showed root resorption, (50.9%) were without root resorption, (35.1%) showed tooth migration and (50.9%) were without tooth migration. 5. The border types of the lesions were scalloped type in (52.6%), smooth type in (47.4%) and morphological type were unilocular in (50.9%), multilocular in (49.1%). 6. The radiologic cyst type of the lesions were follicular type (42.1%) followed by primordial, unclassified odontogenic, residual, lateral periodontal, median mandibular, globulomaxillary type.

  11. Development of 3D CFD simulation method in nuclear reactor safety analysis

    International Nuclear Information System (INIS)

    Rosli Darmawan; Mariah Adam

    2012-01-01

    One of the most prevailing issues in the operation of nuclear reactor is the safety of the system. Worldwide publicity on a few nuclear accidents as well as the notorious Hiroshima and Nagasaki bombing have always brought about public fear on anything related to nuclear. Most findings on the nuclear reactor accidents are closely related to the reactor cooling system. Thus, the understanding of the behaviour of reactor cooling system is very important to ensure the development and improvement on safety can be continuously done. Throughout the development of nuclear reactor technology, investigation and analysis on reactor safety have gone through several phases. In the early days, analytical and experimental methods were employed. For the last three decades 1D system level codes were widely used. The continuous development of nuclear reactor technology has brought about more complex system and processes of nuclear reactor operation. More detailed dimensional simulation codes are needed to assess these new reactors. This paper discusses the development of 3D CFD usage in nuclear reactor safety analysis worldwide. A brief review on the usage of CFD at Malaysia's Reactor TRIGA PUSPATI is also presented. (author)

  12. Recent developments in iodine chemistry in Canada. Present and future applications to reactor safety

    International Nuclear Information System (INIS)

    Fluke, R.J.; Weaver, K.R.; Kupferschmidt, W.C.H.; Wren, J.C.; Ball, J.M.; Evans, G.J.

    1997-01-01

    In Canada, there exists a mature research programme directed towards resolving the nuclear safety and licensing questions surrounding fission product iodine. This integrated programme has had the long term objectives of developing a mechanistic understanding of the important aspects of iodine behaviour in containment, and of producing a mechanistic computer code to predict iodine behaviour under conditions of interest. The research is funded by Canadian Utilities and AECL through the CANDU Owners Group. In parallel with the research, an applications effort is underway to put existing research results into service for the resolution of reactor safety and licensing issues, as well as to identify and develop solutions for more comprehensive problems, such as chemical mitigation strategies to control post-accident iodine release. The present paper describes (a) the present status and objectives of R and D on iodine, its recent evolution and its significant achievements, (b) the analytical tools that are emerging from this programme and (c) existing and planned future applications of the results of the iodine R and D programme. The author concludes with an assessment of the impact that the iodine programme has had on reactor safety and licensing questions in Canada

  13. Reactor safety activities at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN)-Nuclebras

    International Nuclear Information System (INIS)

    Pinheiro, R.B.

    1986-08-01

    This report presents the major activities developed at NUCLEBRAS in the area of Reactor Safety. The Thermohydraulics and Reactor Safety program consists of activities in the analytical and experimental area. The more recent activities under way in the analytical area are presented together with some results. They are mainly related to the development and assessment of advanced computer codes to be used in the analysis of the behavior of the plant during operational transients and postulated accidents and in thermohydraulic core design. In the experimental area, the main accomplishments and activities under way are reported they refer to steady state CHF tests in a 9-rod bundle and rewetting experiments in a tubular test section. In particular, the status of the design development of a new facility for Separate Effects LOCA tests (DTL-ES) is described. Concerning the Components Testing program, the basic characteristics of a valve test facility (CTC) are described and the present status of its construction is reported. Reference is also made to existing installations and a summary of tests already performed for Angra-2 components qualification is presented. (Author) [pt

  14. Modular High Temperature Gas-Cooled Reactor Safety Basis and Approach

    Energy Technology Data Exchange (ETDEWEB)

    David Petti; Jim Kinsey; Dave Alberstein

    2014-01-01

    Various international efforts are underway to assess the safety of advanced nuclear reactor designs. For example, the International Atomic Energy Agency has recently held its first Consultancy Meeting on a new cooperative research program on high temperature gas-cooled reactor (HTGR) safety. Furthermore, the Generation IV International Forum Reactor Safety Working Group has recently developed a methodology, called the Integrated Safety Assessment Methodology, for use in Generation IV advanced reactor technology development, design, and design review. A risk and safety assessment white paper is under development with respect to the Very High Temperature Reactor to pilot the Integrated Safety Assessment Methodology and to demonstrate its validity and feasibility. To support such efforts, this information paper on the modular HTGR safety basis and approach has been prepared. The paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach. The paper gives those involved in the assessment of advanced reactor designs an opportunity to assess an advanced design that has already received extensive review by regulatory authorities and to judge the utility of recently proposed new methods for advanced reactor safety assessment such as the Integrated Safety Assessment Methodology.

  15. Evolution of the radiological protection policy. Applications in developing countries. IPEN a case of study

    International Nuclear Information System (INIS)

    Gordon, A.M.P.L.; Sordi, G.M.A. A.

    2006-01-01

    This paper aims to show the radiological protection development in Brazil from the beginning, when President Joao Cafe Filho signed an agreement with the U.S.A. In this agreement, Brazil joined the 'Atoms for Peace' program established on August 3., 1955. Yet in 1955, Brazil participated as a foundation member in the International Atomic Energy Agency (IAEA). As a result, the Iea - 'Instituto de Energia Atomica'- was created on August 31., 1956 and a research reactor type swimming pool was installed to produce radioisotopes and prepare experts in the field of nuclear activities. This reactor is maintained in operation at the Instituto de Pesquisas Energeticas e Nucleares (IPEN), former Iea. Having the Iea as a case of study, we analyze the radiological protection evolution during the fifty years of its life. We correlate this development with the Brazilian National Nuclear Energy Commission (CNEN) Regulations. CNEN was also created in 1956. The first safety standard in Brazil was delivered in 1973. Therefore, this paper will focus the radiological protection development at national level. Both institutions followed the international radiological protection recommendations, under the difficulties imposed by the historical conditions of a developing country. In order to have an outline of the radiological protection development, we inform that it was started as a section of the Radiological Division at the Iea. At that time, the Iea had four divisions. The radiological protection was performed by four people, being two physicists and two technicians that accomplished all the duties. On that occasion, approximately 30 people operated the Iea. The work staff at IPEN increased, arriving to 1600 people in 1998, including 150 persons in the radiological protection activities. Nowadays, 1200 people, including 100 persons in the health physics duties operate the IPEN. (authors)

  16. Evolution of the radiological protection policy. Applications in developing countries. IPEN a case of study

    Energy Technology Data Exchange (ETDEWEB)

    Gordon, A.M.P.L.; Sordi, G.M.A. A. [Instituto de Pesquisas Energeticas e Nucleares - IPEN, Sao Paulo (Brazil)

    2006-07-01

    This paper aims to show the radiological protection development in Brazil from the beginning, when President Joao Cafe Filho signed an agreement with the U.S.A. In this agreement, Brazil joined the 'Atoms for Peace' program established on August 3., 1955. Yet in 1955, Brazil participated as a foundation member in the International Atomic Energy Agency (IAEA). As a result, the Iea - 'Instituto de Energia Atomica'- was created on August 31., 1956 and a research reactor type swimming pool was installed to produce radioisotopes and prepare experts in the field of nuclear activities. This reactor is maintained in operation at the Instituto de Pesquisas Energeticas e Nucleares (IPEN), former Iea. Having the Iea as a case of study, we analyze the radiological protection evolution during the fifty years of its life. We correlate this development with the Brazilian National Nuclear Energy Commission (CNEN) Regulations. CNEN was also created in 1956. The first safety standard in Brazil was delivered in 1973. Therefore, this paper will focus the radiological protection development at national level. Both institutions followed the international radiological protection recommendations, under the difficulties imposed by the historical conditions of a developing country. In order to have an outline of the radiological protection development, we inform that it was started as a section of the Radiological Division at the Iea. At that time, the Iea had four divisions. The radiological protection was performed by four people, being two physicists and two technicians that accomplished all the duties. On that occasion, approximately 30 people operated the Iea. The work staff at IPEN increased, arriving to 1600 people in 1998, including 150 persons in the radiological protection activities. Nowadays, 1200 people, including 100 persons in the health physics duties operate the IPEN. (authors)

  17. A comparative study on radiological and endoscopic examinations of the stomach cancer

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Sook; Lee, Yong Chul; Kim, Han Suk [National Medical Center, Seoul (Korea, Republic of)

    1985-12-15

    An analysis was done for the diagnostic accuracy of radiological and endoscopic examinations in 132 cases of the histologically proved stomach cancer at the national Medical Center from Jan. 1975 to Jan. 1979. The problem in radiological misdiagnosis was especially discussed aimed to improve the further diagnostic accuracy. The following results were obtained: 1. The incidence of the stomach cancer was higher in male than that of female, and was most prevalent in 5th and 6th decades. 2. The misdiagnosis rate of radiological examination of the stomach cancer was 13.5% (18 cases), that of endoscopic examination was 8.3% (11 cases) and that of both examination was 4.6% (6 cases). 3. In most cases of misdiagnosis, the majority were diagnosed as benign gastric ulcer. 4. The causative factors of misdiagnosis in radiological examination were interpretation error in 8 cases and technically poor, unsatisfactory study in 10 cases. 5. In order to decrease the misdiagnosis rate, standardization of radiological examination and careful interpretation are necessary. 6. Complementary examinations of radiology and endoscopy can decrease the misdiagnosis rate.

  18. External Factors That Influence the Practice of Radiology: Proceedings of the International Society for Strategic Studies in Radiology Meeting.

    Science.gov (United States)

    Rubin, Geoffrey D; McNeil, Barbara J; Palkó, András; Thrall, James H; Krestin, Gabriel P; Muellner, Ada; Kressel, Herbert Y

    2017-06-01

    In both the United States and Europe, efforts to reduce soaring health care costs have led to intense scrutiny of both standard and innovative uses of imaging. Given that the United States spends a larger share of its gross domestic product on health care than any other nation and also has the most varied health care financing and delivery systems in the world, it has become an especially fertile environment for developing and testing approaches to controlling health care costs and value. This report focuses on recent reforms that have had a dampening effect on imaging use in the United States and provides a glimpse of obstacles that imaging practices may soon face or are already facing in other countries. On the basis of material presented at the 2015 meeting of the International Society for Strategic Studies in Radiology, this report outlines the effects of reforms aimed at (a) controlling imaging use, (b) controlling payer expense through changes in benefit design, and (c) controlling both costs and quality through "value-based" payment schemes. Reasons are considered for radiology practices on both sides of the Atlantic about why the emphasis needs to shift from providing a large volume of imaging services to increasing the value of imaging as manifested in clinical outcomes, patient satisfaction, and overall system savings. Options for facilitating the shift from volume to value are discussed, from the use of advanced management strategies that improve workflow to the creation of programs for patient engagement, the development of new clinical decision-making support tools, and the validation of clinically relevant imaging biomarkers. Radiologists in collaboration with industry must enhance their efforts to expand the performance of comparative effectiveness research to establish the value of these initiatives, while being mindful of the importance of minimizing conflicts of interest. © RSNA, 2017.

  19. Current algorithms used in reactor safety codes and the impact of future computer development on these algorithms

    International Nuclear Information System (INIS)

    Mahaffy, J.H.; Liles, D.R.; Woodruff, S.B.

    1985-01-01

    Computational methods and solution procedures used in the US Nuclear Regulatory Commission's reactor safety systems codes, Transient Reactor Analysis Code (TRAC) and Reactor Leak and Power Safety Excursion Code (RELAP), are reviewed. Methods used in TRAC-PF1/MOD1, including the stability-enhancing two-step (SETS) technique, which permits fast computations by allowing time steps larger than the material Courant stability limit, are described in detail, and the differences from RELAP5/MOD2 are noted. Developments in computing, including parallel and vector processing, and their applicability to nuclear reactor safety codes are described. These developments, coupled with appropriate numerical methods, make detailed faster-than-real-time reactor safety analysis a realistic near-term possibility

  20. Cumulative radiation dose caused by radiologic studies in critically ill trauma patients.

    Science.gov (United States)

    Kim, Patrick K; Gracias, Vicente H; Maidment, Andrew D A; O'Shea, Michael; Reilly, Patrick M; Schwab, C William

    2004-09-01

    Critically ill trauma patients undergo many radiologic studies, but the cumulative radiation dose is unknown. The purpose of this study was to estimate the cumulative effective dose (CED) of radiation resulting from radiologic studies in critically ill trauma patients. The study group was composed of trauma patients at an urban Level I trauma center with surgical intensive care unit length of stay (LOS) greater than 30 days. The radiology records were reviewed. A typical effective dose per study for each type of plain film radiograph, computed tomographic scan, fluoroscopic study, and nuclear medicine study was used to calculate CED. Forty-six patients met criteria. The mean surgical intensive care unit and hospital LOS were 42.7 +/- 14.0 and 59.5 +/- 28.5 days, respectively. The mean Injury Severity Score was 32.2 +/- 15.0. The mean number of studies per patient was 70.1 +/- 29.0 plain film radiographs, 7.8 +/- 4.1 computed tomographic scans, 2.5 +/- 2.6 fluoroscopic studies, and 0.065 +/- 0.33 nuclear medicine study. The mean CED was 106 +/- 59 mSv per patient (range, 11-289 mSv; median, 104 mSv). Among age, mechanism, Injury Severity Score, and LOS, there was no statistically significant predictor of high CED. The mean CED in the study group was 30 times higher than the average yearly radiation dose from all sources for individuals in the United States. The theoretical additional morbidity attributable to radiologic studies was 0.78%. From a radiobiologic perspective, risk-to-benefit ratios of radiologic studies are favorable, given the importance of medical information obtained. Current practice patterns regarding use of radiologic studies appear to be acceptable.

  1. Radiology Reporting System Data Exchange With the Electronic Health Record System: A Case Study in Iran.

    Science.gov (United States)

    Ahmadi, Maryam; Ghazisaeidi, Marjan; Bashiri, Azadeh

    2015-03-18

    In order to better designing of electronic health record system in Iran, integration of health information systems based on a common language must be done to interpret and exchange this information with this system is required. This study provides a conceptual model of radiology reporting system using unified modeling language. The proposed model can solve the problem of integration this information system with the electronic health record system. By using this model and design its service based, easily connect to electronic health record in Iran and facilitate transfer radiology report data. This is a cross-sectional study that was conducted in 2013. The study population was 22 experts that working at the Imaging Center in Imam Khomeini Hospital in Tehran and the sample was accorded with the community. Research tool was a questionnaire that prepared by the researcher to determine the information requirements. Content validity and test-retest method was used to measure validity and reliability of questioner respectively. Data analyzed with average index, using SPSS. Also Visual Paradigm software was used to design a conceptual model. Based on the requirements assessment of experts and related texts, administrative, demographic and clinical data and radiological examination results and if the anesthesia procedure performed, anesthesia data suggested as minimum data set for radiology report and based it class diagram designed. Also by identifying radiology reporting system process, use case was drawn. According to the application of radiology reports in electronic health record system for diagnosing and managing of clinical problem of the patient, with providing the conceptual Model for radiology reporting system; in order to systematically design it, the problem of data sharing between these systems and electronic health records system would eliminate.

  2. Reactor safety and radiation protection. Draft of the BMU deparmental budget 16 of the 1998 German federal budget

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    The expenditures earmarked for reactor safety and radiation protection in the 1998 budget of the German Federal Ministry for the Environment, Nature Conservation, and Reactor Safety (BMU) total DM 101 million. The expenditures of the German Federal Office for Radiation Protection (BfS) are to amount to a total of DM 579 million. These are the figures included in departmental budget 16 of the 1998 federal budget, which was discussed by the Federal Parliament in September 1997. The atw compilation singles out a number of significant items of the departmental budget. (orig.) [de

  3. A pilot study of radiation exposures arising from interventional radiology procedures

    International Nuclear Information System (INIS)

    Pellet, S.; Giczi, F.; Gaspardy, G.; Temesi, A.; Ballay, L.

    2006-01-01

    Full text of publication follows: In the past 25 years, considerable number of new therapeutic procedures have been worked out and adopted in radiology. These interventional procedures are mainly based on angiographic methods. During these procedures the exposure of patients and staff are usually greater than of conventional radiography and fluoroscopy as a consequence of longer fluoroscopy times and great number of cine-radiography. In the latest years radiation-induced skin injuries occurred in some patients. Injuries to physicians and staff performing interventional procedures have also been observed. In our days interventional procedures are widely used and more sophisticated procedures are worked out and adopted. Consequently, there is a need for the protection of the patient and the staff on a higher level. Radiation protection of intervention radiology deserves a distinguish attention. In Hungary interventional radiology were performed in 36 laboratories in 2003. According to statistical data the gross number of interventional radiological procedures were 19442. The most frequently performed procedures were the P.T.C.A., the coronary and ilio-femoral stent implantation and chemo-embolization. In 2004, the National Research Institute for Radiobiology and Radio-hygiene and the National Patient Dose Evaluation Program started a pilot study of radiation exposures arising from interventional radiology procedures. During the study the patient exposure were measured by D.A.P.-meters. The patient skin dose and the staff dose were performed by thermoluminescent chips. In their presentation the authors present the most important results of the study. (authors)

  4. An observation study of radiation exposure to nurses during interventional radiology procedure

    International Nuclear Information System (INIS)

    Komemushi, Atsushi; Tanigawa, Noboru; Aoki, Atsuko

    2010-01-01

    The purpose of this study was to prospectively measure the level of radiation exposure among nursing staff during interventional radiology procedures. All interventional radiology procedures performed at our institution between April 20 and June 19, 2009 were included in this study. Radiation exposure was measured as the equivalent dose penetrating tissue to a depth of 10 mm using electronic personal dosimeters attached outside (Ha) and inside (Hb) lead aprons. Effective dose (HE) was estimated by calculating from Ha and Hb. In total, data from 68 procedures were included in this study. Four nurses performed 71 nursing cares. The mean Ha was 0.70±1.0 μSv, while the mean Hb was 0.06±0.2 μSv. The mean HE was 0.14±0.3 μSv. The present findings indicate that during interventional radiology procedures, nurses were exposed to very low levels of radiation. (author)

  5. Computational Fluid Dynamics (CFD) in Nuclear Reactor Safety (NRS) - Proceedings of the workshop on Experiments and CFD Code Application to Nuclear Reactor Safety (XCFD4NRS)

    International Nuclear Information System (INIS)

    2008-01-01

    Computational Fluid Dynamics (CFD) is to an increasing extent being adopted in nuclear reactor safety analyses as a tool that enables specific safety relevant phenomena occurring in the reactor coolant system to be better described. The Committee on the Safety of Nuclear Installations (CSNI), which is responsible for the activities of the OECD Nuclear Energy Agency that support advancing the technical base of the safety of nuclear installations, has in recent years conducted an important activity in the CFD area. This activity has been carried out within the scope of the CSNI working group on the analysis and management of accidents (GAMA), and has mainly focused on the formulation of user guidelines and on the assessment and verification of CFD codes. It is in this GAMA framework that a first workshop CFD4NRS was organized and held in Garching, Germany in 2006. Following the CFD4NRS workshop, this XCFD4NRS Workshop was intended to extend the forum created for numerical analysts and experimentalists to exchange information in the field of Nuclear Reactor Safety (NRS) related activities relevant to Computational Fluid Dynamics (CFD) validation, but this time with more emphasis placed on new experimental techniques and two-phase CFD applications. The purpose of the workshop was to provide a forum for numerical analysts and experimentalists to exchange information in the field of NRS-related activities relevant to CFD validation, with the objective of providing input to GAMA CFD experts to create a practical, state-of-the-art, web-based assessment matrix on the use of CFD for NRS applications. The scope of XCFD4NRS includes: - Single-phase and two-phase CFD simulations with an emphasis on validation in areas such as: boiling flows, free-surface flows, direct contact condensation and turbulent mixing. These applications should relate to NRS-relevant issues such as: pressurized thermal shocks, critical heat flux, pool heat exchangers, boron dilution, hydrogen

  6. Study Manual for breast imaging for radiology residents

    International Nuclear Information System (INIS)

    Ramirez Benavides, Rebeca

    2010-01-01

    Breast cancer is a disease that affects women worldwide. This cancer has become a public health problem, currently holding the first incidence and mortality from neoplasms in women of Costa Rica. That's why early detection makes it so important, so you should educate patients about the importance of annual mammograms, regular breast self-examination and consult immediately with the appearance of any abnormality in the breast. Mammography has been the only continuous proven method of screening for breast cancer. However, breast ultrasound is a valuable and effective tool for the evaluation and diagnosis of breast disease. The country lacks a picture book in the breast that fits entirely on the conditions of post-degree program, be practical and use the own methodology of the health system; therefore, the objective of this research is to organize a manual with the review of recent literature on the radiologic evaluation of the breast, with guidance on the methodology and the own resources of the country. This manual aims to provide a guide or basis for the radiologist in training, the important task of obtaining the knowledge, skill and ability to meet the enormous responsibility to participate in early detection of breast cancer. It also may help prevent the development and progression of the dreaded breast cancer in patients during their subsequent professional performance. (author) [es

  7. Radiological and histopathological study of benign tumors of the mandible

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Seon Young; Baek, Seung Yon; Choi, Kyung Hee; Suh, Jeung Soo; Rhee, Chung Sik; Kim, Hee Seup [Ewha Womans University College of Medicine, Seoul (Korea, Republic of)

    1984-06-15

    Benign tumors of the mandible are uncommon lesions. That were classified into odontogenic tumors and nonodontogenic tumors. Author reviewed the radiological evaluation and pathological microscopic finding from 33 benign tumors of the mandible that were confirmed by the biopsy during last 10 years in Dental Clinics, Ewha Womans University Hospital and Seoul National University Dental Hospital. Following results were obtained; 1. Benign tumors of the mandible were classified into odontogenic (66.7%) and non-odontogenic tumors (33.3%). 2. The range of the age distribution was between 6 years and 67 years old. The commonest age group was the second decade (39.4%). 3. There was no difference to sex distribution. 4. The most frequent location was the body of the mandible (42.4%). 5. Radiographic findings were relatively characteristic in odontogenic tumors rather than non-odontogenic tumors. 1) Radiolucent cystic lesions-ameloblastoma, odontogenic myxoma, odontogenic fibtoma, aneurysmal bone cyst and neurofibroma. 2) Radiopaque mass lesions-odontoma, cementoma and osteoma. 3) Mixed patterns-ossifying fibroma, cementifying fibroma, calcifying odontogenic epithelial tumor and hemangioma. It was concluded that the radiographic examination was of value to diagnose the benign tumors of the mandible in symptomless patients.

  8. Radiological and microanalytical studies of fine Melnik wines

    International Nuclear Information System (INIS)

    Tonev, Dimiter; Geleva, Elena; Damianova, Anna; Grigorov, Todor; Goutev, Nikolai; Protohristov, Hristo; Stoyanov, Chavdar; Bashev, Vladimir; Popov, Evgeni; Tringovska, Ivanka; Kostova, Dimitrina

    2016-01-01

    Nuclear methods and chemical fingerprinting can help in the process of determination of the year of production (vintage) and the geographical provenance or designation of origin of high quality wines. For the first time we report results obtained for fine Bulgarian wines from Melnik region, as well as, vineyard soil, vine stems and grape leaves. The gamma-ray activity of the radioisotope 137 Cs has been measured also for the first time in wines from different vintages using low background, high resolution gamma-ray spectrometry. The specific concentrations of 16 elements have been measured in samples from soil, vine stems, grape leaves and fine wines from the type Shiroka Melnishka, which are grown in typical Melnik vineyard by means of Inductively Coupled Plasma-Optical Emission Spectrometry (ICP-OES). The obtained radiological and chemical correlations can be used as initial data base in order to determinate the wine vintage back to 1986 and, eventually, as tool to establish the designation of origin of the Melnik fine wine and the quality of the wine

  9. Evaluation of radiology as a tool to diagnose pulmonic lesions in calves, for example prior to experimental infection studies

    DEFF Research Database (Denmark)

    Tegtmeier, Conny; Arnbjerg, J.

    2000-01-01

    The aim of the study was to evaluate radiology as a technique to visualize pulmonary lesions in young calves, e.g. as a selection criterion for research animals in order to eliminate animals with lung lesions Drier to experimental studies of pneumonia. Five calves with acute clinical signs...... of pneumonia were included in a direct comparative study of radiological and post mortem findings. Also, a number of animals with no signs of pneumonia were included as controls. The study revealed good agreement between the radiological and post mortem findings. Thus, in conclusion, radiology should...

  10. What we now know (and don't know) about reactor safety

    International Nuclear Information System (INIS)

    Budnitz, R.J.

    1984-01-01

    This paper deals with the likelihood and consequences of major reactor accidents. Our understanding has advanced markedly in the past decade, largely because of the use of probabilistic risk assessment. There is now a good understanding of accident sequences, despite some important gaps. The insights achieved have in many ways revolutionized the reactor safety community's view of the relative importance of various safety issues. Understanding of severe accident phenomena is still inadequate, but experiments and development of analytical methods will soon enable us to calculate better the phenomena involved in core degradation, core melting, containment behavior, and the ultimate fate of fission products released from a melted core. Also we are now gaining important insights into analysis of human errors and external initiating events. Thus the next decade will see another quantum jump in our understanding, rivalling the progress of the last decade. (author)

  11. Recommendations of the Reactor Safety Commission (RSK) 1981-1983. Vol. 5

    International Nuclear Information System (INIS)

    1984-02-01

    Since the reorganization of the RSK in 1971 the recommendations are published in the ''Bundesanzeiger'' (BAnz). This makes the work of the RSK transparent for the public. After publication of the recommendations in the Bundesanzeiger, the Office of the RSK publishes them once more as a summary report by order of the Federal Minister of Interior. The reports are divided generally into two parts: Part I contains the recommendations which are given by the RSK; part II contains the official notices concerning the RSK. There is also a subject index. In addition volume 5 contains as part III all papers which were held on the occasion of the 25th anniversary of the Reactor Safety Commission. (orig./HP) [de

  12. Nuclear reactor safety program in US department of energy and future perspectives

    International Nuclear Information System (INIS)

    Song, Y.T.

    1988-01-01

    The US Department of Energy (DOE) establishes policy, issues orders, and assures compliance with requirements. The contractors who design, construct, modify, operate, maintain and decommission DOE reactors, set forth the assessment of the safety of cognizant reactors and implement DOE orders. Teams of experts in the Department, through scheduled and unscheduled review programs, reassess the safety of reactors in every phases of their lives. As new technology develops, the safety programs are reevaluated and policies are modified to accommodate these new technologies. The diagnostic capabilities of the computer using multiple alarms to enhance detection of defects and control of a reactor have been greatly utilized in reactor operating systems. The Application of artificial intelligence technologies for diagnostic and even for the decision making process in the event of reactor accidents would be one of the future trends in reactor safety programs

  13. Energy deposition measurements in fast reactor safety experiments with fission thermocouple detectors

    International Nuclear Information System (INIS)

    Wright, S.A.; Scott, H.L.

    1979-01-01

    The investigation of phenomena occurring in in-pile fast reactor safety experiments requires an accurate measurement of the time dependent energy depositions within the fissile material. At Sandia Laboratories thin-film fission thermocouples are being developed for this purpose. These detectors have high temperature capabilities (400 to 500 0 C), are sodium compatible, and have milli-second time response. A significant advantage of these detectors for use as energy deposition monitors is that they produce an output voltage which is directly dependent on the temperature of a small chip of fissile material within the detectors. However, heat losses within the detector make it necessary to correct the response of the detector to determine the energy deposition. A method of correcting the detector response which uses an inverse convolution procedure has been developed and successfully tested with experimental data obtained in the Sandia Pulse Reactor (SPR-II) and in the Annular Core Research Reactor

  14. Introductory user's manual for the US Nuclear Regulatory Commission Reactor Safety Research Data Bank

    International Nuclear Information System (INIS)

    Scofield, N.R.; Hardy, H.A.; Laats, E.T.

    1984-03-01

    The United States NRC has established the NRC/Division of Accident Evaluation (DAE) Data Bank Program to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. Local direction of the program is provided by EG and G Idaho, Inc., prime contractor for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). The NRC/DAE Data Bank Program provides a central computer storage mechanism and access software for data that is to be used by code development and assessment groups in meeting the code and correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, training, and advisory services to users and the NRC. The NRC/DAE Data Bank and the capabilities of the data access software are described in this document

  15. Introductory user's manual for the US Nuclear Regulatory Commission Reactor Safety Research Data Bank. Revision 3

    International Nuclear Information System (INIS)

    Hardy, H.A.; Laats, E.T.

    1985-03-01

    The United States Nuclear Regulatory Commission (USNRC) has established the NRC/Division of Accident Evaluation (DAE) Data Bank Program to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. Local direction of the program is provided by EG and G Idaho, Inc., prime contractor for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). The NRC/DAE Data Bank Program provides a central computer storage mechanism and access software for data to be used by code development and assessment groups in meeting the code correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, training, and advisory services to users and the USNRC. The NRC/DAE Data Bank and the capabilities of the data access software are described in this document

  16. Insights from the interim reliability evaluation program pertinent to reactor safety issues

    International Nuclear Information System (INIS)

    Carlson, D.D.

    1983-01-01

    The Interim Reliability Evaluation Program (IREP) consisted of concurrent probabilistic analyses of four operating nuclear power plants. This paper presents and integrated view of the results of the analyses drawing insights pertinent to reactor safety. The importance to risk of accident sequences initiated by transients and small loss-of-coolant accidents was confirmed. Support systems were found to contribute significantly to the sets of dominant accident sequences, either due to single failures which could disable one or more mitigating systems or due to their initiating plant transients. Human errors in response to accidents also were important risk contributors. Consideration of operator recovery actions influences accident sequence frequency estimates, the list of accident sequences dominating core melt, and the set of dominant risk contributors. Accidents involving station blackout, reactor coolant pump seal leaks and ruptures, and loss-of-coolant accidents requiring manual initiation of coolant injection were found to be risk significant

  17. List of reports from the BMFT, CEA, EPRI, JSTA and USNRC concerning reactor safety research

    International Nuclear Information System (INIS)

    1981-09-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special Problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA) the Japan Science and Technology Agency (JSTA) the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Saftety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  18. The Oak Ridge Research Reactor: safety analysis: Volume 2, supplement 2

    International Nuclear Information System (INIS)

    Hurt, S.S.

    1986-11-01

    The Oak Ridge Research Reactor Safety Analysis was last updated via ORNL-4169, Vol. 2, Supplement 1, in May of 1978. Since that date, several changes have been effected through the change-memo system described below. While these changes have involved the cooling system, the electrical system, and the reactor instrumentation and controls, they have not, for the most part, presented new or unreviewed safety questions. However, some of the changes have been based on questions or recommendations stemming from safety reviews or from reactor events at other sites. This paper discusses those changes which were judged to be safety related and which include revisions to the syphon-break system and changes related to seismic considerations which were very recently completed. The maximum hypothetical accident postulated in the original safety analysis requires dynamic containment and filtered flow for compliance with 10CFR100 limits at the site boundary

  19. Nuclear reactor safety program in U.S. Department of Energy and future perspectives

    International Nuclear Information System (INIS)

    Song, Y.T.

    1987-01-01

    The U.S. Department of Energy (DOE) establishes policy, issues orders, and assures compliance with requirements. The contractors who design, construct, modify, operate, maintain and decommission DOE reactors, set forth the assessment of the safety of cognizant reactors and impliment DOE orders. Teams of experts in the Depatment, through scheduled and unscheduled review programs, reassess the safety of reactors in every phases of their lives. As new technology develops, the safety programs are reevaluated and policies are modified to accommodate these new technologies. The diagnostic capabilities of the computer using multiple alarms to enhance detection of defects and control of a reactor have been greatly utilized in reactor operating systems. The application of artificial intelligence (AI) technologies for diagnostic and even for the decision making process in the event of reactor accidents would be one of the future trends in reactor safety programs. (author)

  20. Reports of reactor safety research projects sponsored by the Federal Ministry for Research and Technology (BMFT)

    International Nuclear Information System (INIS)

    1984-04-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. the individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by he FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of progress in reactor safety research. The individual reports are classified according to the research program on the safety of LWRS 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig.) [de

  1. Special topics reports for the reference tandem mirror fusion breeder. Volume 2. Reactor safety assessment

    International Nuclear Information System (INIS)

    Maya, I.; Hoot, C.G.; Wong, C.P.C.; Schultz, K.R.; Garner, J.K.; Bradbury, S.J.; Steele, W.G.; Berwald, D.H.

    1984-09-01

    The safety features of the reference fission suppressed fusion breeder reactor are presented. These include redundancy and overcapacity in primary coolant system components to minimize failure probability, an improved valve location logic to provide for failed component isolation, and double-walled coolant piping and steel guard vessel protection to further limit the extent of any leak. In addition to the primary coolant and decay heat removal system, reactor safety systems also include an independent shield cooling system, the module safety/fuel transfer coolant system, an auxiliary first wall cooling system, a psssive dump tank cooling system based on the use of heat pipes, and several lithium fire suppression systems. Safety system specifications are justified based on the results of thermal analysis, event tree construction, consequence calculations, and risk analysis. The result is a reactor design concept with an acceptably low probability of a major radioactivity release. Dose consequences of maximum credible accidents appear to be below 10CFR100 regulatory limits

  2. Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-04-01

    This three-volume report contains 83 papers out of the 108 that were presented at the Nineteenth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 28--30, 1991. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 14 different papers presented by researchers from Canada, Germany, France, Japan, Sweden, Taiwan, and USSR. This document, Volume 3, presents papers on: Structural engineering; Advanced reactor research; Advanced passive reactors; Human factors research; Human factors issues related to advanced passive light water researchers; Thermal Hydraulics; and Earth sciences. The individual papers have been cataloged separately

  3. Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-04-01

    This three-volume report contains 83 papers out of the 108 that were presented at the Nineteenth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 28--30, 1991. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 14 different papers presented by researchers from Canada, Germany, France, Japan, Sweden, Taiwan, and USSR. This document, Volume 2, presents papers on: Severe accident research; Severe accident and policy implementation; and Accident management. The individual papers have been cataloged separately

  4. Environment report 1990 of the Federal Minister for the Environment, Nature Protection and Reactor Safety

    International Nuclear Information System (INIS)

    1990-01-01

    The 'Environment Report 1990' describes the environmental situation in the Federal Republic of Germany; draws a balance of environmental policy measures taken and introduced; gives information on future fields of action in environmental policy. The 'Environment Report 1990' also deals with the 'Environment Expert Opinion 1987', produced by the board of experts on environmental questions. It contains surveys of the following sectors: Protection against hazardous materials air pollution abatement, water management, waste management, nature protection and preservation of the countryside, soil conservation, noise abatement, radiation protection, reactor safety. A separate part of the 'Environment Report 1990' deals with the progress made in 'interdisciplinary fields' (general law on the protection of the environment, instruments of environmental policy, environmental information and environmental research, transfrontier environmental policy). (orig./HP) [de

  5. Thermophysical properties of thorium and uranium systems for use in reactor safety analysis

    International Nuclear Information System (INIS)

    Fink, J.K.; Chasanov, M.G.; Leibowitz, L.

    1977-06-01

    The data compilation is intended to serve as a preliminary set of thermophysical property values for use in reactor safety analyses of the Th-- 233 U reactor concept. The properties covered include mp, bp, enthalpy, heats of vaporization and fusion, heat capacity, thermal conductivity, density, thermal expansion, emissivity, viscosity, etc. The systems covered are Th, Th 0 . 9 U 0 . 1 , U, ThO 2 , Th 0 . 9 U 0 . 1 O 2 , UO 2 , U 0 . 8 Pu 0 . 2 O 2 , ThC, Th 0 . 9 U 0 . 1 C, UC, U 0 . 8 Pu 0 . 2 C, ThC 2 , Th 0 . 9 U 0 . 1 C 2 , and UC 2 . 5 figures, 10 tables, 150 references

  6. Ultrasonic thermometry system for measuring very high temperatures in reactor safety experiments

    International Nuclear Information System (INIS)

    Carlson, G.A.; Sullivan, W.H.; Plein, H.G.; Kerley, T.M.

    1979-06-01

    Ultrasonic thermometry has many potential applications in reactor safety experiments, where extremely high temperatures and lack of visual access may preclude the use of conventional diagnostics. This report details ultrasonic thermometry requirements for one such experiment, the molten fuel pool experiment. Sensors, transducers, and signal processing electronics are described in detail. Axial heat transfer in the sensors is modelled and found acceptably small. Measurement errors, calculations of their effect, and ways to minimize them are given. A rotating sensor concept is discussed which holds promise of alleviating sticking problems at high temperature. Applications of ultrasonic thermometry to three in-core experiments are described. In them, five 10-mm-length sensor elements were used to measure axial temperatures in a UO 2 or UO 2 -steel system fission-heated to about 2860 0 C

  7. Old and new ways in reactor technology. Reactor concepts and reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Schulten, R

    1989-01-01

    Compared to developments of other technical-scale systems, the period between the recognition of the underlying physics of nuclear fission and the development of a functioning nuclear reactor and its further development to the present level of maturity has been relatively short. The whole development is based on the chain reaction and is rendered safe by the possible auto-stabilization of this reaction. Consequently, the safety of nuclear reactors properly designed is based on automatic mechanisms, which prevent spreads of radioactivity even in major accidents. Controversial opinions about nuclear power uses are mostly based on wrong perceptions both of reactor safety and of radioactive waste, unless they are characterized by sheer ideology. The use of nuclear power worldwide has assumed an important, growing role in the combined uses of a variety energy sources in a surprisingly short period of time and will continue to make a safe, economic, and thus responsible contribution in the long run.

  8. Sodium fast reactor gaps analysis of computer codes and models for accident analysis and reactor safety.

    Energy Technology Data Exchange (ETDEWEB)

    Carbajo, Juan (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin, Madison, WI); Schmidt, Rodney Cannon; Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Ludewig, Hans (Brookhaven National Laboratory, Upton, NY); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Serre, Frederic (Centre d' %C3%94etudes nucl%C3%94eaires de Cadarache %3CU%2B2013%3E CEA, France)

    2011-06-01

    This report summarizes the results of an expert-opinion elicitation activity designed to qualitatively assess the status and capabilities of currently available computer codes and models for accident analysis and reactor safety calculations of advanced sodium fast reactors, and identify important gaps. The twelve-member panel consisted of representatives from five U.S. National Laboratories (SNL, ANL, INL, ORNL, and BNL), the University of Wisconsin, the KAERI, the JAEA, and the CEA. The major portion of this elicitation activity occurred during a two-day meeting held on Aug. 10-11, 2010 at Argonne National Laboratory. There were two primary objectives of this work: (1) Identify computer codes currently available for SFR accident analysis and reactor safety calculations; and (2) Assess the status and capability of current US computer codes to adequately model the required accident scenarios and associated phenomena, and identify important gaps. During the review, panel members identified over 60 computer codes that are currently available in the international community to perform different aspects of SFR safety analysis for various event scenarios and accident categories. A brief description of each of these codes together with references (when available) is provided. An adaptation of the Predictive Capability Maturity Model (PCMM) for computational modeling and simulation is described for use in this work. The panel's assessment of the available US codes is presented in the form of nine tables, organized into groups of three for each of three risk categories considered: anticipated operational occurrences (AOOs), design basis accidents (DBA), and beyond design basis accidents (BDBA). A set of summary conclusions are drawn from the results obtained. At the highest level, the panel judged that current US code capabilities are adequate for licensing given reasonable margins, but expressed concern that US code development activities had stagnated and that the

  9. The present status of iodine chemistry research in Canada and its application to reactor safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Weaver, K R [Ontario Hydro Nuclear, Toronto (Canada); Kupferschmid, W C.H.; Wren, J C; Ball, J M [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.

    1996-12-01

    The current need to understand iodine chemistry in a reactor safety context has become more sharply focussed as the level of that understanding has advanced. At the same time, the situations of most concern within containment, from an iodine perspective, are also being redefined in the light of that understanding. The present paper summarises these developments. Over the past five years, considerable advances have occurred in our understanding of iodine chemistry under conditions of interest in reactor accidents. A number of key experiments have yielded important results in the areas of solution chemistry, the role of surfaces, the importance of organics and the effects of impurities. This understanding supplements the already substantial gains made in characterising the key roles of pH and the effects of radiation. All these factors underline the now evident fact that the kinetics of iodine are the controlling factor when radiation is involved, and that a number of reactive species, not present in thermal reactions, effectively control the observed volatility of iodine. In this paper, recent advances are summarised and the present status of our understanding of iodine chemistry is reviewed. Specifically, an attempt is made to identify those areas where our understanding appears to be relatively complete, and to flag the remaining critical areas where our attention is currently focussed. The state of our modelling capability is reviewed, as is the significance or related areas such as the role of mass transfer. Finally, an overview is presented of the significance of this work for reactor safety, and our expectations for its application over the near term future. (author) 2 figs., 12 refs.

  10. The present status of iodine chemistry research in Canada and its application to reactor safety analysis

    International Nuclear Information System (INIS)

    Weaver, K.R.; Kupferschmid, W.C.H.; Wren, J.C.; Ball, J.M.

    1996-01-01

    The current need to understand iodine chemistry in a reactor safety context has become more sharply focussed as the level of that understanding has advanced. At the same time, the situations of most concern within containment, from an iodine perspective, are also being redefined in the light of that understanding. The present paper summarises these developments. Over the past five years, considerable advances have occurred in our understanding of iodine chemistry under conditions of interest in reactor accidents. A number of key experiments have yielded important results in the areas of solution chemistry, the role of surfaces, the importance of organics and the effects of impurities. This understanding supplements the already substantial gains made in characterising the key roles of pH and the effects of radiation. All these factors underline the now evident fact that the kinetics of iodine are the controlling factor when radiation is involved, and that a number of reactive species, not present in thermal reactions, effectively control the observed volatility of iodine. In this paper, recent advances are summarised and the present status of our understanding of iodine chemistry is reviewed. Specifically, an attempt is made to identify those areas where our understanding appears to be relatively complete, and to flag the remaining critical areas where our attention is currently focussed. The state of our modelling capability is reviewed, as is the significance or related areas such as the role of mass transfer. Finally, an overview is presented of the significance of this work for reactor safety, and our expectations for its application over the near term future. (author) 2 figs., 12 refs

  11. The social and cultural construction of radiological risk: a case study

    International Nuclear Information System (INIS)

    Van Nuffelen, D.

    1996-01-01

    Man, society or culture, considered as objects, cannot be measured in the same way as one would measure gravity or a hyperbola. In these conditions, how can one isolate the socio-anthropological aspects from the overall perception of radiological risks, thus the nuclear question? This paper deals with an empirical study derived from some fundamental research conducted in order to explain how different social actors conceive the nuclear question by means of different social construction of reality. It fits into the sociological scheme of knowledge posing a set of methodological and theoretical questions that have as the object the study of the social determinants of knowledge related to the nuclear question. The present survey, carried out in Belgian agricultural workers, makes clear how such determinants interact to form one social construction of the radiological risk. It allows us to presume that the perception of the radiological risks cannot be reduced to some laypeople's measurable psychic (mis)perceptions. (author)

  12. Request for information about radiological risks in the health area. A cross-cultural study

    Energy Technology Data Exchange (ETDEWEB)

    Prades, A. [Ciemat, Madrid (Spain); Martinez-Arias, R. [Universidad Complutense, Madrid (Spain); Arranz, L. [Hospital Ramon y Cajal, Madrid (Spain); Macias, M.T. [CSIC, Madrid (Spain)

    2000-05-01

    This paper will present some of the key findings of a comparative Latin-American study on radiological risk perception in the health area. The project used a survey method to examine the social demands for information about radiological risks with regard to diagnostic and therapeutic applications. The following topics will be analysed: 1) The role of information as a means for feeling safe; 2) who should inform the public on radiological risks; and 3) what type of information the public would like to receive. A questionnaire was distributed to outpatient samples from ten countries: Argentine, Brazil, Colombia, Cuba, Ecuador, Mexico, Panama, Peru, Uruguay, and Spain, thanks to the collaboration of the different National Radioprotection Societies of the above mentionned countries, and of other concerned professionals (in case they didn't had any association at the time). Correspondence analysis and other techniques of optimal scaling will be used. The paper will discuss the main cross-cultural differences with regard to social demand for information about radiological risks. Our findings may have relevant implications for radiological risks communication programs. (author)

  13. Request for information about radiological risks in the health area. A cross-cultural study

    International Nuclear Information System (INIS)

    Prades, A.; Martinez-Arias, R.; Arranz, L.; Macias, M.T.

    2000-01-01

    This paper will present some of the key findings of a comparative Latin-American study on radiological risk perception in the health area. The project used a survey method to examine the social demands for information about radiological risks with regard to diagnostic and therapeutic applications. The following topics will be analysed: 1) The role of information as a means for feeling safe; 2) who should inform the public on radiological risks; and 3) what type of information the public would like to receive. A questionnaire was distributed to outpatient samples from ten countries: Argentine, Brazil, Colombia, Cuba, Ecuador, Mexico, Panama, Peru, Uruguay, and Spain, thanks to the collaboration of the different National Radioprotection Societies of the above mentionned countries, and of other concerned professionals (in case they didn't had any association at the time). Correspondence analysis and other techniques of optimal scaling will be used. The paper will discuss the main cross-cultural differences with regard to social demand for information about radiological risks. Our findings may have relevant implications for radiological risks communication programs. (author)

  14. Comparative study of radiologic-pathologic findings of experimental clonorchiasis in rabbits

    International Nuclear Information System (INIS)

    Ryu, Kyung Nam; Lim, Jae Hoon; Cho, You Jung; Yang, Moon Ho

    1993-01-01

    Radiological investigation in patients with clonorchiasis is very important as this is the only method of evaluating the severity of clonorchiasis. In order to correlate the radiologic and pathologic findings of clonorchiasis, fourteen rabbits infested with Clonorchis sinensis and five control rabbits were examined radiologically by ultrasonography, computed tomography and cholangiography and the results were correlated with pathologic findings. Dilatation of the intrahepatic small bile ducts of the liver was due to obstruction by flukes: oval or elliptical, small filling defects or irregular margin of the bile ducts on cholangiogram or intraluminal echoes on sonogram represented flukes per se; periductal thickening on sonogram and periductal enhancement of bile ducts on CT were due to inflammatory cell infiltration, adenomatous hyperplasia and periductal fibrosis; band like enhancement at the periphery of the liver on CT represented proliferated bile ducts, destruction of liver cells and resultant fibrosis. The study confirmed the pathological bases for the radiological findings of clonorchiasis in liver and bile ducts and will, perhaps, serve as a basis for the future radiologic-pathological correlation of clonorchiasis and in further clinical and experimental researches in the biliary tract diseases

  15. Comparative study of radiologic-pathologic findings of experimental clonorchiasis in rabbits

    Energy Technology Data Exchange (ETDEWEB)

    Ryu, Kyung Nam; Lim, Jae Hoon; Cho, You Jung; Yang, Moon Ho [College of Medicine, Kyung Hee University, Seoul (Korea, Republic of)

    1993-01-15

    Radiological investigation in patients with clonorchiasis is very important as this is the only method of evaluating the severity of clonorchiasis. In order to correlate the radiologic and pathologic findings of clonorchiasis, fourteen rabbits infested with Clonorchis sinensis and five control rabbits were examined radiologically by ultrasonography, computed tomography and cholangiography and the results were correlated with pathologic findings. Dilatation of the intrahepatic small bile ducts of the liver was due to obstruction by flukes: oval or elliptical, small filling defects or irregular margin of the bile ducts on cholangiogram or intraluminal echoes on sonogram represented flukes per se; periductal thickening on sonogram and periductal enhancement of bile ducts on CT were due to inflammatory cell infiltration, adenomatous hyperplasia and periductal fibrosis; band like enhancement at the periphery of the liver on CT represented proliferated bile ducts, destruction of liver cells and resultant fibrosis. The study confirmed the pathological bases for the radiological findings of clonorchiasis in liver and bile ducts and will, perhaps, serve as a basis for the future radiologic-pathological correlation of clonorchiasis and in further clinical and experimental researches in the biliary tract diseases.

  16. Reports on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1977-11-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of BMFT, informs continuously of the status of these investigations within the series 'GRS-F-Fortschrittsberichte' (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the different projects of the search program. The individual reports are prepared by the contractors themselves as a documentation of their progress in work and published by the GRS-FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. Each report describes the work performed, the results and the next steps of the work. The individual reports are attached to the classification system established by the CEC (Commission of the European Communities). The GRS-F-Progress Reports also include a list of the current investigations arranged according to the projects of the BMFT-Research Program Reactor Safety. This compilation, in addition to the LWR-investigations, also contains first contributions on the safety of advanced reactors. (orig.) [de

  17. Reports on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1977-12-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of these investigations within the series 'GRS-F-Fortschrittsberichte' (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the different projects of the search program. The individual reports are prepared by the contractors themselves as a documentation of their progress in work and published by the GRS-FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. Each report describes the work performed, the results and the next steps of the work. The individual reports are attached to the classification system established by the CEC (Commission of the European Communities). The GRS-F-Progress Reports also include a list of the current investigations arranged according to the projects of the BMFT-Research Program Reactor Safety. This compilation, in addition to the LWR-investigations, also contains first contributions on the safety of advanced reactors. (orig.) [de

  18. Working Group 7.1 on environmental transport, US-USSR Joint Coordinating Committee on Civilian Nuclear Reactor Safety

    International Nuclear Information System (INIS)

    Anspaugh, L.R.; Hendrickson, S.M.

    1991-01-01

    This report contains brief summaries of the status of projects of the Environmental Transport Group of the US-USSR Joint Coordinating Committee of Civilian Nuclear Reactor Safety. Projects reported on include: Management and Administration; Atmospheric Transport; Resuspension; External Dose; Terrestrial Food Chains; Aquatic Food Chains; Hydrological Transport; and Intercalibration

  19. Reports on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1977-06-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of these investigations within the series 'GRS-F-Forschrittsberichte' (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the different projects of the search program. The individual reports are prepared by the contractors themselves as a documentation of their progress in work and published by the GRS-FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. Each report describes the work performed, the results and the next steps of the work. The individual reports are attached to the classification system established by the CEC (Commission of the European Communities). The GRS-F-Progress Reports also include a list of the current investigations arranged according to the projects of the BMFT-Research Program Reactor Safety. This compilation, in addition to the LWR-investigations, also contains first contributions on the safety of advanced reactors. (orig.) [de

  20. Announcement of recommendations by the Reactor Safety Commission (RSK), presented at its 184. meeting on March 23, 1983

    International Nuclear Information System (INIS)

    1983-01-01

    The Reactor Safety Commission concluded that from the safety engineering point of view there are no misgivings about granting a licence under atomic energy law for away-from-reactor storage and operation of the transport container store at Ahaus and Gorleben. (orig.) [de

  1. RA reactor safety analysis, Part II - Accident analysis; Analiza sigurnosti rada Reaktora RA I-III, Deo II - Analiza akcidenta

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Radanovic, Lj; Milovanovic, M; Afgan, N; Kulundzic, P [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    This part of the RA reactor safety analysis includes analysis of possible accidents caused by failures of the reactor devices and errors during reactor operation. Two types of accidents are analyzed: accidents resulting from uncontrolled reactivity increase, and accidents caused by interruption of cooling.

  2. Baseline study of radiology services for the purpose of PACS evaluation

    International Nuclear Information System (INIS)

    Mun, S.K.; Benson, H.; Welsh, C.; Elliott, L.P.; Davros, W.

    1988-01-01

    This paper reports initial results of a radiology department baseline study of workload and data flow patterns for image generation, film library activities, report generation reporting activities at the film alternators and report transcription and validation. The authors analyze the film based operations prior to full implementation of the image management and communication system. The baseline study topics are examined

  3. Radiological safety methodology in radioactive tracer applications for hydrodynamics and environmental studies

    International Nuclear Information System (INIS)

    Suarez, R.; Badano, A.; Dellepere, A.; Artucio, G.; Bertolotti, A.

    1995-01-01

    The use of radioactive tracer techniques as control sewage disposal contamination in Montevideo Estuarine and Carrasco beach has been studied for the Nuclear Technology National Direction. Hydrodynamic models simulation has been introduced as work methodology. As well as radiological safety and radioactive material applications in the environmental studies has been evaluated mainly in the conclusions and recommendations in this report. maps

  4. Contribution to the study of integrated system design in digital imaging. Application to digital radiology

    International Nuclear Information System (INIS)

    Boy, M.

    1987-02-01

    In the first part of this work, we describe the hardware and software used to design integrated systems able to acquire, memorize, process and visualize 1024 x 1024 x 8 bits images. In the second part, we present and analyse the first realised prototype system which is a digital radiology one. After a technical and economical digital radiology study, we present the angiographic and tomographic results. In the third part, we indicate possible evolution of this system and we show how the adopted structure and developed hardware allow applications in various fields [fr

  5. Radiology illustrated. Pediatric radiology

    Energy Technology Data Exchange (ETDEWEB)

    Kim, In-One (ed.) [Seoul National Univ. College of Medicine (Korea, Republic of). Dept. of Radiology

    2014-11-01

    Depicts characteristic imaging findings of common and uncommon diseases in the pediatric age group. Will serve as an ideal diagnostic reference in daily practice. Offers an excellent teaching aid, with numerous high-quality illustrations. This case-based atlas presents images depicting the findings typically observed when imaging a variety of common and uncommon diseases in the pediatric age group. The cases are organized according to anatomic region, covering disorders of the brain, spinal cord, head and neck, chest, cardiovascular system, gastrointestinal system, genitourinary system, and musculoskeletal system. Cases are presented in a form resembling teaching files, and the images are accompanied by concise informative text. The goal is to provide a diagnostic reference suitable for use in daily routine by both practicing radiologists and radiology residents or fellows. The atlas will also serve as a teaching aide and a study resource, and will offer pediatricians and surgeons guidance on the clinical applications of pediatric imaging.

  6. Prognosis in contre-coup intracranial haematomas - a clinical and radiological study of 63 patients

    International Nuclear Information System (INIS)

    Jayakumar, P.N.; Sastry Kolluri, V.R.; Basavakumar, D.G.; Subbakrishna, D.K.; Arya, B.Y.T.; Das, B.S.; Narayana Reddy, G.N.

    1991-01-01

    The clinical and radiological profiles of 63 patients with contre-coup haematomas were studied. The overall mortality was 53 %. The mortality in patients with contre-coup haematomas alone was only half of that found in patients with associated coup injury (80 %). (Authors)

  7. Radiology today

    International Nuclear Information System (INIS)

    Donner, M.W.; Heuck, F.H.W.

    1981-01-01

    The book encompasses the proceedings of a postgraduate course held in Salzburg in June 1980. 230 radiologists from 17 countries discussed here the important and practical advances of diagnostic radiology, nuclear medicine and ultrasound as they contribute to gastrointestinal, urologic, skeletal, cardiovascular, pediatric, and neuroradiology. The book contains 55 single contributions of different authors to the following main themes: Cardiovascular, Radiology, pulmonary radiology, gastrointestinal radiology, urinary tract radiology, skeletal radiology, mammography, lymphography, ultrasound, ENT radiology, and neuroradiology. (orig./MG)

  8. Study on generic intervention levels for protecting the public in a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    Suzuki, Fabio Fumio

    2003-01-01

    After a nuclear accident or radiological emergency, several social and economical factors shall be considered for the actions to protect the public and to recover the environment. The application of the radiological protection principles on practices in intervention situations may lead to adoption of protective measures disproportional to the involved risk, compromising the resources available to more effective actions. This causes a negative impact on the population and may conduct to discredit about the protective measures and the lost of confidence on the authorities. In this context, the principles of radiological protection for interventions should be studied and analyzed for being adequately applied in accident situations or radiological emergencies that involves the country. These principles are constantly improved and the concept of generic intervention level plays an important role in the decision-making to protect the public. The costs involved to the protective measures for the public in Brazil were studied and cost benefit analysis techniques were applied to estimate the generic intervention levels for public protection applicable in the country. These results were compared to those values internationally recommended, as well to values obtained in a similar study accomplished for Japan. It was also performed a sensibility analysis of the results regarding a value and a simple analysis of the results considering the costs of the several protective measures. (author)

  9. Postoperative radiology

    International Nuclear Information System (INIS)

    Burhenne, H.J.

    1989-01-01

    This paper reports on the importance of postoperative radiology. Most surgical procedures on the alimentary tract are successful, but postoperative complications remain a common occurrence. The radiologist must be familiar with a large variety of possible surgical complications, because it is this specialty that is most commonly called on to render a definitive diagnosis. The decision for reoperation, for instance, is usually based on results from radiologic imaging techniques. These now include ultrasonography, CT scanning, needle biopsy, and interventional techniques in addition to contrast studies and nuclear medicine investigation

  10. Best Practice Guidelines for the use of CFD in Nuclear Reactor Safety Applications

    International Nuclear Information System (INIS)

    Mahaffy, J.; Chung, B.; Song, C.; Dubois, F.; Graffard, E.; Ducros, F.; Heitsch, M.; Scheuerer, M.; Henriksson, M.; Komen, E.; Moretti, F.; Morii, T.; Muehlbauer, P.; Rohde, U.; Smith, B. L.; Watanabe, T.; Zigh, G.

    2007-01-01

    In May 2002, an 'Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety Problems' was held at Aix-en-Provence, France. One of three recommended actions was the formation of this writing group to report on the need for guidelines for use of CFD in single phase Nuclear Reactor Safety (NRS) applications. CSNI approved this writing group at the end of 2002, and work began in March 2003. A final report was submitted to GAMA in September 2004, summarizing existing Best Practice Guidelines (BPG) for CFD, and recommending creation of a BPG document for Nuclear Reactor Safety (NRS) applications. The present document is intended to provide an internally complete set of guidelines for a range of single phase applications of CFD to NRS problems. However, it is not meant to be comprehensive; it is recognized that for any specific application a higher level of specificity is possible on questions of nodalization, model selection, and validation. This document should provide direct guidance on the key considerations in known single phase applications, and general directions for resolving remaining details. The intent is that it will serve as a template for further application specific (e.g. PTS, induced break) BPG documents that will provide much more detailed information and examples. The document begins with a summary of NRS related CFD analysis in countries represented by the authors. Chapter 3 deals with definition of the problem and its solution approach. This includes isolation of the portion of the NRS problem most in need of CFD, and use of a classic thermal hydraulic (TH) safety code to provide boundary conditions for the CFD based upon less detailed simulation of the balance of plant. Chapter 4 provides guidance in choosing between various options, and also discusses use of a transient calculation with tightly coupled CFD and TH codes. Chapter 5 discusses selection of physical

  11. Management-changing errors in the recall of radiologic results — A pilot study

    International Nuclear Information System (INIS)

    Brus-Ramer, M.; Yerubandi, V.; Newhouse, J.H.

    2012-01-01

    Aim: To evaluate the occurrence of alterations to diagnostic information from radiological studies, which are altered by person-to-person communication and/or faulty recall, and whether they affect patient management Materials and methods: A structured telephone survey was conducted at a large tertiary care medical centre of house staff managing inpatients who had undergone chest, abdominal, or pelvic computed tomography (CT) or magnetic resonance imaging (MRI) and remained in the hospital at least 2 days later. Fifty-six physicians were surveyed regarding 98 patient cases. Each physician was asked how he or she first became aware of the results of the study. Each was then asked to recall the substance of radiological interpretation and to compare it with the radiology report. Each was then asked to assess the level of difference between the interpretations and whether management was affected. Results were correlated with the route by which interviewees became aware of the report, the report length, and whether the managing service was medical or surgical. Results: In nearly 15% (14/98) of cases, differences between the recalled and official results were such that patient management could have been (11.2%) or had already been affected (3.1%). There was no significant correlation between errors and either the route of report communication or the report length. Conclusion: There was a substantial rate of error in the recall and/or transmission of diagnostic radiological information, which was sufficiently severe to affect patient management.

  12. Reactor safety in industrial nuclear power plants. Developments in a political and technical environment as it prevails in the German Federal Republic

    International Nuclear Information System (INIS)

    Laufs, Paul

    2013-01-01

    The present book describes the development of reactor safety in German light-water nuclear power plants from the beginnings with its multifarious links to model solutions seen in other countries, national and international research projects and accidents in conventional and nuclear power plants. It contains detailed, richly illustrated articles on specific safety techniques such as rupture safety of the pressurised envelope, safeguarding of emergency cooling in the event of accidents involving coolant loss, control technology and protection of the surroundings through containment. The results of national and international risk studies are discussed. It is shown how efforts on the part of industry, government and science to enhance safety resources and improve safety culture have been driven by a civic environment in which the use of nuclear energy has become a central issue of political debate. The book is written in readily comprehensible language and offers a wealth of material for further study.

  13. Changes in the ocular surface: initial observations from a pilot study of diagnostic radiology technicians (radiographers)

    International Nuclear Information System (INIS)

    Guerdal, Canan; Aydin, Sevda; Sengoer, Tomris; Onmus, Hale; Oezarar, Muemtaz

    2002-01-01

    The purpose of this study was to evaluate the clinical and cytological changes in the ocular surface of radiology technicians (radiographers) exposed to diagnostic doses of radiation. The Schirmer, Rose Bengal staining and Tear-Break-Up-Time tear function tests were carried out following routine ophthalmic examination in 15 radiology technicians (group I) and 15 controls (group II). Impression cytology was performed by placing 5-mm-thick half-circular cellulose acetate filter paper in the upper and lower quadrants around the limbus. The cytological evaluation was made using the mapping technique. Significantly increased dry eye was detected in group I. In the impression cytology investigation, squamous metaplasia and intraepithelial lymphocytic infiltration was noted in all the group-I cases. A distinct change was observed between the regions showing squamous metaplasia and neigbouring normal epithelial cell structure. Dry eye and ocular surface cytological changes were observed in diagnostic radiology technicians. Routine ophthalmic evaluation of radiology technicians would be beneficial in detecting early cytological changes and dry eye. (orig.)

  14. Clinico-radiological study of fibro-osseous lesions of the jaw

    International Nuclear Information System (INIS)

    Nah, Kyung Sik; Park, Tae Won

    1982-01-01

    Since the fibro-osseous lesion is not a specific diagnostic term, the author studied clinically and radiologically 44 cases which had been diagnosed as fibro-osseous lesion in SNUDH (1972-1981.12). The obtained results were as follows. 1. Clinico-radiologically, the cases of fibro-osseous lesions were divided into two groups. 2. The first group was fibrous dysplasia(21 cases). 3. The second group was tumors of periodontal ligament origin, including ossifying fibroma, cementifying fibroma and cemento-ossifying fibroma (23 cases). 4. In most cases the chief complaint was painless swelling of the jaw and the mean age of the fibrous dysplasia (24.6 yrs) was a little younger than that of the periodontal ligament origin lesions (29.2 yrs). 5. In fibrous dysplasia, maxilla was often involved and showed ground-glass of smoke pattern radiologically. 6. The tumors of periodontal ligament origin occurred more in female, mandible and radiologically showed varying amounts of radiopaque foci in well-circumscribed osteolytic lesion.

  15. Radiology trainer. Musculoskeletal system

    International Nuclear Information System (INIS)

    Staebler, A.; Erlt-Wagner, B.

    2006-01-01

    This book enables students to simulate examinations. The Radiology Trainer series comprises the whole knowledge of radiology in the form of case studies for self-testing. It is based on the best-sorted German-language collection of radiological examinations of all organ regions. Step by step, radiological knowledge is trained in order to make diagnoses more efficient. The book series ensures optimal preparation for the final medical examinations and is also a valuable tool for practical training. (orig.)

  16. Very high temperature measurements: Applications to nuclear reactor safety tests; Mesures des tres hautes temperatures: Applications a des essais de surete des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Parga, Clemente-Jose

    2013-09-27

    This PhD dissertation focuses on the improvement of very high temperature thermometry (1100 deg. C to 2480 deg. C), with special emphasis on the application to the field of nuclear reactor safety and severe accident research. Two main projects were undertaken to achieve this objective: - The development, testing and transposition of high-temperature fixed point (HTFP) metal-carbon eutectic cells, from metrology laboratory precision (±0.001 deg. C) to applied research with a reasonable degradation of uncertainties (±3-5 deg. C). - The corrosion study and metallurgical characterization of Type-C thermocouple (service temp. 2300 deg. C) prospective sheath material was undertaken to extend the survivability of TCs used for molten metallic/oxide corium thermometry (below 2000 deg. C)

  17. Nuclear technology and reactor safety engineering. The situation ten years after the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Birkhofer, A.

    1996-01-01

    Ten years ago, on April 26, 1986 the most serious accident ever in the history of nuclear tgechnology worldwide happened in unit 4 of the nuclear power plant in Chernobyl in the Ukraine, this accident unveiling to the world at large that the Soviet reactor design lines are bearing unthought of safety engineering deficits. The dimensions of this reactor accident on site, and the radioactive fallout spreading far and wide to many countries in Europe, vividly nourished the concern of great parts of the population in the Western world about the safety of nuclear technology, and re-instigated debates about the risks involved and their justification. Now that ten years have elapsed since the accident, it is appropriate to strike a balance and analyse the situation today. The number of nuclear power plants operating worldwide has been growing in the last few years and this trend will continue, primarily due to developments in Asia. The Chernobyl reactor accident has pushed the international dimension of reactor safety to the foreground. Thus the Western world had reason enough to commit itself to enhancing the engineered safety of reactors in East Europe. The article analyses some of the major developments and activities to date and shows future perspectives. (orig.) [de

  18. OECD/CSNI specialist meeting on nuclear aerosols in reactor safety - Summary and Conclusions

    International Nuclear Information System (INIS)

    Allelein, Hans-Josef; Boulaud, Denis; Guentay, Salih; Dehbi, Abdelouahab; Hontanon, Esther; Jokiniemi, Jorma; Jones, Alan V.; Koroll, Grant W.; Tinkler, Charles G.; Schaperow, J.; Royen, Jacques

    1999-01-01

    The Third OECD Specialist Meeting on Nuclear Aerosols in Reactor Safety was organised in Cologne, Germany, from 15-18 June 1998, in collaboration with the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH. It was attended by sixty-five specialists representing thirteen OECD Member countries and the Commission of the European Communities. Thirty-nine papers were presented, in eight sessions. The meeting was concluded by a general discussion devoted to the following topics: - What has been solved up to the level of plant applications and accident management? - Where is more work needed for plant applications? Over the last eight years significant progress has been made in source term modelling and code development. Results have been consolidated in codes which are being used for plant calculations to address safety issues. For example, two countries used their source term codes last year to assess the impact of heating from deposited fission products on the potential for steam generator tube rupture. Also, another source term code was used to assess the need of sprays for fission product removal in the proposed design of a new type of reactor. Over the next few years, experiments and model development will continue, with more emphasis on application to risk-important severe accident scenarios

  19. Reactor safety research against the backdrop of the Energy-Omnibus Law

    International Nuclear Information System (INIS)

    Kuczera, B.

    1995-01-01

    On July 19, 1994, the German Federal Parliament adopted the Coal/Nuclear Power Omnibus Law, in which a new quality of safety of future nuclear power plants has been laid down. The defense-in-depth safety concept underlying the nuclear power plants currently in operation is derived from the principle of safety precautions made against reactor accidents, and encompasses preventive measures of accident mangement and mitigating measures of containing possible consequences. Accident management leads to the requirement that even in the most unlikely accidents with core meltdown the consequences remain limited to the plant. A new quality in reactor safety is represented by the System 80+ advanced pressurized water reactor and by the European Pressurized Water Reactor, EPR. Despite different views about the approaches used to address individaul aspects in the achievement of safety goals, there is agreement on the principle that risk provisions, by achieving more transparency, are to result in better public acceptance of the peaceful uses of nuclear power. (orig.) [de

  20. RB research reactor safety report; Izvestaj o sigurnsti istrazivackog reaktora RB

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Pesic, M; Vranic, S [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1979-04-15

    This new version of the safety report is a revision of the safety report written in 1962 when the RB reactor started operation after reconstruction. The new safety report was needed because reactor systems and components have been improved and the administrative procedures were changed. the most important improvements and changes were concerned with the use of highly enriched fuel (80% enriched), construction of reactor converter outside the reactor vessel, improved control system by two measuring start-up channels, construction of system for heavy water leak detection, new inter phone connection between control room and other reactor rooms. This report includes description of reactor building with installations, rector vessel, reactor core, heavy water system, control system, safety system, dosimetry and alarm systems, experimental channels, neutron converter, reactor operation. Safety aspects contain analyses of accident reasons, method for preventing reactivity insertions, analyses of maximum hypothetical accidents for cores with natural uranium, 2% enriched and 80% enriched fuel elements. Influence of seismic events on the reactor safety and well as coupling between reactor and the converter are parts of this document.

  1. Exploration of High-Dimensional Scalar Function for Nuclear Reactor Safety Analysis and Visualization

    Energy Technology Data Exchange (ETDEWEB)

    Dan Maljovec; Bei Wang; Valerio Pascucci; Peer-Timo Bremer; Michael Pernice; Robert Nourgaliev

    2013-05-01

    The next generation of methodologies for nuclear reactor Probabilistic Risk Assessment (PRA) explicitly accounts for the time element in modeling the probabilistic system evolution and uses numerical simulation tools to account for possible dependencies between failure events. The Monte-Carlo (MC) and the Dynamic Event Tree (DET) approaches belong to this new class of dynamic PRA methodologies. A challenge of dynamic PRA algorithms is the large amount of data they produce which may be difficult to visualize and analyze in order to extract useful information. We present a software tool that is designed to address these goals. We model a large-scale nuclear simulation dataset as a high-dimensional scalar function defined over a discrete sample of the domain. First, we provide structural analysis of such a function at multiple scales and provide insight into the relationship between the input parameters and the output. Second, we enable exploratory analysis for users, where we help the users to differentiate features from noise through multi-scale analysis on an interactive platform, based on domain knowledge and data characterization. Our analysis is performed by exploiting the topological and geometric properties of the domain, building statistical models based on its topological segmentations and providing interactive visual interfaces to facilitate such explorations. We provide a user’s guide to our software tool by highlighting its analysis and visualization capabilities, along with a use case involving dataset from a nuclear reactor safety simulation.

  2. The influence of experience and knowledge on reactor safety in Germany

    International Nuclear Information System (INIS)

    Bointner, Raphael; Schubert, Katharina

    2016-01-01

    After five decades of nuclear power generation in Germany, the government decided to phase out nuclear power plants until 2022 as a consequence of the Fukushima disaster in 2011. Electricity generation is accompanied by human and technical errors, which questions if the nuclear phase-out has an influence on reactor safety. Past errors, available as so-called reportable events of nuclear power plants, can be approximated with experience measured in cumulated electricity generation by applying the Duffey-Saull method with a high coefficient of determination (R"2 = 0.84). Errors are declining with growing experience, which means the reportable events per TWh are declining over time. Today, approximately 0.9 reportable events per generated TWh occur and, given unchanging operational conditions, it is expected to remain at this magnitude in the near future. Moreover, knowledge induced by public Research and Development expenditures may supplement experience in reducing reportable events. Thus, the cumulative fission knowledge stock of Germany was added to the Duffey-Saull method for the first time. By adjusting the knowledge depreciation rate within this extended method, the prediction of reportable events is more accurate. Best results were obtained with 10.8% depreciation rate, which is also in line with the literature. (author)

  3. Qualification of safety-critical software for digital reactor safety system in nuclear power plants

    International Nuclear Information System (INIS)

    Kwon, Kee-Choon; Park, Gee-Yong; Kim, Jang-Yeol; Lee, Jang-Soo

    2013-01-01

    This paper describes the software qualification activities for the safety-critical software of the digital reactor safety system in nuclear power plants. The main activities of the software qualification processes are the preparation of software planning documentations, verification and validation (V and V) of the software requirements specifications (SRS), software design specifications (SDS) and codes, and the testing of the integrated software and integrated system. Moreover, the software safety analysis and software configuration management are involved in the software qualification processes. The V and V procedure for SRS and SDS contains a technical evaluation, licensing suitability evaluation, inspection and traceability analysis, formal verification, software safety analysis, and an evaluation of the software configuration management. The V and V processes for the code are a traceability analysis, source code inspection, test case and test procedure generation. Testing is the major V and V activity of the software integration and system integration phases. The software safety analysis employs a hazard operability method and software fault tree analysis. The software configuration management in each software life cycle is performed by the use of a nuclear software configuration management tool. Through these activities, we can achieve the functionality, performance, reliability, and safety that are the major V and V objectives of the safety-critical software in nuclear power plants. (author)

  4. Proceedings of the seminar on nuclear safety research and the workshop on reactor safety research

    International Nuclear Information System (INIS)

    2001-07-01

    The seminar on the nuclear safety research was held on November 20, 2000 according to the start of new five year safety research plan (FY2001-2005: established by Nuclear Safety Commission) with 79 participants. In the seminar, Commissioner Dr. Kanagawa gave the outline of the next five year safety research plan. Following this presentation, progresses and future scopes of safety researches in the fields of reactor facility, fuel cycle facility, radioactive waste and environmental impact on radiation at Japan Atomic Energy Research Institute (JAERI) were reported. After the seminar, the workshop on reactor safety research was held on November 21-22, 2000 with 141 participants. In the workshop, four sessions titled safety of efficient and economic utilization of nuclear fuel, safety related to long-term utilization of power reactors, research on common safety-related issues and toward further improvement of nuclear safety were organized and, outcomes and future perspectives in these wide research R and D in the related area at other organizations including NUPEC, JAPEIC and Kansai Electric Power Co. was presented in each session. This report compiles outlines of the presentations and used materials in the seminar and the workshop to form the proceedings for the both meetings. (author)

  5. In-pile experiments and test facilities proposed for fast reactor safety

    International Nuclear Information System (INIS)

    Grolmes, M.A.; Avery, R.; Goldman, A.J.; Fauske, H.K.; Marchaterre, J.F.; Rose, D.; Wright, A.E.

    1976-01-01

    The role of in-pile experiments in support of the resolution of fast breeder reactor safety and licensing issues has been re-examined, with emphasis on key safety issues. Experiment needs have been related to the specific characteristics of these safety issues and to realistic requirements for additional test facility capabilities which can be achieved and utilized within the next ten years. It is found that those safety issues related to the energetics of core disruptive accidents have the largest impact on new facility requirements. However, utilization of existing facilities with modifications can provide for a continuing increase in experiment capability and experiment results on a timely bases. Emphasis has been placed upon maximum utilization of existing facilities and minimum requirements for new facilities. This evaluation has concluded that a new Safety Test Facility, STF, along with major modifications to the EBR II facility, improvement in TREAT capabilities, the existing Sodium Loop Safety Facility and corresponding Support Facilities provide the essential elements of the Safety Research Experiment Facilities (SAREF) required for resolution of key issues

  6. Pilot study of the dose in crystalline lens in the interventional radiology practice

    International Nuclear Information System (INIS)

    Castro, A.; Martinez, A.; Fernandez, A.; Molina, D.; Sanchez, L.; Diaz, A.

    2014-08-01

    The interventional radiology involves considerable exposure levels for the occupationally exposed personnel (OEP). The doses can encompass a wide range of values in dependence of the function that develops the personnel and the complexity of each procedure. In organs like the crystalline lens and skin values can be reached that imply the appearance of deterministic effects if is not fulfilled the appropriate measures of radiological protection. This has been demonstrated through multiple studies, among those that the retrospective study of damages in the crystalline lens and dose has been one of those most commented, known as RELID. The objective of that study was to examine the opacity prevalence in the crystalline lens in workers linked to the interventional cardiology and to correlate it with the occupational exposition. The obtained results contributed to that the ICRP recommend a new limit value of equivalent dose for crystalline lens of 20 mSv in one year. With the objective of analyzing the operational implications, in the radiological surveillance programs that they could originate with the new recommendations was developed a pilot study to evaluate the dose in crystalline lens in the OEP linked to the interventional radiology in a Cuban hospital. For this, an anthropomorphic mannequin RANDO-ALDERSON was used on which thermoluminescent dosimeters were placed below and above of the leaded apron and in different positions at level of the crystalline lens: above, below and to the sides of the leaded lenses that the personnel uses routinely. The mannequin was located on the same positions that occupy the main specialist that execute the procedure, as well as of the nurse to assist him. The measurements were made simulating the more representative procedures about complexity, duration time and exposure rate. The used dosimeters were RADOS model for whole body composed of two thermoluminescent detectors Gr-200 (LiF: Mg, Cu, P) to evaluate personal equivalent dose

  7. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1987-02-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Federal Minister for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  8. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1990-05-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  9. List of reports in the field of reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1991-08-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  10. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1990-02-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  11. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1987-05-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Federal Minister for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  12. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1989-05-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  13. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA und USNRC

    International Nuclear Information System (INIS)

    1989-11-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Engergie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  14. List of reports of BMFT, CEA, EPRI, JSTA and USNRC in the field of reactor safety research

    International Nuclear Information System (INIS)

    1985-04-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commisariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electrical Power Research Institute (EPRI) and the United States Nuclear Regulatory Commision, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quaterly. (orig./HP) [de

  15. The concept and contribution of the Federal Government as regards the improvement of reactor safety in Middle and Eastern Europe

    International Nuclear Information System (INIS)

    Gast, K.; Breest, H.C.

    1992-01-01

    An increase in information on reactor safety in the Middle and Eastern European countries makes it clear that extensive assistance measures are urgently needed. This assistance can only be given on the basis of extensive international collaboration. A differenciated analysis and organization of the necessary assistance measures with specific reference to the countries and the facilities in question must be carried out. Within the framework of international assistance programmes, appropriate coordinating commissions in which banks with international experience are involved should be established. On the whole, the imperative increase in the safety of reactors in Middle and Eastern Europe will be a difficult and expensive task which can only be mastered if a joint effort is made within the framework of an international commission which addresses itself to the problem of reactor safety. (orig./HSCH) [de

  16. Radiological environmental study in area to future anthropogenic transformations

    International Nuclear Information System (INIS)

    Grinnan, T.; MIller, C.R.A.

    1998-01-01

    In this work the existent relationship is identified between the data radioecologics and the geological formations to the north area Holguin with the objective to study the possible incidence that this can have in the rate environmental dose in the event of transformations anthropogenic the place

  17. Insider Threat Case Studies at Radiological and Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Pope, Noah Gale [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hobbs, Christopher [Centre for Science and Security Studies, London (United Kingdom)

    2015-04-13

    Seven case studies are presented. The cases include thefts of various materials and sabotage. For each case there is an overview of the incident, a timeline, a profile of the perpetrator, and a discussion of the security system failures which allowed the incident to take place.

  18. Insider Threat Case Studies at Radiological and Nuclear Facilities

    International Nuclear Information System (INIS)

    Pope, Noah Gale; Hobbs, Christopher

    2015-01-01

    Seven case studies are presented. The cases include thefts of various materials and sabotage. For each case there is an overview of the incident, a timeline, a profile of the perpetrator, and a discussion of the security system failures which allowed the incident to take place.

  19. Roadmap on R&D and Human Resource for Light Water Reactors Safety and Knowledge Management: Status in Japan

    International Nuclear Information System (INIS)

    Sekimura, N.

    2016-01-01

    Full text: The roadmap for light water reactor safety technology and human resource has been constructed by the Special Committee on Nuclear Safety Research Roadmap in the Atomic Energy Society of Japan (AESJ). Based upon the lessons learned from the Fukushima Daiichi accident, effective planning of research activities to improve safety can also contribute to enhance human resource and management of accumulated knowledge-base in the future domestic and international community. (author

  20. Radiologic study of 42 cases of Wilson disease

    International Nuclear Information System (INIS)

    Xie, Y.; Zhang, X.; Xu, X.; Zhang, Z.; Feng, Y.

    1985-01-01

    This paper reports 42 cases of bone and joint radiographic changes in hepatolenticular degeneration. The cases were proven clinically by opthalmologic and laboratory study, and their radiographic and joint changes were divided into five groups: no abnormal findings, osteoporosis, osteomalacia (rickets), distinct changes, and miscellaneous. Distinct changes include marginal bone fragments, angulation of carpal bones, squaring of metacarpal heads, and calcification of the joint capsule or tendon insertion. The mechanism causing the bone changes in heptolenticular degeneration is also discussed. (orig.)

  1. Radiologic study of 42 cases of Wilson disease

    Energy Technology Data Exchange (ETDEWEB)

    Xie, Y.; Zhang, X.; Xu, X.; Zhang, Z.; Feng, Y.

    1985-02-01

    This paper reports 42 cases of bone and joint radiographic changes in hepatolenticular degeneration. The cases were proven clinically by opthalmologic and laboratory study, and their radiographic and joint changes were divided into five groups: no abnormal findings, osteoporosis, osteomalacia (rickets), distinct changes, and miscellaneous. Distinct changes include marginal bone fragments, angulation of carpal bones, squaring of metacarpal heads, and calcification of the joint capsule or tendon insertion. The mechanism causing the bone changes in heptolenticular degeneration is also discussed.

  2. Review of SFR In-Vessel Radiological Source Term Studies

    International Nuclear Information System (INIS)

    Suk, Soo Dong; Lee, Yong Bum

    2008-10-01

    An effort has been made in this study to search for and review the literatures in public domain on the studies of the phenomena related to the release of radionuclides and aerosols to the reactor containment of the sodium fast reactor (SFR) plants (i.e., in-vessel source term), made in Japan and Europe including France, Germany and UK over the last few decades. Review work is focused on the experimental programs to investigate the phenomena related to determining the source terms, with a brief review on supporting analytical models and computer programs. In this report, the research programs conducted to investigate the CDA (core disruptive accident) bubble behavior in the sodium pool for determining 'primary' or 'instantaneous' source term are first introduced. The studies performed to determine 'delayed source term' are then described, including the various stages of phenomena and processes: fission product (FP) release from fuel , evaporation release from the surface of the pool, iodine mass transfer from fission gas bubble, FP deposition , and aerosol release from core-concrete interaction. The research programs to investigate the release and transport of FPs and aerosols in the reactor containment (i.e., in-containment source term) are not described in this report

  3. A radiological health study of industrial gamma radiography in Canada

    International Nuclear Information System (INIS)

    1979-05-01

    As an occupational group, industrial radiographers receive radiation doses second only to reactor workers. This report is a result of a study carried out to research the causes for this relatively high dose and determine if and how it can be improved. The data presented herein were obtained from questionnaires and field visits to organizations involved in gamma radiography and from the Canadian National Dose Registry. Some applications of radiography such as pipeline work give rise to higher than average doses. When all safety measures are conscientiously aplied, the doses are reasonalbe. However, ignorance, carelessness and indifference account for much unnecessary exposure to radiation. (Auth)

  4. Reports covering research projects in the field of reactor safety supported by the German Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1976-03-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the safety program 'Reactor Safety' are sponsored by the Bundesminister fuer Forschung und Technologie (BMFT - Secretary of State for Research and Technology). Objective of this program is to continue improving the safety of LWR, in order to minimize the risk for the environment. With grant assistance from the Bundesminister des Innern. (BMI - Secretary of State for Home Affairs) research cont racts in the field of reactor safety are being performed. Results of these projects should contribute to resolve questions arising nuclear licensing procedures. The Forschungsbetreuung (FB - research supervision department) at the Institute for Reactor Safety (IRS), as consultants to BMFT and BMI, provides information about the progress of investigations. Individual reports will be prepared and put into standard forms by the research contractors. Each report gives information on: 1) the work accomplished, 2) the results obtained, 3) the work planned to be continued. Initial reports of research projects describe in addition the purpose of the work. A BMFT-research program on the safety of Fast Breeders (Schneller Brutreaktor - SBR) is presently under discussion. In order to define several problems, investigations included in the present compilation (RS 139, 140, 143, 162) will be previously performed. (orig.) [de

  5. Reports on the research projects in the field of reactor safety sponsored by the Federal Ministry of Science and Technology

    International Nuclear Information System (INIS)

    1975-12-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the safety program 'Reactor Safety' are sponsored by the Bundesminister fuer Forschung und Technologie (BMFT - Secretary of State for Research and Technology). Objective of this program is to continue improving the safety of LWR, in order to minimize the risk for the environment. With grant assistance from the Bundesminister des Innern (BMI - Secretary of State for Home Affairs) research contracts in the field of reactor safety are being performed. Results of these projects should contribute to resolve questions arising nuclear licensing procedures. The Forschungsbetreuung (FB - research supervision department) at the Institute for Reactor Safety (IRS), as consultants to BMFT and BMI, provides information about the progress of investigations. Individual reports will be prepared and put into standard forms by the research contractors. Each report gives information on: 1) the work accomplished, 2) the results obtained, 3) the work planned to be continued. Initial reports of research projects describe in addition the purpose of the work. A BMFT-research program on the safety of Fast Breeders (Schneller Brutreaktor - SBR) is presently under discussion. In order to define several problems, investigations included in the present compilation (RS 139, 140, 143, 162) will be previously performed. (orig.) [de

  6. Report on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1978-12-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS - Projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear power-plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks first projects on the safety of advanced reactors are sponsored by the BMFT. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS - F - Fortschrittsberichte (GRS - F - Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. The individual reports are arranged according to the amended LWR Safety Research Program of the BMFT which will appear in the near future. Another table contents uses the same classification system as applied in the Nuclear Safety Index of the CEC and the OECD. (orig./HP) [de

  7. Reports on the research projects in the field of reactor safety sponsored by the Federal Ministry of Science and Technology

    International Nuclear Information System (INIS)

    1976-12-01

    Investigations on the safety of light water reactors (LWR) being performed in the framework of the safety program 'Reactor Safety' are sponsored by the Bundesminister fuer Forschung und Technologie (BMFT - Secretary of State for Research and Technology). Objective of this program is to continue improving the safety of LWR, in order to minimize the risk for the environment. With grant assistance from the Bundesminister des Innern (BMI - Secretary of State for Home Affairs) research contrcts in the field of reactor safety are being performed. Results of these projects should contribute to resolve questions arising nuclear licensing procedures. The Forschungsbetreuung (FB - research supervision department) at the Institute for Reactor Safety (IRS), as consultants to BMFT and BMI, provides information about the progress of investigations. Individual reports will be prepared and put into standard forms by the research contractors. Each report gives information on: 1) the work accomplished, 2) the results obtained, 3) the work planned to be continued. Initial reports of research projects describe in addition the purpose of the work. A BMFT-research program on the safety of Fast Breeders (Schneller Brutreaktor - SRB) is presently under discussion. In order to define several problems, investigations included in the present compilation (RS 139, 140, 143, 162) will be previously performed. (orig.) [de

  8. A radiological study of the kiwi (Apteryx australis mantelli)

    International Nuclear Information System (INIS)

    Beale, G.

    1985-01-01

    A kiwi chick has been examined at intervals for four and a half years since hatching. The rate of skeletal maturation has been analysed from radiographs (x-ray photographs). Other aspects of the skeleton have been assessed, particularly the cervical spine. The results suggest that the thorax of the ancestors of the kiwi was more cephalically placed than at present and that four vertebrae classified as cervical were then in the thorax and carried ribs. Even in the modern kiwi vestigal ribs can be seen on the fifteenth cervical vertebra. Studies of the gastrointestinal tract have been carried out on other kiwis using a barium solution with videotaping and radiographic procedure. Anatomical and physiological observations, e.g., temperature, pulse and respiration studies have been made. On those birds requiring anaesthesia the effects of anaesthetic agents have been recorded. Some blood analysis has been done and there are observations on air sacs, the diaphragm and eggs. There is an appendix detailing the radiographic procedures used and the total amount of radiation administered, which was not significantly greater than natural gamma radiation over the same period

  9. Findings of the Marshall Islands nationwide radiological study

    International Nuclear Information System (INIS)

    McEwan, A.C.

    1996-01-01

    Full text: The Marshall Islands were affected by nuclear weapon tests carried out over the period 1946-1958, and particularly from the Bravo detonation on 1 March 1954, which deposited heavy fallout on the islands of Rongelap atoll about 100 miles to the east of Bikini. Surveys of residual radioactivity of the northern atolls of the Marshalls group had been carried out by the US Department of Energy, but continuing concerns about health effects of exposure to fallout, particularly thyroid disease, led the Marshall Islands government in 1989 to set up a study of residual radioactivity across the entire country. A study of residual radioactivity on all significant atolls and islands was carried out by ground surveys during 1990-94. The study was supervised by an international panel of 5 non US scientists. The measurements included portable gamma spectrometer measurements at points on a grid pattern, with associated soil samples and periodic soil profile and vegetation samples. From these measurements external exposure rates from deposited fallout have been calculated, and estimates made of the ingestion doses which might be received by resident populations consuming diets made up of differing amounts of locally produced foodstuffs. On the basis of a survey of dietary intake by a Rongelap community a current diet (containing 18% of foods from local sources) and a more traditional diet (75% from local sources) were used for comparison purposes. Measurements were made on 432 islands of the 29 atolls and 5 islands that make up the Marshalls group. Atolls in the latitude range 9-12 degrees north have Cs-137 soil concentrations which are elevated above levels expected from global fallout. Over 90% of the radiation dose from residual fallout is attributable to Cs-137, and arises primarily from dietary intake. Doses to actual or hypothetical residents are about 4 times greater for traditional as compared with current diets. For four atolls there are some islands where

  10. The radiological study of areas gastricae in chronic gastritis

    International Nuclear Information System (INIS)

    Baik, D. I.; Jaun, W. K.; Lee, S. W.; Han, C. Y.

    1980-01-01

    A chronic gastritis is common and clinically significant, but specific findings were rarely described in UGIS. And the authors attempted to clarify the area gastrica of the stomach related to the chronic gastritis. The authors reviewed 'Areae gastricae' micromucosal patterns of stomach, retrospectively with double contrast barium meal study in 16 cases, histologically proven cases of chronic gastritis by endoscopic biopsy from January 1, 1980 to June 30, 1980. Here the commonest site of chronic gastritis is evident in 12 cases in pyloric gland area, and a sixe of area gastrica shows above 2.5mm in longest diameter with combinding morphology, regular to irregular, 3 to 1 and coarse barium accumulations of intervening sulci. The chronic gastritis could be suggested with this better technique of UGIS

  11. The radiological study of areas gastricae in chronic gastritis

    Energy Technology Data Exchange (ETDEWEB)

    Baik, D. I.; Jaun, W. K.; Lee, S. W.; Han, C. Y. [Inje Medical College Paik Hospital (Korea, Republic of)

    1980-12-15

    A chronic gastritis is common and clinically significant, but specific findings were rarely described in UGIS. And the authors attempted to clarify the area gastrica of the stomach related to the chronic gastritis. The authors reviewed 'Areae gastricae' micromucosal patterns of stomach, retrospectively with double contrast barium meal study in 16 cases, histologically proven cases of chronic gastritis by endoscopic biopsy from January 1, 1980 to June 30, 1980. Here the commonest site of chronic gastritis is evident in 12 cases in pyloric gland area, and a sixe of area gastrica shows above 2.5mm in longest diameter with combinding morphology, regular to irregular, 3 to 1 and coarse barium accumulations of intervening sulci. The chronic gastritis could be suggested with this better technique of UGIS.

  12. The appendicolith in acute appendicitis: a radiological study

    International Nuclear Information System (INIS)

    Kang, Hyo Seok; Lee, Myung Hee; Lee, Sun Kyu; Ro, In Woo; Bahk, Yong Whee

    1981-01-01

    The diagnostic importance of finding an appendicolith in the plain x-ray of the abdomen has been well documented. However, most of the papers so far published have stressed x-ray findings of the preoperative abdomen in acute appendicitis. In the present study we have attempted to correlate incidences of appendicoliths in surgical specimen and plain x-ray of the abdomen. The materials were 37 surgical specimens of the appendix removed for acute appendicitis at St. Mary's Hospital, St. Paul's Hospital, Kang Nam Hospital, Holy Family Hospital and Our Lady of Mercy Hospital of Catholic Medical College during the period of 6 months from August 1980. Each surgical specimen was subjected to soft tissue radiography to detect calcified appendicolith. Then the preoperative x-rays of abdomen were retrospectroscopically analysed for the presence of radiographically demonstrable appendicoliths. Our study revealed that in as many as 32% of 37 surgical specimens one or more calcified appendicoliths were demonstrated radiographically whereas only one of these was identified as such in the preoperative x-ray film of the abdomen. Such a great discrepancy between the incidences of appendicoliths in the surgical specimen and preoperative x-ray films of the abdomen are ascribed to (1) relative smallness of appendicoliths (87% of the stones measured less than 1 cm in diameter in radiographs of surgical specimen in our series), (2) overlapping of these small stones on the right iliac bone and (3) underpenetrating of the iliac bone area in x-ray films of the abdomen. For improving detectability of appendicoliths therefore it is recommended that the technique of radiography of plain abdomen should be such that a small appendicolith overlying the iliac bone can be brought out of trabecular shadows

  13. The radiological study of optic canal in Korean

    International Nuclear Information System (INIS)

    Cha, Seong Sook; Juhn, Jae Ryang; Lee, Jang Sik; Chae, Yoo Soon; Bae, Cheol

    1982-01-01

    Various methods of taking of optic foramen view and availabilities have been studied by many foreign investigators, but those in Korea have not been reported yet. The authors have measured and examined the size and shapes of optic foramina of optic foramen views in 111 Korean checked at Inje Medical College Hospital during about 3 years form June 1979 to March 1982. The cases were divided into two groups, A and B, for the convenience of study. Group A consisted of 50 normal Korean 5 to 55 years of age with no visual symptoms and signs. Group B included 69 patients 3 to 75 years of age with visual symptoms and signs. The results were as follows: 1. Mean value of actual diameter of optic foramen measured by Goalwin's method in Groups A: Right: A diameter; 4.21 mm, B diameter; 4.32 mm, Left: A diameter; 4.29 mm, B diameter; 4.30 mm. 2. Absolute symmetry of the great diameters of both optic foramina in Group A; 36%, difference of 0.5 or less; 28%, from 0.5 to 1.0 mm; 18%, from 1.0 to 1.5 mm; 8%, uncomparable cases; 10%. The greatest difference was 1.4 mm. 3. The shapes of optic foramen in Group A: oval shape; 65%, circular; 29%, keyhole or double foramen; 6%. 4. In Group B, the peak age group was second decade (31%), the most common clinical cause of examination of optic foramen view was optic nerve atrophy (30%), and the pathologic findings were only 4 cases (7%). 5. The technique of optic foramen view by modified Pfeiffer's method delineated the outline of optic foramen more clearly than ordinary Rhese's method in our experience

  14. Radiologic study of mandibular third molar of Korean youths

    International Nuclear Information System (INIS)

    Ahn, Hyung Kyu

    1982-01-01

    The author has made a study on the classification of the mandibular 3rd molars of Korean youths through dental radiography by means of Pell and Gregory's classification and on the prevalence of the dental caries of distal surface of the mandibular 2nd molar adjacent to the mandibular 3rd molars turned anteriorly. The results are as follow; 1. It was found that the largest case number was class I (272 cases, 52.9%) in the relation of the tooth to the ramus of the mandible and 2nd molar. 2. The mesio-angular position was the largest number (239 cases, 46.5%) in the relation of the long axis of the impacted mandibular 3rd molar to the long axis of the 2nd molar. 3. The mesio-angular position of class I was the largest number (140 cases, 27.2%) in the relation of the tooth to the ramus of the mandible and 2nd molar and the long axis of the impacted mandibular 3rd moral to the long axis of the 2nd molar. 4. The average angle of the long axis of mandibular 3rd molar in mesioangular position or horizontal position to the occlusal plane was 143 W 5. Mandibular 3rd molar with lesion such as dental cries or pericoronitis was 73 cases (14.2). 6. The caries incidence rate of the distal surface of the 2nd molar was about 3.1%.

  15. [Diagnosis. Radiological study. Ultrasound, computed tomography and magnetic resonance imaging].

    Science.gov (United States)

    Gallo Vallejo, Francisco Javier; Giner Ruiz, Vicente

    2014-01-01

    Because of its low cost, availability in primary care and ease of interpretation, simple X-ray should be the first-line imaging technique used by family physicians for the diagnosis and/or follow-up of patients with osteoarthritis. Nevertheless, this technique should only be used if there are sound indications and if the results will influence decision-making. Despite the increase of indications in patients with rheumatological disease, the role of ultrasound in patients with osteoarthritis continues to be limited. Computed tomography (CT) is of some -although limited- use in osteoarthritis, especially in the study of complex joints (such as the sacroiliac joint and facet joints). Magnetic resonance imaging (MRI) has represented a major advance in the evaluation of joint cartilage and subchondral bone in patients with osteoarthritis but, because of its high cost and diagnostic-prognostic yield, this technique should only be used in highly selected patients. The indications for ultrasound, CT and MRI in patients with osteoarthritis continue to be limited in primary care and often coincide with situations in which the patient may require hospital referral. Patient safety should be bourne in mind. Patients should be protected from excessive ionizing radiation due to unnecessary repeat X-rays or inadequate views or to requests for tests such as CT, when not indicated. Copyright © 2014 Elsevier España, S.L. All rights reserved.

  16. High Explosive Radiological Dispersion Device: Time and Distance Multiscale Study

    International Nuclear Information System (INIS)

    Sharon, A.; Sattinger, I.; Halevy, D.; Banaim, P.; Yaar, I.; Krantz, L.

    2014-01-01

    A wide range of explosion tests imitates different explosive RDD scenarios were conducted and aimed at increasing the preparedness for possible terrorism events, where radioactive (RA) materials disperse via an explosive charge. About 20 atmospheric dispersion tests were conducted using6-8 Ci of 99mTc which were coupled to TNT charges within the range of 0.2525 kg. Tests performed above different typical urban ground surfaces (in order to study the surface effect on the activity ground deposition pattern due to different in particles size distribution). We have used an efficient aerosolizing devices, means that most of the RA particles were initially created within the size of fine aerosols, mostly respirable. Ground activity measurements were performed both, around the dispersion point and up to few hundred meters downwind. Micrometeorology parameters (wind intensity and direction, potential temperature, relative humidity, solar radiation and atmospheric stability) were collected allowing comparisons topredictions of existing atmospheric dispersion models’1. Based on the experimental results, new model parameterizations were performed. Improvements in the models’ predictions were achieved and a set of thumb rules for first responders was formulated. This paper describes the project objectives, some of the experimental setups and results obtained. Post detonation nuclear forensic considerations can be made based upon results achieved

  17. Brachyphalangism and brachymetapodia of the hand. A radiological study

    Energy Technology Data Exchange (ETDEWEB)

    Pryde, A W; Kitabatake, Takashi

    1960-10-01

    Left hand roentgenograms were studied of Japanese children of Hiroshima divided into three groups; Group I was 1302 male and 1237 female normal, healthy controls; Group II was 219 children exposed to the atomic bomb on August 6, 1945 while still intra-utero; Group III was 174 non-exposed control children who were intra-utero on August 6, 1945. Brachymesophalangism of the left little finger was found in the control children in 14.13 percent of males and 21.26 percent of females when epiphyseal irregularity as well as actual shortening is considered as a criterion. Incidence of brachymesophalangism of the left little finger was not significantly different for children exposed to the atomic bomb while intra-utero. Bone age of children with brachymesophalangism and those exposed to the atomic bomb while intra-utero showed no difference from the normal. Brachytelephalangism of the thumb occurs in 2.1 percent of normal boys and in 2.9 percent of normal girls. A possible relation between brachymesophalangism of the little finger and brachytelephalangism of the thumb occurring in the same child is suggested by an association significant at the 5 percent level. Brachymetapodia occurred in 0.2 percent of normal boys and 0.6 percent in girls and was seen most often in the fifth metacarpal. 21 references, 6 tables.

  18. Morphological changes of the epiglottis with aging: A radiological study

    International Nuclear Information System (INIS)

    Jin, Bong Joon; Sim, Joong Seop; Yoon, Sei Chul; Ahn, Kwan Shik; Bahk, Yong Whee

    1983-01-01

    In man the epiglottis is a thin lamella of a yellow elastic cartilage. The upper part is free and is known as leaf and lower part participates in the formation of the anterior wall of the vestibule of the larynx. The ipithelial covering extends forward onto the base of the tongue over the medial glossoepiglottic folds. The sides of epiglottis are connected with the cartilages of Wrisberg and arytenoid cartilage by the aryepiglottic fold. In view of these anatomical complexities, the function and physiology of the epiglottis have been debated since Magendi (1815), who proposed the theory that the epiglottis acts as a flap valve to prevent food entering the windpipe, and who found that he could remove the free part of the epiglottis in dog without spoilling the dog. Following the introduction of laryngoscopy (Gracia, 1815; Liston, 1840; Czermark; 1861) and modern cineradiographic equipment in 1950's, the anatomy and physiology of epiglottis has become much clearer age as it is seen on the lateral x-ray of the neck. In the present study we have made an attempt to systematically analyze aging changes of the epiglottis in the lateral x-ray of the neck in 245 healthy adults. The age ranged from 16 to 65 years old. Based on our observation the epiglottis was classified into type A, B and C according to their curvatures. Thus, type A represented those with posterior curvature, type B those with straight epiglottis and type C anterior curvature. Type C was subdivided into I, II and III according to the degree of curvature. Thus, type C-I, C-II and C-III represented mild, moderate and marked anterior curvature, respectively. Type A epiglottis was found in the second, third and fourth decades and type C-III in the older age group. Type A was least common and type C most prevalent. It seems that the epiglottis inclines anteriorly with backward curvature with age (p<0.0001)

  19. Comparative Study on Radiological Impact Due To Direct Exposure to a Radiological Dispersal Device Using A Sealed Radiation Source

    International Nuclear Information System (INIS)

    Margeanu, C.A.

    2011-01-01

    Nowadays, one of the most serious terrorist threats implies radiological dispersal devices (RDDs), the so-called dirty bombs, that combine a conventional explosive surrounded by an inflammatory material (like thermit) with radioactive material. The paper objective is to evaluate the radiological impact due to direct exposure to a RDD using a sealed radiation source (used for medical and industrial applications) as radioactive material. The simulations were performed for 60Co, 137Cs and 192Ir radiation sources. In order to model the contamination potential level and radiation exposure due to radioactive material spreading from RDD, Lawrence Livermore National Laboratory's HOTSPOT 2.07 computer code was used. The worst case scenario has been considered, calculations being performed for two radioactive material dispersion models, namely General radioactive Plume and General Explosion. Following parameters evolution with distance from the radiation source was investigated: total effective dose equivalent, time-integrated air concentration, ground surface deposition and ground shine dose rates. Comparisons between considered radiation sources and radioactive material dispersion models have been performed. The most drastic effects on population and the environment characterize 60Co sealed radiation source use in RDD.

  20. The NKS-B Programme for Nordic cooperation on nuclear and radiological emergency preparedness, including measurement strategies, radioecology and waste management

    DEFF Research Database (Denmark)

    Andersson, Kasper Grann; Leino, Kaisu; Magnússon, Sigurður M.

    2014-01-01

    The NKS platform for Nordic cooperation and competence maintenance in nuclear and radiological safety comprises two parallel programmes: the NKS-R programme on nuclear reactor safety and the NKS-B programme on emergency preparedness. This paper introduces the NKS-B programme and its current...