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Sample records for r6 leak-before-break procedure

  1. Practical applications of the R6 leak-before-break procedure

    International Nuclear Information System (INIS)

    Bouchard, P.J.

    1997-01-01

    A forthcoming revision to the R6 Leak-before-Break Assessment Procedure is briefly described. Practical application of the LbB concepts to safety-critical nuclear plant is illustrated by examples covering both low temperature and high temperature (>450 degrees C) operating regimes. The examples highlight a number of issues which can make the development of a satisfactory LbB case problematic: for example, coping with highly loaded components, methodology assumptions and the definition of margins, the effect of crack closure owing to weld residual stresses, complex thermal stress fields or primary bending fields, the treatment of locally high stresses at crack intersections with free surfaces, the choice of local limit load solution when predicting ligament breakthrough, and the scope of calculations required to support even a simplified LbB case for high temperature steam pipe-work systems

  2. Practical applications of the R6 leak-before-break procedure

    Energy Technology Data Exchange (ETDEWEB)

    Bouchard, P.J.

    1997-04-01

    A forthcoming revision to the R6 Leak-before-Break Assessment Procedure is briefly described. Practical application of the LbB concepts to safety-critical nuclear plant is illustrated by examples covering both low temperature and high temperature (>450{degrees}C) operating regimes. The examples highlight a number of issues which can make the development of a satisfactory LbB case problematic: for example, coping with highly loaded components, methodology assumptions and the definition of margins, the effect of crack closure owing to weld residual stresses, complex thermal stress fields or primary bending fields, the treatment of locally high stresses at crack intersections with free surfaces, the choice of local limit load solution when predicting ligament breakthrough, and the scope of calculations required to support even a simplified LbB case for high temperature steam pipe-work systems.

  3. Development of a leak-before break procedure for pressurised components

    International Nuclear Information System (INIS)

    Langston, D.B.

    1989-05-01

    For pressurised components there is an increasing interest in the use of leak-before-break arguments to show that defects will behave in a ''failsafe'' manner by growing in such a way as to cause a detectable leak before a disruptive failure of the pressure boundary can occur. The CEGB operates a wide variety of plant and has recognised the need for a flexible leak-before-break procedure which can be applied in a variety of different situations including part-through defects. This paper describes the development of such a procedure and discusses some of the key aspects of the leak-before-break procedure. (author)

  4. A simplified leak-before-break evaluation procedure for austenitic and ferritic steel piping

    Energy Technology Data Exchange (ETDEWEB)

    Gamble, R.M.; Zahoor, A.; Ghassemi, B. [NOVETECH Corp., Rockville, MD (United States)

    1994-10-01

    A simplified procedure has been defined for computing the allowable circumferential throughwall crack length as a function of applied loads in piping. This procedure has been defined to enable leak-before-break (LBB) evaluations to be performed without complex and time consuming analyses. The development of the LBB evaluation procedure is similar to that now used in Section 11 of the ASME Code for evaluation of part-throughwall flaws found in piping. The LBB evaluation procedure was bench marked using experimental data obtained from pipes having circumferential throughwall flaws. Comparisons of the experimental and predicted load carrying capacities indicate that the method has a conservative bias, such that for at least 97% of the experiments the experimental load is equal to or greater than 90% of the predicted load. The procedures described in this report are applicable to pipe and pipe fittings with: (1) wrought austenitic steel (Ni-Cr-Fe alloy) having a specified minimum yield strength less than 45 ksi, and gas metal-arc, submerged arc and shielded metal-arc austenitic welds, and (2) seamless or welded wrought carbon steel having a minimum yield strength not greater than 40 ksi, and associated weld materials. The procedures can be used for cast austenitic steel when adequate information is available to place the cast material toughness into one of the categories identified later in this report for austenitic wrought and weld materials.

  5. Margins in high temperature leak-before-break assessments

    International Nuclear Information System (INIS)

    Budden, P.J.; Hooton, D.G.

    1997-01-01

    Developments in the defect assessment procedure R6 to include high-temperature mechanisms in Leak-before-Break arguments are described. In particular, the effect of creep on the time available to detect a leak and on the crack opening area, and hence leak rate, is discussed. The competing influence of these two effects is emphasized by an example. The application to Leak-before-Break of the time-dependent failure assessment diagram approach for high temperature defect assessment is then outlined. The approach is shown to be of use in assessing the erosion of margins by creep

  6. Margins in high temperature leak-before-break assessments

    Energy Technology Data Exchange (ETDEWEB)

    Budden, P.J.; Hooton, D.G.

    1997-04-01

    Developments in the defect assessment procedure R6 to include high-temperature mechanisms in Leak-before-Break arguments are described. In particular, the effect of creep on the time available to detect a leak and on the crack opening area, and hence leak rate, is discussed. The competing influence of these two effects is emphasized by an example. The application to Leak-before-Break of the time-dependent failure assessment diagram approach for high temperature defect assessment is then outlined. The approach is shown to be of use in assessing the erosion of margins by creep.

  7. Leak before break experience in CANDU reactors

    International Nuclear Information System (INIS)

    Price, E.G.; Moan, G.D.; Coleman, C.E.

    1988-04-01

    The paper describes how the requirements for Leak-Before-Break are met in CANDU reactors. The requirements are based on operational and laboratory experience. After the onset of leakage in a fuel channel from a delayed hydride crack, time is available to the operator to take action before the crack grows to an unstable length. The time available is calculated using different models which use crack growth data from small specimen tests. When the results from crack growth behaviour experiments, carried out on components removed from reactor are used in the model, the time available for operator response is about 100 hours

  8. Applicability of the leak before break concept

    International Nuclear Information System (INIS)

    1993-06-01

    Within the framework of the IAEA Extrabudgetary Programme on the Safety of WWER-440 Model 230 NPPs, a list of safety issues requiring broad studies of general interest have been agreed upon by an Advisory Group which met in Vienna in September 1990. The information on the status of the issues, and on amount of work already completed and under way in various countries, needs to be compiled. Moreover, an evaluation of what further work is required to resolve each of the issues is also necessary. In view of this, the IAEA has started the preparation of a series of status reports on the various issues. This report on the generic safety issue ''Applicability of the Leak Before Break Concept'' presents a comprehensive survey of technical information available in the field and identifies those which require further investigation. 50 refs, 15 figs, 2 tabs

  9. Leak before break piping evaluation diagram

    International Nuclear Information System (INIS)

    Fabi, R.J.; Peck, D.A.

    1994-01-01

    Traditionally Leak Before Break (LBB) has been applied to the evaluation of piping in existing nuclear plants. This paper presents a simple method for evaluating piping systems for LBB during the design process. This method produces a piping evaluation diagram (PED) which defines the LBB requirements to the piping designer for use during the design process. Several sets of LBB analyses are performed for each different pipe size and material considered in the LBB application. The results of this method are independent of the actual pipe routing. Two complete LBB evaluations are performed to determine the maximum allowable stability load, one evaluation for a low normal operating load, and the other evaluation for a high normal operating load. These normal operating loads span the typical loads for the particular system being evaluated. In developing the allowable loads, the appropriate LBB margins are included in the PED preparation. The resulting LBB solutions are plotted as a set of allowable curves for the maximum design basis load, such is the seismic load versus the normal operating load. Since the required margins are already accounted for in the LBB PED, the piping designer can use the diagram directly with the results of the piping analysis and determine immediately if the current piping arrangement passes LBB. Since the LBB PED is independent of pipe routing, changes to the piping system can be evaluated using the existing PED. For a particular application, all that remains is to confirm that the actual materials and pipe sizes assumed in creating the particular design are built into the plant

  10. Leak-before-break experience in CANDU reactors

    International Nuclear Information System (INIS)

    Price, E.G.; Moan, G.D.; Coleman, C.E.

    1988-01-01

    In the Canada deuterium uranium (CANDU) reactor, each of the ∼ 400 hot pressure tubes containing the fuel bundles and the pressurized heat transport water is surrounded and insulated from the cold moderator by a calandria tube. The pressure tubes are made from cold-worked Zr-2.5 Nb with a minimum wall thickness of 4.19 mm, and the calandria tubes are made from annealed Zircaloy-2 with a minimum wall thickness of 1.37 mm. The annulus between these two tubes contains an inert gas. Leak-before-break has developed into an operational tool in CANDU reactors to prevent unstable failure of pressure tubes. A procedure for leak detection and reactor response has been developed from the use of the annulus gas, whose dew point is measured to ascertain if leaks have crept into the annulus. The characteristics of the crack are used to establish the response time for leak detection. The reactor is required to be shut down before the length of the slowly growing crack has reached the critical stage. This critical crack length, determined using slit burst tests on tubes, is the crack length at which the crack growth becomes unstable. The most likely crack growth mechanism is delayed hydride cracking. This mechanism requires three conditions to occur simultaneously: the material must be sensitive to delayed hydride cracking; zirconium hydrides must be present in the material; and the tensile stress must be sufficiently great

  11. Aspects of leak before break quantification in pressurized pipes

    International Nuclear Information System (INIS)

    Hellen, R.A.J.; Darlaston, B.J.L.; Connors, D.C.

    1980-01-01

    In fitness for purpose studies of pressurized structures containing defects, the concept of leak before break is often invoked. As the assumptions used in the concept are sometimes very pessimistic it is desirable to be able to quantify them more precisely. Two aspects are currently receiving attention; these are the way in which a crack profile develops during fatigue and what happens when the remaining ligament below the crack fails. These aspects are being evaluated experimentally and theoretically. Data are presented from tests on pipes subjected to cyclic pressure and subsequently failed. An analytical approach is proposed on the question of ligament failure, this being based on the development of some recent work on flat plates. The overall question of leak before break is considered. As the understanding and confidence increases, it is possible to reduce the range of interest and focus on specific aspects of the problem. This paper examines these aspects. (author)

  12. The leak before break criteria, requirements and implications

    International Nuclear Information System (INIS)

    Martinez M, E.

    1992-05-01

    Inside this work a general balance is made on the Leak before break approach (LBB), like they are the history and licensing, those limitations, the acceptance criteria of the LBB, the current state of the regulatory development and the current state of it application in countries like E.U.A, Germany, Canada, Italy and France. Everything it with the purpose of evaluating the opportunities that offers the LBB criteria for it possible application in Mexico. (Author)

  13. Probabilistic fracture mechanics analysis for leak-before-break evaluation of light water reactor's piping

    International Nuclear Information System (INIS)

    Yoshimura, Shinobu; Yagawa, Genki; Akiba, Hiroshi; Fujioka, Terutaka.

    1997-01-01

    This paper describes Probabilistic Fracture Mechanics (PFM) analyses for quantitative evaluation of the likelihood of Leak-Before-Break (LBB) of Light Water Reactor's (LWR's) piping. The PFM analyses in general assume probabilistic distributions of initial crack size, applied stress cycles, crack growth laws, fracture criteria, leakage detection capability, defect inspection capability and so on. Referring to the deterministic procedure for LBB evaluation, most appropriate PFM models and data for LBB evaluation are discussed. Here the LBB index is newly proposed in order to quantitatively evaluate the likelihood of LBB. Through intensive sensitivity analyses, it is clarified that the LBB is more likely to occur for larger diameter pipe; the performance of leakage detection significantly affects the LBB likelihood; the LBB likelihood increases with plant's aging even conservatively assuming leak detection capability; the R6 method (Category 1, Option 1) for fracture criterion gives very conservative results; and In-Service Inspection (ISI) reduces the increase rate of failure probability than the failure probability itself. (author)

  14. Leak before break application in French PWR plants under operation

    Energy Technology Data Exchange (ETDEWEB)

    Faidy, C. [EDF SEPTEN, Villeurbanne (France)

    1997-04-01

    Practical applications of the leak-before break concept are presently limited in French Pressurized Water Reactors (PWR) compared to Fast Breeder Reactors. Neithertheless, different fracture mechanic demonstrations have been done on different primary, auxiliary and secondary PWR piping systems based on similar requirements that the American NUREG 1061 specifications. The consequences of the success in different demonstrations are still in discussion to be included in the global safety assessment of the plants, such as the consequences on in-service inspections, leak detection systems, support optimization,.... A large research and development program, realized in different co-operative agreements, completes the general approach.

  15. Leak-before-break behaviour of nuclear piping systems

    International Nuclear Information System (INIS)

    Bartholome, G.; Wellein, R.

    1992-01-01

    The general concept for break preclusion of nuclear piping systems in the FRG consists of two main prerequisites: Basic safety; independent redundancies. The leak-before-break behaviour is open of these redundancies and will be verified by fracture mechanics. The following items have to be evaluated: The growth of detected and postulated defects must be negligible in one life time of the plant; the growth behaviour beyond design (i.e. multiple load collectives are taken into account) leads to a stable leak; This leakage of the piping must be detected by an adequate leak detection system long before the critical defect size is reached. The fracture mechanics calculations concerning growth and instability of the relevant defects and corresponding leakage areas are described in more detail. The leak-before-break behaviour is shown for two examples of nuclear piping systems in pressurized water reactors: main coolant line of SIEMENS-PWR 1300 MW (ferritic material, diameter 800 mm); surge line of Russian WWER 440 (austenitic material, diameter 250 mm). The main results are given taking into account the relevant leak detection possibilities. (author). 9 refs, 9 figs

  16. TACIS 91: Application of leak-before-break concept in VVER 440-230

    Energy Technology Data Exchange (ETDEWEB)

    Bartholome, G.; Faidy, C.; Franco, C. [and others

    1997-04-01

    The applicability of the leak-before-break (LBB) concept for primary piping in the first generation of WWER type plants in Russia is investigated. The procedures for LBB behavior used in France and Germany are applied, and the evaluation is discussed within the framework of the European Technical Assistance for the Community of Independent States (TACIS) project. Emphasis is placed on experimental validation of national and international engineering practice for evaluating and optimizing existing installations. Design criteria of WWER plants are compared to western standard design.

  17. CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings

    Energy Technology Data Exchange (ETDEWEB)

    1984-08-01

    On September 1 and 2, 1983, the CSNI subcommittee on primary system integrity held a special meeting in Monterey, California, on the subject of leak-before-break in nuclear reactor piping systems. The purpose of the meeting was to provide an international forum for the exchange of ideas, positions, and research results; to identify areas requiring additional research and development; and to determine the general attitude toward acceptance of the leak-before-break concept. The importance of the leak-before-break issue was evidenced by excellent attendance at the meeting and through active participation by the meeting attendees. Approximately 125 people representing fifteen different nations attended the meeting. The meeting was divided into four technical sessions addressing the following areas: Application of Piping Fracture Mechanics to Leak-Before Break, Leak Rate and Leak Detection, Leak-Before-Break Studies, Methods and Results, Current and Proposed Positions on Leak-Before-Break.

  18. CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings

    International Nuclear Information System (INIS)

    1984-08-01

    On September 1 and 2, 1983, the CSNI subcommittee on primary system integrity held a special meeting in Monterey, California, on the subject of leak-before-break in nuclear reactor piping systems. The purpose of the meeting was to provide an international forum for the exchange of ideas, positions, and research results; to identify areas requiring additional research and development; and to determine the general attitude toward acceptance of the leak-before-break concept. The importance of the leak-before-break issue was evidenced by excellent attendance at the meeting and through active participation by the meeting attendees. Approximately 125 people representing fifteen different nations attended the meeting. The meeting was divided into four technical sessions addressing the following areas: Application of Piping Fracture Mechanics to Leak-Before Break, Leak Rate and Leak Detection, Leak-Before-Break Studies, Methods and Results, Current and Proposed Positions on Leak-Before-Break

  19. Probabilistic leak-before-break analysis with correlated input parameters

    International Nuclear Information System (INIS)

    Qian Guian; Niffenegger, Markus; Karanki, Durga Rao; Li Shuxin

    2013-01-01

    Highlights: ► The correlation of crack growth has the most significant impact on LBB behavior. ► The correlation impact increases with the correlation coefficients. ► The correlation impact increases with the number of cracks. ► Independent assumption may lead to nonconservative result. - Abstract: The paper presents a probabilistic methodology considering the correlations between the input variables for the analysis of leak-before-break (LBB) behavior of a pressure tube. A computer program based on Monte Carlo (MC) simulation with Nataf transformation has been developed to allow the proposed methodology to calculate both the time from the first leakage to unstable fracture and the time from leakage detection to unstable fracture. The results show that the correlation of the crack growth rates between different cracks has the most significant impact on the LBB behavior of the pressure tube. The impact of the parameters correlation on LBB behavior increases with the crack numbers. If the correlations between different parameters for an individual crack are not considered, the predicted results are nonconservative when the cumulative probability is below 50% and conservative when it is above 50%.

  20. Influence of Crack Morphology on Leak Before Break Margins

    International Nuclear Information System (INIS)

    Weilin Zang

    2007-11-01

    The purpose of the project is to evaluate the deterministic LBB-margins for different pipe systems in a Swedish PWR-plant and using different crack morphology parameters. Results: - The influence of crack morphology on Leak Before Break (LBB) margins is studied. The subject of the report is a number of LBB-submittals to SKI where deterministic LBB-margins are reported. These submittals typically uses a surface roughness of 0.0762 mm (300 microinch) and number of turns equal to zero and an in-house code for the leak rate evaluations. The present report has shown that these conditions give the largest LBB-margins both in terms of the quotient between the critical crack length and the leakage crack size and for the leak rate margin. - Crack morphology parameters have a strong influence on the leak rate evaluations. Using the SQUIRT code and more recent recommendations for crack morphology parameters, it is shown that in many cases the evaluated margins, using 1 gpm as the reference leak rate detection limit, are below the safety factor of 2 on crack size and 10 on leak rate, which is generally required for LBB approval. - The effect of including weld residual stresses on the LBB margins is also investigated. It is shown that for the two examples studied, weld residual stresses were important for the small diameter thin wall pipe whereas it was negligible for the large diameter thick wall pipe which had a self-balanced weld residual stress distribution

  1. Comparison of safety margins for leak-before-break assessment of 500 MWe PHWR straight pipes: using contemporary techniques

    International Nuclear Information System (INIS)

    Rastogi, Rohit; Bhasin, Vivek; Kushwaha, H.S.

    1998-01-01

    The Leak Before Break (LBB) analysis of Primary Heat Transport (PHT) Piping of 500 MWe Indian PHWR is being performed using different well established techniques like R6 method (Nuclear Electric UK) and J-Tearing based methods (USNRC). These methods show that PHT piping has required safety margins and can be qualified for LBB. These analysis also showed that the piping has high fracture toughness and plastic collapse is the dominant mode of failure. To enhance the confidence in the results obtained from the above methods, further studies were done on the PHT piping. Procedures which predicted margins against plastic collapse were used. The analysis procedures used were Modified Limit Load Method, MPA Method (both from Germany), Moments Method (from Italy) and the Z-Factor method given in ASME Boiler and Pressure Vessel Code. The safety margins obtained from these analysis satisfied the LBB requirements. A table was generated which compared the safety margins obtained using all the above mentioned procedures. This report presents the results of this study. (author)

  2. Leak-before-break assessment of RBMK-1500 fuel channel in case of delayed hydride cracking

    International Nuclear Information System (INIS)

    Klimasauskas, A.; Grybenas, A.; Makarevicius, V.; Nedzinskas, L.; Levinskas, R.; Kiselev, V.

    2003-01-01

    One of the factors determining remaining lifetime of Zr-2.5% Nb fuel channel (FC) is the amount of hydrogen dissolved during corrosion process. When the concentration of hydrogen exceeds the terminal solid solubility limit zirconium hydrides are precipitated. As a result form necessary conditions for delayed hydride cracking (DHC). Data from the RBMK-1500 fuel channel tubes (removed from service) shows that hydrogen in some cases distributes unevenly and hydrogen concentration can differ several times between individual FC tubes or separate zones of the same tube and possibly, can reach dangerous levels in the future. Consequently, lacking statistical research data, it is difficult to forecast increase of hydrogen concentration and formation of DHC. So it is important to verify if under the most unfavorable situation leak before break condition will be satisfied in the case of DHC. To estimate possible DHC rates in RBMK 1500 FC pressure tubes experiments were done in the following order: hydriding of the Zr-2.5Nb pressure tube material to the required hydrogen concentration; hydrogen analysis; machining of specimens, fatigue crack formation in the axial direction, DHC testing; average crack length measurement and DHC velocity calculation. During the tests in average DHC values were determined at 283, 250 and 144 degC (with hydrogen concentrations correspondingly 76, 54 and 27 ppm). The fracture resistance dependence from hydrogen concentration was measured at 20 degC. To calculate leak through the postulated flaw, statistical distribution of DHC surface irregularity was determined. Leak before break analysis was carried out according to requirements of RBMK 1500 regulatory documents. J integral and crack opening were calculated using finite element method. Loading of the FC was determined using RELAP5 code. Critical crack length was calculated using R6 and J-integral methods. Coolant flow rate through the postulated crack was estimated using SQUIRT software

  3. Regulatory aspects of the Leak Before Break application

    International Nuclear Information System (INIS)

    Korosec, D.; Vojvodic Tuma, J.

    2000-01-01

    In the present paper the Leak Before Break (LBB) methodology is described on the way, as it was evaluated in Slovenian Nuclear Safety Administration in the process of the nuclear power plant (NPP) Krsko modernization process. In the recent decade, reviewed regulatory position regarding elimination the dynamic effects of the postulated primary coolant pipe ruptures in some countries was issued. The basis for such new approach are research achievements on different areas of science like metallurgy, fracture mechanics, dynamic analysis and testing of materials. By this new regulatory position the utility has the possibility to adopt LBB concept, but has to fulfill at least general prerequisites, described in standard review plan, where the basic principles and objectives of the evaluation process are described. World wide practice shows that more intensive and detailed evaluation is necessary as it is described in the standard review plan. The concerns and requests raising during evaluation of the consequences of the adopted LBB concept have generally some common points comparing regulatory experience of different countries which have already accepted this methodology or are currently under the process of evaluation. But nevertheless every nuclear power plant is unique, comparing specific material properties, dynamic analysis assumptions, safety analyses performed etc. One of the most important areas in the LBB evaluation process is reliable primary piping material evaluation. Several generic material studies were performed and the applicability of these studies for the justification of LBB has to be carefully performed. Elimination of the double ended guillotine break from the safety analysis has very strong impact to the safety analysis results and finally to the structures, systems and components too. Nuclear safety administration has made a lot of effort to make its position on this methodology clear. The expertise of the authorized institutions is in such process

  4. Problems identified in quantifying leak before break in pressure containing structures

    International Nuclear Information System (INIS)

    Darlaston, B.J.L.; Connors, D.C.; Hellen, R.A.J.

    1979-01-01

    The leak before break approach is often applied to pressure containing plant as part of the safety assessment. The assumptions used in this approach are sometimes very pessimistic. It is therefore desirable to be able to quantify the concept more precisely. The two aspects which are of considerable importance are the way the crack profile develops and what happens when the remaining ligament below the crack fails. These two aspects are receiving attention and together with the development of the basic concept of 'leak before break' form the basis of this paper. Some thirty burst tests have been carried out on straight pipes of various dimensions. The results have been analysed using the CEGB Failure Assessment Route for structures containing defects. It was shown that in most cases the leaks and the breaks could be separated by this procedure. However all these tests involved machined rather than fatigue grown defects. A complementary program on pipes has the objective of examining defect growth under cyclic loads. The tests on the 152 mm diameter pipes showed that these defects did not grow in a uniform manner but after a while began to tunnel through the wall locally leading to failure of part of the ligament. This implies that some defects considered to be in the break category would only lead to leaks. As a consequence of these results the experimental programme was redesigned to concentrate on the growth of defects which it was thought would span the boundary of leak and break. For the pipe dimensions and materials used, this represented long defects which would penetrate well into the wall before ligament failure occurred. The analysis and interpretation of this aspect of the programme is part analytical part empirical. (orig.)

  5. A French guideline for defect assessment at elevated temperature and leak before break analysis

    Energy Technology Data Exchange (ETDEWEB)

    Drubay, B.; Chapuliot, St.; Lacire, M.H.; Marie, St. [CEA Saclay, Lab. d' Ingegrite des Structures et Normalisation, LISN, 91 - Gif sur Yvette (France); Deschanels, H. [FRAMATOME/Novatome, 69 - Lyon (France); Cambefort, P. [Electricite de France (EDF/SEPTEN), 69 - Lyon (France)

    2001-07-01

    A large program is performed in France in order to develop, for the design and operating FBR (fast breeder reactor) plants, defect assessment procedures and Leak-Before-Break methods (L.B.B.). The main objective of this A16 guide is to propose analytical solutions at elevated temperature coherent with those proposed at low temperature by the RSE-M. The main items developed in this A16 guide for laboratory specimen, plates, pipes and elbows are the following: evaluation of ductile crack initiation and crack propagation based on the J parameter and material characteristics as J{sub R}-{delta}a curve or J{sub i}/G{sub fr}. Algorithms to evaluate the maximum endurable load under increasing load for through wall cracks or surface cracks are also proposed; determination of fatigue or creep-fatigue crack initiation based on the {sigma} approach calculating stress and strain at a characteristic distance d from the crack tip; evaluation of fatigue crack growth based on da/dN-{delta}K{sub eff} relationship with a {delta}K{sub eff} derived from a simplified estimation of {delta}J for the cyclic load; evaluation of creep-fatigue crack growth adding the fatigue crack growth and the creep crack growth during the hold time derived from a simplified evaluation of C{sup *}; Leak-Before-Break procedure. The fracture mechanic parameters determined in the A16 guide (K{sub 1}, J, C{sup *}) are derived from handbooks and formula in accordance with those proposed in the RSE-M document for in service inspection. Those are: the K{sub I} handbook for a large panel of surface and through-wall defect in plates, pipes and elbows; elastic stress and reference stress formula; analytical Js and Cs{sup *} formulations for mechanical and through thickness thermal load. The main part of the formula and assessment methodologies proposed in the A16 guide are included in a software, called MJSAM, developed under the MS Windows environment in support of the document. This allows a simple application of

  6. A French guideline for defect assessment at elevated temperature and leak before break analysis

    International Nuclear Information System (INIS)

    Drubay, B.; Chapuliot, St.; Lacire, M.H.; Marie, St.; Deschanels, H.; Cambefort, P.

    2001-01-01

    A large program is performed in France in order to develop, for the design and operating FBR (fast breeder reactor) plants, defect assessment procedures and Leak-Before-Break methods (L.B.B.). The main objective of this A16 guide is to propose analytical solutions at elevated temperature coherent with those proposed at low temperature by the RSE-M. The main items developed in this A16 guide for laboratory specimen, plates, pipes and elbows are the following: evaluation of ductile crack initiation and crack propagation based on the J parameter and material characteristics as J R -Δa curve or J i /G fr . Algorithms to evaluate the maximum endurable load under increasing load for through wall cracks or surface cracks are also proposed; determination of fatigue or creep-fatigue crack initiation based on the σ approach calculating stress and strain at a characteristic distance d from the crack tip; evaluation of fatigue crack growth based on da/dN-ΔK eff relationship with a ΔK eff derived from a simplified estimation of ΔJ for the cyclic load; evaluation of creep-fatigue crack growth adding the fatigue crack growth and the creep crack growth during the hold time derived from a simplified evaluation of C * ; Leak-Before-Break procedure. The fracture mechanic parameters determined in the A16 guide (K 1 , J, C * ) are derived from handbooks and formula in accordance with those proposed in the RSE-M document for in service inspection. Those are: the K I handbook for a large panel of surface and through-wall defect in plates, pipes and elbows; elastic stress and reference stress formula; analytical Js and Cs * formulations for mechanical and through thickness thermal load. The main part of the formula and assessment methodologies proposed in the A16 guide are included in a software, called MJSAM, developed under the MS Windows environment in support of the document. This allows a simple application of the analysis proposed in the document. (authors)

  7. Integrated probabilistic assessment for DHC initiation, growth and leak-before-break of PHWR pressure tubes

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Young-Jin [Power Engineering Research Institute, KEPCO Engineering and Construction, 188 Gumi-dong, Bundang-gu, Seongnam-si, Gyeonggi-do 463-870 (Korea, Republic of); Chang, Yoon-Suk, E-mail: yschang@khu.ac.kr [Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do 446-701 (Korea, Republic of)

    2014-08-15

    Highlights: • We develop an integrated approach for probabilistic assessment of PHWR pressure tube. • We examine probabilities of DHC initiation, growth, penetration and LBB failure. • The proposed approach is helpful to calculate rupture probabilities in reactor flaws even in the case of very low rupture probability. - Abstract: A few hundred zirconium alloy pressure tubes in a pressurized heavy water reactor (PHWR) serve as the nuclear fuel channel, as well as the reactor coolant pressure boundary. The pressure tubes are inspected periodically and a fitness-for-service assessment (FFSA) must be conducted if any flaw is detected in the inspection. A Canadian standard provides FFSA procedures of PHWR pressure tubes, which include probabilistic assessment for flaws considering delayed hydride cracking (DHC) and leak-before-break (LBB). In the present study, an integrated approach with detailed stepwise calculation procedures and integration methodology for probabilistic assessment of pressure tube was developed. In the first step of this approach, a probability of the DHC initiation, growth and penetration for single initial flaw is calculated. In the next step, a probability of LBB failure, which means tube rupture, for single through-wall crack (TWC) is calculated. Finally, a rupture probability for all initial flaws in a reactor can be calculated using the penetration probability for single flaw and the LBB failure probability for single TWC, as well as the predicted total number of initial flaw in the reactor.

  8. Integrated probabilistic assessment for DHC initiation, growth and leak-before-break of PHWR pressure tubes

    International Nuclear Information System (INIS)

    Oh, Young-Jin; Chang, Yoon-Suk

    2014-01-01

    Highlights: • We develop an integrated approach for probabilistic assessment of PHWR pressure tube. • We examine probabilities of DHC initiation, growth, penetration and LBB failure. • The proposed approach is helpful to calculate rupture probabilities in reactor flaws even in the case of very low rupture probability. - Abstract: A few hundred zirconium alloy pressure tubes in a pressurized heavy water reactor (PHWR) serve as the nuclear fuel channel, as well as the reactor coolant pressure boundary. The pressure tubes are inspected periodically and a fitness-for-service assessment (FFSA) must be conducted if any flaw is detected in the inspection. A Canadian standard provides FFSA procedures of PHWR pressure tubes, which include probabilistic assessment for flaws considering delayed hydride cracking (DHC) and leak-before-break (LBB). In the present study, an integrated approach with detailed stepwise calculation procedures and integration methodology for probabilistic assessment of pressure tube was developed. In the first step of this approach, a probability of the DHC initiation, growth and penetration for single initial flaw is calculated. In the next step, a probability of LBB failure, which means tube rupture, for single through-wall crack (TWC) is calculated. Finally, a rupture probability for all initial flaws in a reactor can be calculated using the penetration probability for single flaw and the LBB failure probability for single TWC, as well as the predicted total number of initial flaw in the reactor

  9. Estimation of Fracture Parameters for Leak-before-Break Assessment on Elevated Temperature

    International Nuclear Information System (INIS)

    Lee, S. Y.; Kim, N. H.; Koo, G. H.; Kim, D. J.

    2015-01-01

    When the liquid sodium leaks this interaction may cause the fire that is harmful to safety of the reactor. Therefore, it is necessary to prevent against sodium fire in SFRs. Leak-before-Break(LBB) concept, had been devised for this purpose and has following advantage than Double-ended Guillotine Break(DEGB) design. If DEGB is excluded, the number of extinguish facilities and firewalls against the sodium fire can be minimize. LBB concept, has been well established and had many experience in regard of light water reactors(LWRs). But LBB assessment to SFRs is more complicated because SFRs is operated on elevated temperature region. On this region, because creep damage occurs to material and grows defects LBB assessment to SFRs should be considering creep effects. The procedure and method for this purpose are provided RCC-MRx A16 that is France code. To calculate fracture parameters such as K and J are required to some coefficients and equations which have been limited in RCC-MRx A16. Thus, in this study obtained K and J using finite element analysis for the sub-model including the crack. In this study, fracture parameters for LBB assessment were estimated by finite element analysis. This result will be applicable to LBB assessment of PGSFR

  10. Demonstration of leak-before-break in Japan Sodium cooled Fast Reactor (JSFR) pipes

    International Nuclear Information System (INIS)

    Wakai, Takashi; Machida, Hideo; Yoshida, Shinji; Xu, Yang; Tsukimori, Kazuyuki

    2014-01-01

    This paper describes the leak-before-break (LBB) assessment procedure applicable to Japan Sodium cooled Fast Reactor (JSFR) pipes made of modified 9Cr–1Mo steel. For the sodium pipes of JSFR, the continuous leak monitoring will be adopted as an alternative to a volumetric test of the weld joints under conditions that satisfy LBB. Firstly, a LBB assessment flowchart eliminating uncertainty resulted from small scale leakage, such as self plugging phenomenon and influence of crack surface roughness on leak rate, was proposed. Secondly, a rational unstable fracture assessment technique, taking the compliance changing with crack extension into account, was also proposed. Thirdly, a crack opening displacement (COD) assessment technique was developed, because COD assessment method applicable to JSFR pipes – thin wall and small work hardening material – had not been proposed yet. In addition, fracture toughness tests were performed using compact tension (CT) specimens to obtain the fracture toughness, J IC , and the crack growth resistance (J–R) curve at elevated temperature. Finally, by using the flowchart, proposed techniques and collected data, LBB assessment for the primary sodium pipes of JSFR was conducted. As a result, LBB aspect was successfully demonstrated with sufficient margins

  11. Leak-Before-Break: Further developments in regulatory policies and supporting research

    International Nuclear Information System (INIS)

    Wilkowski, G.M.; Chao, K.-S.

    1990-02-01

    The fourth in a series of international Leak-Before-Break (LBB) Seminars supported in part by the US Nuclear Regulatory Commission was held at the National Central Library in Taipei, Taiwan on May 11 and 12, 1989. The seminar updated the international polices and supporting research on LBB. Attendees included representatives from regulatory agencies, electric utilities, nuclear power plant fabricators, research organizations, and academic institutions. Regulatory policy was the subject of presentations by Mr. G. Arlotto (US NRC, USA) Dr. B. Jarman (AECB, Canada), Dr.P. Milella (ENEA-DISP, Italy), Dr. C. Faidy (EDF/Septen, France ), and Dr. K. Takumi (NUPEC, Japan). A paper by Mr. K. Wichman and Mr. A. Lee of the US NRC Office of Nuclear Reactor Regulation is included as background material to these proceedings; it discusses the history and status of LBB applications in US nuclear power plants. In addition, several papers on the supporting research programs described regulatory policy or industry standards for flaw evaluations, e.g., the ASME Section XI code procedures. Supporting research programs were reviewed on the first and second day by several participants from Taiwan, US, Japan, Canada, Italy, and France. Each individual paper has been cataloged separately

  12. Leak-before-break diagrams using simple plastic limit load criteria for pipes with circumferential cracks

    International Nuclear Information System (INIS)

    Goerner, F.; Munz, D.

    1984-01-01

    Simple criteria for local and global instabilities were used to calculate leak-before-break-diagrams for load-controlled deformations. Relations between the tension and bending stresses in the uncracked pipe and the critical crack angle α/sub c/, below which complete fracture cannot occur, were developed for combined loading by internal pressure and external tension and bending. The different assumptions made for local and global instability lead to similar conclusions about the allowable crack length for leak-before-break behavior. It was not the intention of this paper to compare the conclusions with experimental results available

  13. A leak-before-break strategy for CANDU primary piping systems

    International Nuclear Information System (INIS)

    Aggarwal, M.L.; Kozluk, M.J.; Lin, T.C.; Manning, B.W.; Vijay, D.K.

    1986-01-01

    Recent advances in elastic-plastic fracture mechanics have made it possible to assess the stability of cracks in ductile piping systems. These technological developments have been used by Ontario Hydro as the nucleus of an approach for demonstrating that CANDU primary heat transport piping systems will not break catastrophically; at worst they would leak at a detectable rate. This leak-before-break approach has been taken on the Darlington nuclear generating station as a design stage alternative to the provision of pipe whip restraints on large diameter, primary heat transport system piping. Positive conclusions reached via this approach are considered sufficient to exclude the requirement to provide protective devices, such as pipe whip restraints. In arriving at the proposed leak-before-break approach a review of current and proposed leak-before-break licensing positions of other jurisdictions (particularly those in the United States and the Federal Republic of Germany) was carried out. The approach presented makes use of recent American developments in the area of elastic-plastic fracture mechanics. It also gives consideration to aspects which are unique to the pressurized heavy water (CANDU) reactors used by Ontario Hydro. The proposed leak-before-break approach is described and its use is illustrated by applying it to the Darlington generating station primary heat transport system pump suction piping. (author)

  14. Lead plant application of leak-before-break to high energy piping. Final report, January 1989

    International Nuclear Information System (INIS)

    1989-01-01

    This report presents the experience gained during a successful application of a leak-before-break program by Duquesne Light Company. This program was directed at the high energy nuclear piping at Beaver Valley Power Station - Unit 2. This experience can be applied to other nuclear plant leak-before-break efforts in order to minimize the number of pipe whip restraints, jet impingement shields, snubbers, and to discount the consideration of remaining pipe rupture dynamic effects. The chronology of events leading to Nuclear Regulatory Commission approval of the Beaver Valley Power Station - Unit 2 lead plant effort is described. The final report and pertinent sections of the final Safety Evaluation Report are also included. (author)

  15. Analysis methods for evaluating leak-before-break in U-tube steam generators

    International Nuclear Information System (INIS)

    Griesbach, T.; Cipolla, R.

    1985-01-01

    In recent years, there has been an increased incidence of cracking in steam generator tubes. As a result, there has been increased effort in assuring that cracks in steam generator tubes will leak well in advance of significant loss in structural integrity. Demonstrating a leak-before-break condition is an integrated analysis process that utilizes several engineering disciplines, specifically, materials engineering, fracture mechanics, stress analysis, and fluid mechanics. The output from a leak-before-break assessment is typically depicted in terms of available margins against failure and measurable or detectable leak rate. In this paper, the analysis methods for performing a leak-before-break analysis for the U-tubes of a recirculating steam generator are presented. The results from generic analysis for the first row U-tubes illustrates the analysis techniques. Because of realistic input values used herein, these results also suggest that large leak rates are possible from cracks in U-bend regions, yet these cracks are small relative to their critical size for failure. Hence, orderly shutdowns can be completed prior to the point when tube bursting is of concern

  16. French regulatory practice and reflections on the leak-before-break concept

    International Nuclear Information System (INIS)

    Barrachin, B.; Jamet, P.

    1986-01-01

    For nuclear units in the design phase, the vendor (FRAMATOME) and the utility (EDF) examine the possibility of applying the leak-before-break criterion to a certain number of circuits, particularly the primary circuit and various parts of the secondary circuit. EDF has not completed its reflection on the leak-before-break approach and consequently, French safety authorities have not been officially notified of any request for assessment of the acceptability of such an approach. Nevertheless, from a strict safety point of view, it is possible to determine minimal conditions required in the implementation of such a course of action. Firstly, removing pipe breaks from the design basis of the plant will significantly weaken the application of the defense in-depth concept. This must be counter-balanced by reinforced manufacturing non destructive examinations and a stringent in-service inspection. Secondly, the demonstration of the existence of leaks before breaks must be obtained with a high degree of certainty, which requires large investments in a certain number of fields. The exact methodology will be defined by the Vendor and the utility at a later stage. However, from our point of view, analysis should involve the following steps: Definition of a maximum size defect; analysis of evolution under normal loads; stability analysis, definition of the critical defect; Definition of the detectable defect. This paper develops each of these points, and specifies, for each discipline, the domains in which present knowledge must be expanded and deepened [fr

  17. A probabilistic method for leak-before-break analysis of CANDU reactor pressure tubes

    Energy Technology Data Exchange (ETDEWEB)

    Puls, M.P.; Wilkins, B.J.S.; Rigby, G.L. [Whiteshell Labs., Pinawa (Canada)] [and others

    1997-04-01

    A probabilistic code for the prediction of the cumulative probability of pressure tube ruptures in CANDU type reactors is described. Ruptures are assumed to result from the axial growth by delayed hydride cracking. The BLOOM code models the major phenomena that affect crack length and critical crack length during the reactor sequence of events following the first indications of leakage. BLOOM can be used to develop unit-specific estimates of the actual probability of pressure rupture in operating CANDU reactors and supplement the existing leak before break analysis.

  18. Study on criterion for leak before break assessment of pressure pipes

    International Nuclear Information System (INIS)

    Yang Linjuan

    2009-01-01

    Based on the elastoplastic fracture mechanics, this paper established the expression formulas of limit buckling pressure P u on the ligament of axial and circumferential surface cracks and the initial pressure for the through cracks P c . A new Leak Before Break (LBB) assessment criterion was put forward to predict the failure mode of pressure pipes, i.e., when P u is less than P c , the pipe will leak; when P u is equal to or larger than P c , the pipe will break, which is verified by the test data reported in literatures. (authors)

  19. A probabilistic method for leak-before-break analysis of CANDU reactor pressure tubes

    International Nuclear Information System (INIS)

    Puls, M.P.; Wilkins, B.J.S.; Rigby, G.L.

    1997-01-01

    A probabilistic code for the prediction of the cumulative probability of pressure tube ruptures in CANDU type reactors is described. Ruptures are assumed to result from the axial growth by delayed hydride cracking. The BLOOM code models the major phenomena that affect crack length and critical crack length during the reactor sequence of events following the first indications of leakage. BLOOM can be used to develop unit-specific estimates of the actual probability of pressure rupture in operating CANDU reactors and supplement the existing leak before break analysis

  20. The concepts of leak before break and absolute reliability of NPP equipment and piping

    International Nuclear Information System (INIS)

    Getman, A.F.; Komarov, O.V.; Sokov, L.M.

    1997-01-01

    This paper describes the absolute reliability (AR) concept for ensuring safe operation of nuclear plant equipment and piping. The AR of a pipeline or component is defined as the level of reliability when the probability of an instantaneous double-ended break is near zero. AR analysis has been applied to Russian RBMK and VVER type reactors. It is proposed that analyses required for application of the leak before break concept should be included in AR implementation. The basic principles, methods, and approaches that provide the basis for implementing the AR concept are described

  1. Methods of assessing the leak-before-break behaviour of pressurized components

    International Nuclear Information System (INIS)

    Goerner, F.

    1984-01-01

    A general overview of the parameters is first given, which are important for the stress and service life of a pressurized component. The individual parameters are discussed, where the main points are the calculation of stress intensity factors, the fatigue behaviour and the calculation of plastic limiting loads and elastic-plastic failure factors (COD and J integral), using the Dugdale model. In a final chapter, the leak-before-break diagrams are given and compared for different methods of calculation for pipes with longitudinal and circumferential cracks and for flat plates. (orig./HP) [de

  2. The concepts of leak before break and absolute reliability of NPP equipment and piping

    Energy Technology Data Exchange (ETDEWEB)

    Getman, A.F.; Komarov, O.V.; Sokov, L.M. [and others

    1997-04-01

    This paper describes the absolute reliability (AR) concept for ensuring safe operation of nuclear plant equipment and piping. The AR of a pipeline or component is defined as the level of reliability when the probability of an instantaneous double-ended break is near zero. AR analysis has been applied to Russian RBMK and VVER type reactors. It is proposed that analyses required for application of the leak before break concept should be included in AR implementation. The basic principles, methods, and approaches that provide the basis for implementing the AR concept are described.

  3. The application of leak before break concepts piping of KWU-plants

    International Nuclear Information System (INIS)

    Bartholome, G.; Bieselt, R.W.

    1985-01-01

    The fracture of pipes with longitudinal and circumferential cracks was investigated by experiments and theoretical approaches (flow stress criteria and limit load analyses). The experiments show that the critical crack dimensions can conservatively be determined by fracture mechanics. The tests and calculations are applied to KWU primary coolant piping with hypothetical longitudinal and circumferential defects. Reactor systems, design, fabrication, stress analysis, material, non-destructive testing, quality control and inservice inspection are considered referring to the leak-before-break behaviour. On the basis of the extreme toughness of the materials, the known loads, the high level of non-destructive examinations, the leakage monitoring system and the high quality of manufacture and processing it is shown that a spontaneous failure need not be postulated. (orig.)

  4. Specialist meeting on leak before break in reactor piping and vessels

    Energy Technology Data Exchange (ETDEWEB)

    Bartholome, G.; Bazant, E.; Wellein, R. [Siemens KWU, Stuttgart (Germany)] [and others

    1997-04-01

    A series of research projects sponsored by the Federal Minister for Education, Science, Research and Technology, Bonn are summarized and compared to utility, manufacturer, and vendor tests. The purpose of the evaluation was to experimentally verify Leak-before-Break behavior, confirm the postulation of fracture preclusion for piping (straight pipe, bends and branches), and quantify the safety margin against massive failure. The results are applicable to safety assessment of ferritic and austenitic piping in primary and secondary nuclear power plant circuits. Moreover, because of the wide range of the test parameters, they are also important for the design and assessment of piping in other technical plant. The test results provide justification for ruling out catastrophic fractures, even on pipes of dimensions corresponding to those of a main coolant pipe of a pressurized water reactor plant on the basis of a mechanical deterministic safety analysis in correspondence with the Basis Safety Concept (Principle of Fracture Exclusion).

  5. Application of leak-before-break criteria to pressurized water reactors

    International Nuclear Information System (INIS)

    Roege, P.; Day, B.; Beckjord, E.; Golay, M.

    1986-01-01

    The possibility of consequential damage to safety-related systems or components after postulated pipe breaks in Light Water Reactors has led to the installation of pipe restraints capable of withstanding the loads in such an accident. These restraints are a significant part of initial capital cost, and because of their size and location, impede plant maintenance. The Piping Review Committee of the U.S. Nuclear Regulatory Commission has concluded that, subject to fulfillment of certain criteria, the pipe restraints for pressurized water reactor main coolant piping are not necessary, because the failure mode of this piping is such that it will leak before it will break, and the leakage of reactor coolant is large enough to detect. In this study, we examine the piping systems of a 4-loop 1,150 MWe pressurized water reactor, determining the crack size that would be stable from a fracture mechanics point of view, and the range of leak rates that would ensue. We then consider the sensitivity of conventional leak detection systems, and find that pipe sizes down to 45 cm in diameter would meet the leak-before-break criteria. Improvements in the sensitivity of conventional leak detectors would extend this range down to pipe sizes down to the range of 20 - 45 cm in diameter. The development of local leak detection systems which would respond to leaks in compartments or confined areas would make it possible to apply the criteria to sizes as low as 10 - 20 cm in diameter, which appear to be the limit of the net cost savings of eliminating pipe restraints and adding additional leak detection instrumentation. Extending the leak-before-break concept into this smallest pipe range may require improved precision in crack definition, flow modeling, and leak detection. Better detection of leaks may also require use of new detection methods coupled to novel approaches to piping system design. (J.P.N.)

  6. The J-resistance curve Leak-before-Break test program on material for the Darlington Nuclear Generating Station

    International Nuclear Information System (INIS)

    Mukherjee, B.

    1988-01-01

    The Darlington Leak-Before-Break (DLBB) approach has been developed for large diameter (21, 22, 24 inch) SA106B heat transport (HT) piping and SA105 fittings as a design alternative to pipewhip restraints and in recognition of the questionable benefits of providing such restraints. Ontario Hydro's DLBB approach is based on the elastic plastic fracture mechanics method. In this test program, J-resistance curves were determined from actual pipe heats that were used in the construction of the Darlington heat transport systems (Units 1 and 2). Test blocks were prepared using four different welding procedures for nuclear Class I piping. The test program was designed to take into account the effect of various factors such as test temperature, crack plane orientation, welding effects, etc., which have influence on fracture properties. A total of 91 tests were conducted. An acceptable lower bound J-resistance curve for the piping steels was obtained by machining maximum thickness specimens from the pipes and by testing side grooved compact tension specimens. Test results showed that all pipes, welds and heat-affected zone materials within the scope of the DLBB program exhibited uppershelf toughness behaviour. All specimens showed high crack initiation toughness Jsub(lc), rising J-resistance curve and stable and ductile crack extension. Toughness of product forms depended on the direction of crack extension (circumferential versus axial crack orientation). Toughness of DLBB welds and parent materials at 250 0 C was lower than that at 20 0 C. (author)

  7. Corrosion in nuclear power plants and it implication in the leak before break criteria

    International Nuclear Information System (INIS)

    Martinez M, E.

    1992-05-01

    The corrosion in a general way can be defined like a chemical or electrochemical reaction, which is carried out in the surface of the metallic materials exposed to a specific medium. Due to the operation conditions in the nuclear power plants are practically fixed and its modification in most of the cases is difficult or expensive, the natural tendency to prevent the corrosion has been generally directed toward the selection of materials. Numerous materials have been employees as substitute of the traditional steels, among other the stabilized stainless steels, those of extra low carbon and numerous nickel base alloys. The basic evaluation that establishes the approach Leak before break (LBB) it involves the analysis by means of 'fracture mechanics' of a postulated crevice that it crosses the thickness of the material, which causes a same flight, with a margin of safety, to the detection limit that it has for a shutdown of the reactor. Due to the crevice size postulated, it cannot be established highly starting from the mechanical properties of the material since these its will be affected by the corrosion mechanisms that can settle down, it was determined that the implementation of the LBB criteria, it cannot be established for components or systems that its are susceptible of suffering corrosion. (Author)

  8. The detection of leaks on sodium pipes in a 'leak before break' approach

    International Nuclear Information System (INIS)

    Antonakas, D.

    1989-01-01

    The operation of circuits containing liquid sodium requires, given the chemical affinity of this fluid for air and water, a reliable detection of possible leaks. This system of detection should alert the operators to the occurrence of a leak in sufficient time to limit the potential consequences of a discharge of sodium in the building, leading to a severe sodium fire or at least to an extended corrosion of the pipe system. From a design point of view, the most likely event leading to this situation can be the consequence. of an initial undetected defect which develops under the effect of thermo-mechanical loadings, produces a sodium. leak below the dejection threshold remains undetectable white progressing and finally leads to a guillotine-type rupture when an incidental loading is superimposed to the normal one. The 'leak before break' approach which is now currently introduced in design considerations consists of insuring the detection of incipient leaks corresponding to through-the-wall cracks well below instability of the pipe. Under this short statement, lies a considerable and still necessary effort of research broadly presented in the present paper

  9. Leak-before-break analysis of thermally aged nuclear pipe under different bending moments

    Energy Technology Data Exchange (ETDEWEB)

    Lv, Xuming; Li, Shilei; Zhang, Hailong; Wang, Yanli; Wang, Xitao [University of Science and Technology Beijing, Beijing (China); Wang, Zhaoxi [CPI Nuclear Power Institute, Beijing (China); Xue, Fei [Suzhou Nuclear Power Research Institute, Suzhou (China)

    2015-10-15

    Cast duplex stainless steels are susceptible to thermal aging during long-term service at temperatures ranging from 280°C to 450°C. To analyze the effect of thermal aging on leak-before-break (LBB) behavior, three-dimensional finite element analysis models were built for circumferentially cracked pipes. Based on the elastic–plastic fracture mechanics theory, the detectable leakage crack length calculation and J-integral stability assessment diagram approach were carried out under different bending moments. The LBB curves and LBB assessment diagrams for unaged and thermally aged pipes were constructed. The results show that the detectable leakage crack length for thermally aged pipes increases with increasing bending moments, whereas the critical crack length decreases. The ligament instability line and critical crack length line for thermally aged pipes move downward and to the left, respectively, and unsafe LBB assessment results will be produced if thermal aging is not considered. If the applied bending moment is increased, the degree of safety decreases in the LBB assessment.

  10. Application of a finite element method to leak before break (LBB) of a heat exchanger

    International Nuclear Information System (INIS)

    Lee, Choon-Yeol; Kwon, Jae-Do; Lee, Yong-Sun

    2003-01-01

    The leak before break (LBB) concept is difficult to apply to a structure with a thin tube that is immersed in a water environment. A heat exchanger in a nuclear power plant is such a structure. The present paper addresses an application of the LBB concept to a heat exchanger in a nuclear power plant. The minimum leaked coolant amount containing the radioactive material which can activate the radiation detector device installed near the heat exchanger is assumed. The postulated initial flaw size that cannot grow to the critical flaw size within the time period to activate the radiation detector is justified. In this case, the radiation detector can activate the warning signal caused by coolant leakage from initially postulated flaws of the heat exchanger. The nuclear plant can safely shutdown when this occurs. Since the postulated initial flaw size can not grow to the critical flaw size, the structural integrity of the heat exchanger is not impeded. Particularly the informational scenario presented in this paper discusses an actual nuclear plant. (author)

  11. Leak before break behaviour of austenitic and ferritic pipes containing circumferential defects

    Energy Technology Data Exchange (ETDEWEB)

    Stadtmueller, W.; Sturm, D.

    1997-04-01

    Several research projects carried out at MPA Stuttgart to investigate the Leak-before-Break (LBB) behavior of safety relevant pressure bearing components are summarized. Results presented relate to pipes containing circumferential defects subjected to internal pressure and external bending loading. An overview of the experimentally determined results for ferritic components is presented. For components containing postulated or actual defects, the dependence of the critical loading limit on the defect size is shown in the form of LBB curves. These are determined experimentally and/or by calculation for through-wall slits, and represent the boundary curve between leakage and massive fracture. For surface defects and a given bending moment and internal pressure, no fracture will occur if the length at leakage remains smaller than the critical defect length given by the LBB curve for through-wall defects. The predictive capability of engineering calculational methods are presented by way of example. The investigation programs currently underway, testing techniques, and initial results are outlined.

  12. Some research in the field of leak before break criteria for piping

    International Nuclear Information System (INIS)

    Lazzeri, L.

    1984-01-01

    Leak-before-break research activity has lead to the following basic results: a) From an extensive analysis of the available experimental data it is concluded that the concept of net section collapse is a simple, reliable, valid tool in the case of very ductile materials. b) The analysis of some experimental data has lead to the conclusion that for partially ductile materials mixed ductile, fragile conditions may be present. c) From the analyses at a and b criteria have been established in order to compute collapse conditions for through cracked pipes as a function of the applied load (moment and axial load) in terms of net section collapse. d) The role of the thermal and secondary self equilibrating loads is discussed. e) The leak areas are often evaluated on the basis of the 0.1 Aflow criterion, i.e. somewhat arbitrarily assuming a leak area equal to 10% the pipe flow area. f) The 0.1 Aflow criteria is applied to typical lines, and it is concluded that such loads can be taken without using the classical pipe whip restraints, even if some increase in the size of the snubbers might be necessary

  13. Proceedings of the seminar on leak before break in reactor piping and vessels

    International Nuclear Information System (INIS)

    Faidy, C.; Gilles, P.

    1997-04-01

    The objective of the seminar was to present the current state of the art in Leak-Before-Break (LBB) methodology development, validation, and application in an international forum. With particular emphasis on industrial applications and regulatory policies, the seminar provided an opportunity to compare approaches, experiences, and codifications developed by different countries. The seminar was organized into four topic areas: status of LBB applications; technical issues in LBB methodology; complementary requirements (leak detection and inspection); LBB assessment and margins. As a result of this seminar, an improved understanding of LBB gained through sharing of different viewpoints from different countries, permits consideration of: simplified pipe support design and possible elimination of loss-of-coolant-accident (LOCA) mechanical consequences for specific cases; defense-in-depth type of applications without support modifications; support of safety cases for plants designed without the LOCA hypothesis. In support of these activities, better estimates of the limits to the LBB approach should follow, as well as an improvement in codifying methodologies. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  14. Proceedings of the seminar on leak before break in reactor piping and vessels

    Energy Technology Data Exchange (ETDEWEB)

    Faidy, C. [ed.] [Electricite de France, Villeurbanne (France); Gilles, P. [ed.] [Framatome, Paris (France)

    1997-04-01

    The objective of the seminar was to present the current state of the art in Leak-Before-Break (LBB) methodology development, validation, and application in an international forum. With particular emphasis on industrial applications and regulatory policies, the seminar provided an opportunity to compare approaches, experiences, and codifications developed by different countries. The seminar was organized into four topic areas: status of LBB applications; technical issues in LBB methodology; complementary requirements (leak detection and inspection); LBB assessment and margins. As a result of this seminar, an improved understanding of LBB gained through sharing of different viewpoints from different countries, permits consideration of: simplified pipe support design and possible elimination of loss-of-coolant-accident (LOCA) mechanical consequences for specific cases; defense-in-depth type of applications without support modifications; support of safety cases for plants designed without the LOCA hypothesis. In support of these activities, better estimates of the limits to the LBB approach should follow, as well as an improvement in codifying methodologies. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  15. Leak before break evaluation for main steam piping system made of SA106 Gr.C

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Kyoung Mo; Jee, Kye Kwang; Pyo, Chang Ryul; Ra, In Sik [Korea Power Engineering Company, Seoul (Korea, Republic of)

    1997-04-01

    The basis of the leak before break (LBB) concept is to demonstrate that piping will leak significantly before a double ended guillotine break (DEGB) occurs. This is demonstrated by quantifying and evaluating the leak process and prescribing safe shutdown of the plant on the basis of the monitored leak rate. The application of LBB for power plant design has reduced plant cost while improving plant integrity. Several evaluations employing LBB analysis on system piping based on DEGB design have been completed. However, the application of LBB on main steam (MS) piping, which is LBB applicable piping, has not been performed due to several uncertainties associated with occurrence of steam hammer and dynamic strain aging (DSA). The objective of this paper is to demonstrate the applicability of the LBB design concept to main steam lines manufactured with SA106 Gr.C carbon steel. Based on the material properties, including fracture toughness and tensile properties obtained from the comprehensive material tests for base and weld metals, a parametric study was performed as described in this paper. The PICEP code was used to determine leak size crack (LSC) and the FLET code was used to perform the stability assessment of MS piping. The effects of material properties obtained from tests were evaluated to determine the LBB applicability for the MS piping. It can be shown from this parametric study that the MS piping has a high possibility of design using LBB analysis.

  16. Application of the leak-before-break concept to steam generator tubes

    International Nuclear Information System (INIS)

    Keim, E.; Kastner, W.

    1994-01-01

    The Leak-Before-Break (LBB) behaviour of a piping component means that the length of a crack resulting in a leak is smaller than the critical crack length and that the leak is safety detectable by a suitable monitoring system. The LBB-concept of Siemens/KWU is based on computer codes for the evaluation of critical crack lengths, crack openings, leakage areas and leakage rates, developed by Siemens/KWU. The fracture mechanics analysis supplies the input for the thermal-hydraulic analysis. The resulting leakage rate related to the crack length of a longitudinal or circumferential crack and the minimum detectable values of leakage rate and crack length lead to two criteria, which allow for the LBB-behaviour of the pipe: - the critical crack length must be larger than the crack length being safety detected by leakage monitoring systems (LMS) - the critical crack length must be larger than the crack length being safety detected by non-destructive examination (NDE). This LBB-concept is applied to steam generator (SG) tubes. Two examples, which will be presented, show that this concept is a very useful and effective tool which allows the prediction of LBB-behaviour of SG tubes. (Author)

  17. Proceedings of the seminar on Leak-Before-Break: Progress in regulatory policies and supporting research

    International Nuclear Information System (INIS)

    Kashima, K.; Wilkowski, G.M.

    1988-03-01

    The third in a series of international Leak-Before-Break (LBB) Seminars supported in part by the US Nuclear Regulatory Commission was held at TEPCO Hall in the Tokyo Electric Power Company's (TEPCO) Electric Power Museum on May 14 and 15, 1987. The seminar updated the international policies and supporting research on LBB. Attendees included representatives from regulatory agencies, electric utility representatives, fabricators of nuclear power plants, research organizations, and university professors. Regulatory policy was the subject of presentations by Mr. G. Arlotto (US NRC, USA), Dr. H. Schultz (GRS, W. Germany), Dr. P. Milella (ENEA-DISP, Italy), Dr. C. Faidy, P. Jamet, and S. Bhandari (EDF/Septen, CEA/CEN, and Framatome, France), and Mr. T. Fukuzawa (MITI, Japan). Dr. F. Nilsson presented revised nondestructive inspection requirements relative to LBB in Sweden. In addition, several papers on the supporting research programs discussed regulatory policy. Questions following the presentations of the papers focused on the impact of various LBB policies or the impact of research findings. Supporting research programs were reviewed on the first and second day by several participants from the US, Japan, Germany, Canada, Italy, Sweden, England, and France

  18. Fracture mechanics assessment of thermal aged nuclear piping based on the Leak-Before-Break concept

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Mingya, E-mail: chenmingya@cgnpc.com.cn [Suzhou Nuclear Power Research Institute, Suzhou, Jiangsu Province (China); Yu, Weiwei [Suzhou Nuclear Power Research Institute, Suzhou, Jiangsu Province (China); Qian, Guian [Paul Scherrer Institute, Nuclear Energy and Safety Department, Villigen PSI (Switzerland); Wang, Rongshan; Lu, Feng; Zhang, Guodong; Xue, Fei; Chen, Zhilin [Suzhou Nuclear Power Research Institute, Suzhou, Jiangsu Province (China)

    2016-05-15

    Highlights: • The effects of thermal aging on crack unstable tearing are studied. • The critical size of crack unstable tearing is calculated by different methods. • The critical failure models are compared. • The conservatism of J–T diagram is shown. - Abstract: The Leak-Before-Break (LBB) concept has been accepted to design the primary piping system of the pressurized water reactor (PWR). Due to thermal aging of long term operation, the cast stainless steels (CSSs) which are used for the primary piping of PWR, suffer a significant loss of fracture toughness, and as a consequence the safety margin of the thermal aged pipe decreases. Therefore, the aged piping should be analyzed and validated by the LBB concept. In this paper, elastic–plastic fracture mechanics (EPFM) assessments of the thermal aged piping are presented according to the LBB concept. The critical break size of crack unstable tearing is calculated by the EPFM method. The crack driving force diagram (J–a diagram), the stability assessment diagram (J–T diagram) and a numerical method are applied to calculate the critical crack size of crack break. The effects of thermal aging on the plastic limit load, J–T diagram, critical crack size of the EPFM and the critical failure mode are studied. The results show that the thermal aging effect decreases the maximum allowed J-integral at a certain ductile tearing modulus by more than 50% and it increases the flow stress and plastic limit load by 11.78%. The results based on the J–T diagram are about 40% conservative than those based on the direct numerical method for the high loading case. For the thermal aged piping, it is important to consider the competition failure modes between plastic collapse and unstable ductile tearing.

  19. Additional requirements for leak-before-break application to primary coolant piping in Belgium

    Energy Technology Data Exchange (ETDEWEB)

    Roussel, G. [AIB Vincotte Nuclear, Brussels (Belgium)

    1997-04-01

    Leak-Before-Break (LBB) technology has not been applied in the first design of the seven Pressurized Water Reactors the Belgian utility is currently operating. The design basis of these plants required to consider the dynamic effects associated with the ruptures to be postulated in the high energy piping. The application of the LBB technology to the existing plants has been recently approved by the Belgian Safety Authorities but with a limitation to the primary coolant loop. LBB analysis has been initiated for the Doel 3 and Tihange 2 plants to allow the withdrawal of some of the reactor coolant pump snubbers at both plants and not reinstall some of the restraints after steam generator replacement at Doel 3. LBB analysis was also found beneficial to demonstrate the acceptability of the primary components and piping to the new conditions resulting from power uprating and stretch-out operation. LBB analysis has been subsequently performed on the primary coolant loop of the Tihange I plant and is currently being performed for the Doel 4 plant. Application of the LBB to the primary coolant loop is based in Belgium on the U.S. Nuclear Regulatory Commission requirements. However the Belgian Safety Authorities required some additional analyses and put some restrictions on the benefits of the LBB analysis to maintain the global safety of the plant at a sufficient level. This paper develops the main steps of the safety evaluation performed by the Belgian Safety Authorities for accepting the application of the LBB technology to existing plants and summarizes the requirements asked for in addition to the U.S. Nuclear Regulatory Commission rules.

  20. Leak-Before-Break assessment of a welded piping based on 3D finite element method

    International Nuclear Information System (INIS)

    Chen, Mingya; Yu, Weiwei; Chen, Zhilin; Qian, Guian; Lu, Feng; Xue, Fei

    2017-01-01

    Highlights: • The effects of load reduction, strength match, welding width, load level, crack size and constraint are studied. • The results show that the LBB margin is dependent on the load level. • The results show that higher strength-match of WPJs will have higher crack-front constraints. • The results show that the engineering method has a high precision only if the width of weld is comparable to the crack depth. - Abstract: The paper studies the effects of the load reduction (discrepancy between designing and real loadings), strength match of the welded piping joint (WPJ), welding width, crack size and crack tip constraint on the Leak-Before-Break (LBB) assessment of a welded piping. The 3D finite element (FE) method is used in the study of a surge line of the steam generator in a nuclear power plant. It is demonstrated that the LBB margin is dependent on the loading level and the load reduction effect should be considered. When the loading is high enough, there is a quite large deviation between the J-integral calculated based on the real material property of WPJ and that calculated based on the engineering method, e.g. Zahoor handbook of Electric Power Research Institute (EPRI). The engineering method assumes that the whole piping is made of the unique welding material in the calculation. As the influence of the strength matching and welding width is ignored in the engineering method for J-integral calculation, the engineering method has a sufficient precision only if the width of welding is comparable to the crack depth. Narrower welding width leads to higher constraint of the plastic deformation in the welding and larger high stress areas in the base for the low strength-match WPJ. Higher strength matching of WPJs has higher crack-front constraints.

  1. The {open_quotes}leak-before-break{close_quotes} applicability in decision support system {open_quotes}strength{close_quotes}

    Energy Technology Data Exchange (ETDEWEB)

    Torop, V.M.; Orynyak, I.V. [Institute for Problems of Strength, Kiev (Ukraine); Kutovoy, O.L. [Institute of Structure Integrity, Kiev (Ukraine)

    1997-04-01

    A software decision support system, STRENGTH, for application of leak before break analysis, is described. The background methodology and sample application are outlined. The program allows multioptional computation of loading parameters for different types of defects, and variable properties for metals and welded joints. Structural strength is assessed, and service life predictions are made. The program is used to analyze specific defects identified by nondestructive testing.

  2. The leak before break criteria, requirements and implications; El criterio de fuga antes de ruptura, requerimientos e implicaciones

    Energy Technology Data Exchange (ETDEWEB)

    Martinez M, E

    1992-05-15

    Inside this work a general balance is made on the Leak before break approach (LBB), like they are the history and licensing, those limitations, the acceptance criteria of the LBB, the current state of the regulatory development and the current state of it application in countries like E.U.A, Germany, Canada, Italy and France. Everything it with the purpose of evaluating the opportunities that offers the LBB criteria for it possible application in Mexico. (Author)

  3. Proceedings of a specialist meeting on leak before break in reactor piping and vessels

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-07-01

    This Specialist Meeting was organised by EDF, Framatome and CEA with the participation of SFEN, and it was sponsored jointly by the CEC DG XI, Nuclear Electric, IAEA, US NRC, and by the Principal Working Group 3 (PWG-3) on Reactor Component Integrity of the NEA CSNI. The activities of PWG-3 fall into three main areas: Non-Destructive Examination (NDE), fracture analysis and aging/materials degradation. In fracture analysis, the activities are organised by the Fracture Analysis Group, and include the round robins on Fracture Analysis of Large Scale International Reference Experiments (FALSIRE). The topic of the workshop falls mainly into the second area of fracture analysis. The objective of the meeting was to present the current state of the art in Leak-Before-Break (LBB) methodology development, validation, and application in an international forum. With particular emphasis on industrial applications and regulatory policies, the seminar provided an opportunity to compare approaches, experiences, and codifications developed by different countries. The seminar was organized into four topic areas: status of LBB applications; technical issues in LBB methodology; complementary requirements (leak detection and inspection); LBB assessment and margins. As a result of this seminar, an improved understanding of LBB gained through sharing of different viewpoints from different countries, permits consideration of: simplified pipe support design and possible elimination of loss-of-coolant-accident (LOCA) mechanical consequences for specific cases; defense-in-depth type of applications without support modifications; support of safety cases for plants designed without the LOCA hypothesis. In support of these activities, better estimates of the limits to the LBB approach should follow, as well as an improvement in codifying methodologies. The formal proceedings of the meeting were published by US NRC as a NUREG report (NUREG/CP--0155). This includes the final versions of papers

  4. Proceedings of a specialist meeting on leak before break in reactor piping and vessels

    International Nuclear Information System (INIS)

    1996-01-01

    This Specialist Meeting was organised by EDF, Framatome and CEA with the participation of SFEN, and it was sponsored jointly by the CEC DG XI, Nuclear Electric, IAEA, US NRC, and by the Principal Working Group 3 (PWG-3) on Reactor Component Integrity of the NEA CSNI. The activities of PWG-3 fall into three main areas: Non-Destructive Examination (NDE), fracture analysis and aging/materials degradation. In fracture analysis, the activities are organised by the Fracture Analysis Group, and include the round robins on Fracture Analysis of Large Scale International Reference Experiments (FALSIRE). The topic of the workshop falls mainly into the second area of fracture analysis. The objective of the meeting was to present the current state of the art in Leak-Before-Break (LBB) methodology development, validation, and application in an international forum. With particular emphasis on industrial applications and regulatory policies, the seminar provided an opportunity to compare approaches, experiences, and codifications developed by different countries. The seminar was organized into four topic areas: status of LBB applications; technical issues in LBB methodology; complementary requirements (leak detection and inspection); LBB assessment and margins. As a result of this seminar, an improved understanding of LBB gained through sharing of different viewpoints from different countries, permits consideration of: simplified pipe support design and possible elimination of loss-of-coolant-accident (LOCA) mechanical consequences for specific cases; defense-in-depth type of applications without support modifications; support of safety cases for plants designed without the LOCA hypothesis. In support of these activities, better estimates of the limits to the LBB approach should follow, as well as an improvement in codifying methodologies. The formal proceedings of the meeting were published by US NRC as a NUREG report (NUREG/CP--0155). This includes the final versions of papers

  5. Application of Leak Before Break concept in 316LN austenitic steel pipes welded using 316L

    International Nuclear Information System (INIS)

    Cunto, Gabriel Giannini de

    2017-01-01

    This work presents a study of application of the Leak Before Break (LBB) concept, usually applied in nuclear power plants, in a pipe made from steel AISI type 316LN welded a coated electrode AISI type 316L. LBB concept is a criterion based on fracture mechanics analysis to show that a crack leak, present in a pipe, can be detected by leak detection systems, before this crack reaches a critical size that results in pipe fail. In the studied pipe, tensile tests and Ramberg-Osgood analyses were performed, as well as fracture toughness tests for obtaining the material resistance curve J-R. The tests were performed considering the base metal, weld and heat affected zone (HAZ), at the same operating temperatures of a nuclear power plant. For the mechanical properties found in these tests, load limit analyses were performed in order to determine the size of a crack which could cause a detectable leakage and the critical crack size, considering failure by plastic collapse. For the critical crack size found in the weld, which is the region that presented the lowest toughness, Integral J and tearing modulus T analyses were performed, considering failure by tearing instability. Results show a well-defined behavior between the base metal, HAZ and weld zones, where the base metal has a high toughness behavior, the weld has a low toughness behavior and the HAZ showed intermediate mechanical properties between the base metal and the weld. Using the PICEP software, the leak rate curves versus crack size and also the critical crack size were determined by considering load limit analysis. It was observed that after a certain crack size, the leak rate in base metal is much higher than for the HAZ and the weld, considering the same crack length. This occurs because in the base metal crack, it is expected that the crack grows in a more rounded form due to its higher toughness. The lowest critical crack size was found for the base metal presenting circumferential cracks. For the

  6. ProLBB - A Probabilistic Approach to Leak Before Break Demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Dillstroem, Peter; Weilin Zang (Inspecta Technology AB, Stockholm (SE))

    2007-11-15

    Recently, the Swedish Nuclear Power Inspectorate has developed guidelines on how to demonstrate the existence of Leak Before Break (LBB). The guidelines, mainly based on NUREG/CR-6765, define the steps that must be fulfilled to get a conservative assessment of LBB acceptability. In this report, a probabilistic LBB approach is defined and implemented into the software ProLBB. The main conclusions, from the study presented in this report, are summarized below. - The probabilistic approach developed in this study was applied to different piping systems in both Boiler Water Reactors (BWR) and Pressurised Water Reactors (PWR). Pipe sizes were selected so that small, medium and large pipes were included in the analysis. The present study shows that the conditional probability of fracture is in general small for the larger diameter pipes when evaluated as function of leak flow rate. However, when evaluated as function of fraction of crack length around the circumference, then the larger diameter pipes will belong to the ones with the highest conditional fracture probabilities. - The total failure probability, corresponding to the product between the leak probability and the conditional fracture probability, will be very small for all pipe geometries when evaluated as function of fraction of crack length around the circumference. This is mainly due to a small leak probability which is consistent with expectations since no active damage mechanism has been assumed. - One of the objectives of the approach was to be able to check the influence of off-centre cracks (i.e. the possibility that cracks occur randomly around the pipe circumference). To satisfy this objective, new stress intensity factor solutions for off-centre cracks were developed. Also to check how off-centre cracks influence crack opening areas, new form factors solutions for COA were developed taking plastic deformation into account. - The influence from an off-center crack position on the conditional

  7. ProLBB - A Probabilistic Approach to Leak Before Break Demonstration

    International Nuclear Information System (INIS)

    Dillstroem, Peter; Weilin Zang

    2007-11-01

    Recently, the Swedish Nuclear Power Inspectorate has developed guidelines on how to demonstrate the existence of Leak Before Break (LBB). The guidelines, mainly based on NUREG/CR-6765, define the steps that must be fulfilled to get a conservative assessment of LBB acceptability. In this report, a probabilistic LBB approach is defined and implemented into the software ProLBB. The main conclusions, from the study presented in this report, are summarized below. - The probabilistic approach developed in this study was applied to different piping systems in both Boiler Water Reactors (BWR) and Pressurised Water Reactors (PWR). Pipe sizes were selected so that small, medium and large pipes were included in the analysis. The present study shows that the conditional probability of fracture is in general small for the larger diameter pipes when evaluated as function of leak flow rate. However, when evaluated as function of fraction of crack length around the circumference, then the larger diameter pipes will belong to the ones with the highest conditional fracture probabilities. - The total failure probability, corresponding to the product between the leak probability and the conditional fracture probability, will be very small for all pipe geometries when evaluated as function of fraction of crack length around the circumference. This is mainly due to a small leak probability which is consistent with expectations since no active damage mechanism has been assumed. - One of the objectives of the approach was to be able to check the influence of off-centre cracks (i.e. the possibility that cracks occur randomly around the pipe circumference). To satisfy this objective, new stress intensity factor solutions for off-centre cracks were developed. Also to check how off-centre cracks influence crack opening areas, new form factors solutions for COA were developed taking plastic deformation into account. - The influence from an off-center crack position on the conditional

  8. Leak-before-break concept for evaluation of flows detected in pressure tubes in a Candu type reactor

    International Nuclear Information System (INIS)

    Crespi, J.C.

    1992-01-01

    This paper reviews the role of the Leak-Before-Break concept for evaluation of flaws detected in cold-worked Zr 2.5% Nb pressure tubes in a CANDU type reactors. The acceptance criteria are intended to prevent failure by brittle fracture, plastic collapse of the ligament and delayed hydride cracking. The methodology developed here was of great help in order to establish the operative conditions for fuel channel garter springs repositioning by means of the SLA Rette tool at Embalse Nuclear Generating Station, Cordoba, Argentina. (author)

  9. Application of the leak-before-break concept to the primary circuit piping of the Leningrad NPP

    Energy Technology Data Exchange (ETDEWEB)

    Eperin, A.P.; Zakharzhevsky, Yu.O.; Arzhaev, A.I. [and others

    1997-04-01

    A two-year Finnish-Russian cooperation program has been initiated in 1995 to demonstrate the applicability of the leak-before-break concept (LBB) to the primary circuit piping of the Leningrad NPP. The program includes J-R curve testing of authentic pipe materials at full operating temperature, screening and computational LBB analyses complying with the USNRC Standard Review Plan 3.6.3, and exchange of LBB-related information with emphasis on NDE. Domestic computer codes are mainly used, and all tests and analyses are independently carried out by each party. The results are believed to apply generally to RBMK type plants of the first generation.

  10. Application of fracture mechanics leak-before-break analyses for protection against pipe rupture in SEP plants

    International Nuclear Information System (INIS)

    Copeland, J.F.; Riccardella, P.C.

    1984-01-01

    In accordance with the latest NRC guidance the leak-before-break technique was evaluated for high-energy piping systems in a nuclear power plant. The elements of this evaluation include determination of: 1) largest crack size which will remain stable; 2) leak rate resulting from a crack with length twice the pipe wall thickness; 3) size of crack which will leak at a rate greater than 1 gpm, if 2) results in less than 1 gpm; and 4) analysis of part-through cracks for subcritical crack growth rates to establish in-service inspection (ISI) intervals. Conclusions reached are: 1) The fracture mechanics leak-before-break approach is shown as a viable option to prevent pipe rupture. 2) Austenitic stainless steel pipes possess significant toughness, and large cracks are required for rupture. 3) The net section plastic collapse analysis is more conservative than tearing modulus evaluations. 4) Leak rates are large enough to assure detection well before cracks reach a critical size. 5) In the case studied, subcritical crack growth is slow enough to require ISI intervals of about 10 years to detect part-through cracks

  11. Material property requirements for application leak-before-break technology on nuclear power plant high-energy piping

    International Nuclear Information System (INIS)

    Li Chengliang; Deng Xiaoyun; Yin Zhiying; Liu Meng

    2012-01-01

    The application of leak-before-break (LBB) technology on nuclear power plant high-energy piping systems can improve their safety and economy, while propose some new requirements on testing material properties. The U.S. Nuclear Regulatory Commission's LBB related standard review plan and implementation specifications were analyzed, and test items, object, temperature, quantity and thermal aging effect of five general requirements were summarized. In addition, four key testing technical requirements, such as specimen size, side grooves, strain range and the orientation of specimens were also discussed to ensure the test data usefulness, representativeness and integrity. This study can provide some guidance for the aforementioned test program on domestic materials. (authors)

  12. Leak-before-break analysis of a dissimilar metal welded joint for connecting pipe-nozzle in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Gong, N. [MOE Key Laboratory of Pressurized System and Safety, School of Mechanical and Power Engineering, East China University of Science and Technology, Shanghai 200237 (China); Wang, G.Z., E-mail: gzwang@ecust.edu.cn [MOE Key Laboratory of Pressurized System and Safety, School of Mechanical and Power Engineering, East China University of Science and Technology, Shanghai 200237 (China); Xuan, F.Z.; Tu, S.T. [MOE Key Laboratory of Pressurized System and Safety, School of Mechanical and Power Engineering, East China University of Science and Technology, Shanghai 200237 (China)

    2013-02-15

    Highlights: ► Leak-before-break (LBB) analysis for a dissimilar metal weld joint (DMWJ) is made. ► Pipe-nozzle geometry and inhomogeneous material property of DMWJ are incorporated. ► LBB behavior of a defect can be assessed by LBB assessment diagram and LBB curve. ► Feasibility region of LBB is enlarged with decreasing load and increasing J{sub R}. -- Abstract: This paper presents a leak-before-break (LBB) analysis for a dissimilar metal welded joint (DMWJ) connected the safe end to pipe-nozzle of a reactor pressure vessel of which is relevant to safety of nuclear power plant. Three-dimensional finite element analysis models were built for the DMWJ structure, and the initial inner circumferential surface cracks were postulated at the interface between A508 steel and buttering Alloy82. Based on the elastic–plastic fracture mechanics theory of J-integral, the crack growth stability was analyzed, and the pipe-nozzle geometry effect and inhomogeneous material properties of the DMWJ have been incorporated. Base on the analysis results, the LBB curves and LBB assessment diagrams were constructed for the DMWJ, and effects of applied bending moment loads and J-resistance curves of materials on LBB behavior were analyzed. The results show that the LBB behavior of a defect in the DMWJ under an upmost severe load can be assessed and predicted by plotting the defect size and its propagation path in the LBB assessment diagrams. With decreasing the maximum bending moment load and increasing the crack growth resistance of materials, the ligament instability lines shift upward and the critical crack length lines move to the right in the LBB assessment diagrams, which leads to enlargement of the feasibility region in the LBB behavior.

  13. The application of leak before break concept to W7-X target module

    Energy Technology Data Exchange (ETDEWEB)

    Dundulis, G., E-mail: gintas@mail.lei.lt; Janulionis, R.; Karalevičius, R.

    2013-11-15

    Highlights: • LBB application to Wendelstein 7-X fusion reactor. • R6 method application to crack analysis. • Through wall crack opening analysis. • Determination of leak rate function. • Crack growth analysis. -- Abstract: Fusion is the energy production technology, which could potentially solve problems with growing energy demand of population in the future. Wendelstein 7-X (W7-X) is an experimental stellarator of the helias type fusion reactor currently being built in Greifswald, Germany. This experimental stellarator is a complex structure, such as nuclear power plants and high level of safety requirements should be used for structural integrity analysis. It is thus not possible to obtain simple solutions for general cases, therefore sophisticated methods are necessary for the analysis. Inside the Plasma Vessel (PV) of W7-X there is a number of different components such as pipes, divertors, baffles and targets. A guillotine failure of one component is very dangerous for structural integrity of surrounding components located in PV. For this reason it is very important to evaluate possibility to apply “leak before break” (LBB) concept for W7-X. The LBB concept is widely used in the nuclear industry to describe the idea that in the piping carrying the coolant of a power reactor a leak will occur before a catastrophic break will occurred. LBB allows to conduct the structural design without considering the loads due to postulated line breaks. The LBB analysis was made for the case when plasma vessel is operating in “baking” mode. “Baking” is the mode, when the cooling system is working as a warming system and it heats the plasma vessel structures up to 160 °C in order to release the absorbed gases from the surfaces and to pump them out of the plasma vessel before plasma operation. The LBB analysis was performed for most loaded component of target module. According to the results of the analysis it is possible to conclude that target module 1H

  14. MARATHON - a computer code for the probabilistic estimation of leak-before-break time in CANDU reactors

    International Nuclear Information System (INIS)

    Walker, J.R.

    1990-02-01

    The presence of high levels of moisture in the annulus gas system of a CANDU reactor indicates that a leaking crack may be present in a pressure tube. This will initiate the shutdown of the reactor to prevent the possibility of fuel channel damage. It is also desirable, however, to keep the reactor partially pressurized at hot shutdown for as long as it is necessary to unambiguously identify the leaking pressure tube. A premature full depressurization may cause an extended shutdown while the leaking tube is being located. However, fast fracture could occur during an excessively long hot shutdown period. A probabilistic methodology, together with an associated computer code (called MARATHON), has been developed to calculate the time from first leakage to unstable fracture in a probabilistic format. The methodology explicitly uses distributions of material properties and allows the risk associated with leak-before-break to be estimated. A model of the leak detection system is integrated into the methodology to calculate the time from leak detection to unstable fracture. The sensitivity of the risk to changing reactor conditions allows the optimization of reactor management after leak detection. In this report we describe the probabilistic model and give details of the quality assurance and verification of the MARATHON code. Examples of the use of MARATHON are given using preliminary material property distributions. These preliminary material property distributions indicate that the probability of unstable fracture is very low, and that ample time is available to locate the leaking tube

  15. Effective applied moment in circumferential through-wall cracked pipes for leak-before-break evaluation considering pipe restraint effects

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yeji; Hwang, Il-Soon [Seoul National University, Seoul 08826 (Korea, Republic of); Oh, Young-Jin, E-mail: yjoh2@kepco-enc.com [KEPCO Engineering and Construction Co. Inc., Gimcheon 39660 (Korea, Republic of)

    2016-05-15

    Highlights: • Effective applied moment at pipe cracked section considering the pipe restraint effect. • Verification of the proposed evaluation methods using finite element analyses. • Applicability for distributed external load of the proposed methods. - Abstract: In the leak-before-break (LBB) design of nuclear power plants, crack opening displacement (COD) is an essential element for determining the length of the leakage size crack. Recent researches regarding the evaluation of COD have indicated that the current practice of the LBB evaluation without consideration of the pressure induced bending (PIB) restraint overestimates COD, which in turn gives non-conservative results. Under a free-ended boundary condition, however, the applied moment at cracked section also can be overestimated, which has conservative effects on LBB evaluation. Therefore, it is necessary to evaluate pipe restraint effects on the applied moment as well as on COD to keep the constancy. In this paper, an evaluation method for the effect of the PIB restraint on COD and an effective applied moment (=crack driving force) at cracked section was developed. Both the linear elastic and elastic–plastic behaviors of the crack were considered. By comparing the behaviors with 3-D finite element analysis results from earlier studies, it was confirmed that the proposed methods make accurate estimations of the PIB restraint effect on COD. Next, the applicability of the proposed method to other types of external loading conditions was examined.

  16. Belgian experience in applying the {open_quotes}leak-before-break{close_quotes} concept to the primary loop piping

    Energy Technology Data Exchange (ETDEWEB)

    Gerard, R.; Malekian, C.; Meessen, O. [Tractebel Energy Engineering, Brussels (Belgium)

    1997-04-01

    The Leak Before Break (LBB) concept allows to eliminate from the design basis the double-ended guillotine break of the primary loop piping, provided it can be demonstrated by a fracture mechanics analysis that a through-wall flaw, of a size giving rise to a leakage still well detectable by the plant leak detection systems, remains stable even under accident conditions (including the Safe Shutdown Earthquake (SSE)). This concept was successfully applied to the primary loop piping of several Belgian Pressurized Water Reactor (PWR) units, operated by the Utility Electrabel. One of the main benefits is to permit justification of supports in the primary loop and justification of the integrity of the reactor pressure vessel and internals in case of a Loss Of Coolant Accident (LOCA) in stretch-out conditions. For two of the Belgian PWR units, the LBB approach also made it possible to reduce the number of large hydraulic snubbers installed on the primary coolant pumps. Last but not least, the LBB concept also facilitates the steam generator replacement operations, by eliminating the need for some pipe whip restraints located close to the steam generator. In addition to the U.S. regulatory requirements, the Belgian safety authorities impose additional requirements which are described in details in a separate paper. An novel aspect of the studies performed in Belgium is the way in which residual loads in the primary loop are taken into account. Such loads may result from displacements imposed to close the primary loop in a steam generator replacement operation, especially when it is performed using the {open_quote}two cuts{close_quotes} technique. The influence of such residual loads on the LBB margins is discussed in details and typical results are presented.

  17. A review of recent advances in the role of leak-before-break concept in assessments of flaws detected in CANDU pressure tubes

    International Nuclear Information System (INIS)

    Crespi, J.C.

    1994-01-01

    If a crack develops in a pressure tube, the leak is detected by monitoring the moisture in the gas annulus and the reactor shutdown before it becomes unstable. Because the delayed hydride cracking has been associated to date with all pressure tube failures at a rolled joints, the delayed hydride cracking is considered to be the dominant mecanism by which the flaws can grow to a size which exceeds the critical crack length. For the delayed hydride cracking failure mode leak-before-break is used as defense in depth against unstable rupture. The methodology depends on showing than the time available to detect a delayed hydride crack is much greater that the time required to detect it in the gas annulus. The time available is estimated from measurements of: (a) axial delayed hydride crack growth rates, (b) crack lengths at penetrations of the tube wall when leakage first occurs and (c) critical crack lengths at instability when a crack is growing by the delayed hydride cracking mechanism. A review of recent advances in the experimental data used in leak-before-break assessment are presented and discussed. (author). 17 refs, 6 figs, 2 tabs

  18. Study of DCRC and RCCM-MR LBB procedures

    International Nuclear Information System (INIS)

    Zhang Zhengming; Cabrillat, M.T.; Lejeail, Y.; Michel, B.

    2006-01-01

    The Leak-Before-Break (LBB) technology has been rapidly developed during the past two decades. The Design and Construction Rules Committee (DCRC) had published a document titled as 'Leak-Before-Break Procedure for Sodium boundary Components'. RCC-MR had also published a document titled as 'A16: Guide for Defect Assessment and Leak Before Break Analysis'. this paper will focus on the comparison of the above two documents. (authors)

  19. Application of Leak Before Break concept in 316LN austenitic steel pipes welded using 316L; Aplicação do conceito 1vazamento antes da falha' (Leak Before Break) em tubulações de aço 316LN soldado com metal de adição 316L

    Energy Technology Data Exchange (ETDEWEB)

    Cunto, Gabriel Giannini de

    2017-07-01

    This work presents a study of application of the Leak Before Break (LBB) concept, usually applied in nuclear power plants, in a pipe made from steel AISI type 316LN welded a coated electrode AISI type 316L. LBB concept is a criterion based on fracture mechanics analysis to show that a crack leak, present in a pipe, can be detected by leak detection systems, before this crack reaches a critical size that results in pipe fail. In the studied pipe, tensile tests and Ramberg-Osgood analyses were performed, as well as fracture toughness tests for obtaining the material resistance curve J-R. The tests were performed considering the base metal, weld and heat affected zone (HAZ), at the same operating temperatures of a nuclear power plant. For the mechanical properties found in these tests, load limit analyses were performed in order to determine the size of a crack which could cause a detectable leakage and the critical crack size, considering failure by plastic collapse. For the critical crack size found in the weld, which is the region that presented the lowest toughness, Integral J and tearing modulus T analyses were performed, considering failure by tearing instability. Results show a well-defined behavior between the base metal, HAZ and weld zones, where the base metal has a high toughness behavior, the weld has a low toughness behavior and the HAZ showed intermediate mechanical properties between the base metal and the weld. Using the PICEP software, the leak rate curves versus crack size and also the critical crack size were determined by considering load limit analysis. It was observed that after a certain crack size, the leak rate in base metal is much higher than for the HAZ and the weld, considering the same crack length. This occurs because in the base metal crack, it is expected that the crack grows in a more rounded form due to its higher toughness. The lowest critical crack size was found for the base metal presenting circumferential cracks. For the

  20. Developments in UK defect assessment procedures R6 revision 4 and BS7910

    International Nuclear Information System (INIS)

    Sharples, J.K.; Ainsworth, R.A.; Budden, P.J.

    2003-01-01

    The R6 defect assessment procedures have been developed over many years by the UK nuclear power generation industry. The procedures are updated on a regular basis, taking into account the information resulting from the R6 development programme and other available information worldwide. A major revision, Revision 4, of the R6 procedures was released in 2000. Just prior to that release, in 1999, the British Standards flaw assessment procedure BS7910 was issued and combined and updated the previous published documents PD6493 and PD6539, for components operating at temperatures where creep was negligible and important, respectively. BS79l0 is also under constant development. This paper provides a brief overview of the BS7910 and R6 Revision 4 procedures and describes updates to the respective documents since they were first issued. Some ongoing developments which will lead to future revisions to the documents are also described. (author)

  1. Corrosion in nuclear power plants and it implication in the leak before break criteria; Corrosion en centrales nucleares y su implicacion en el criterio de fuga antes de ruptura

    Energy Technology Data Exchange (ETDEWEB)

    Martinez M, E

    1992-05-15

    The corrosion in a general way can be defined like a chemical or electrochemical reaction, which is carried out in the surface of the metallic materials exposed to a specific medium. Due to the operation conditions in the nuclear power plants are practically fixed and its modification in most of the cases is difficult or expensive, the natural tendency to prevent the corrosion has been generally directed toward the selection of materials. Numerous materials have been employees as substitute of the traditional steels, among other the stabilized stainless steels, those of extra low carbon and numerous nickel base alloys. The basic evaluation that establishes the approach Leak before break (LBB) it involves the analysis by means of 'fracture mechanics' of a postulated crevice that it crosses the thickness of the material, which causes a same flight, with a margin of safety, to the detection limit that it has for a shutdown of the reactor. Due to the crevice size postulated, it cannot be established highly starting from the mechanical properties of the material since these its will be affected by the corrosion mechanisms that can settle down, it was determined that the implementation of the LBB criteria, it cannot be established for components or systems that its are susceptible of suffering corrosion. (Author)

  2. Corrosion in nuclear power plants and it implication in the leak before break criteria; Corrosion en centrales nucleares y su implicacion en el criterio de fuga antes de ruptura

    Energy Technology Data Exchange (ETDEWEB)

    Martinez M, E

    1992-05-15

    The corrosion in a general way can be defined like a chemical or electrochemical reaction, which is carried out in the surface of the metallic materials exposed to a specific medium. Due to the operation conditions in the nuclear power plants are practically fixed and its modification in most of the cases is difficult or expensive, the natural tendency to prevent the corrosion has been generally directed toward the selection of materials. Numerous materials have been employees as substitute of the traditional steels, among other the stabilized stainless steels, those of extra low carbon and numerous nickel base alloys. The basic evaluation that establishes the approach Leak before break (LBB) it involves the analysis by means of 'fracture mechanics' of a postulated crevice that it crosses the thickness of the material, which causes a same flight, with a margin of safety, to the detection limit that it has for a shutdown of the reactor. Due to the crevice size postulated, it cannot be established highly starting from the mechanical properties of the material since these its will be affected by the corrosion mechanisms that can settle down, it was determined that the implementation of the LBB criteria, it cannot be established for components or systems that its are susceptible of suffering corrosion. (Author)

  3. Probabilistic assessment of leak-before-break

    International Nuclear Information System (INIS)

    Bush, S.H.

    1984-01-01

    A summary of results illustrating what might be derived from a probabilistic risk assessment (PRA) study follows. The failure probabilities for larger sizes of nuclear piping are considered to be in the range of 10 -4 to 10 -6 per reactor-year (exclusive of intergranular stress corrosion cracking (IGSCC). Smaller pipe sizes, of lesser safety significance, have much higher failure rates. In BWRs, IGSCC can cause failure rates much higher than 10 -4 in piping 4 to 10 in. in size. Suggested failure mechanisms apply in most instances, exclusive of IGSCC. Catastrophic failures would appear more likely from operator error or design and construction errors (water hammer, improper handling of dynamic loads, and undetected fabrication defects) rather than conventional flaw initiation and growth by fatigue

  4. Qualification of PHT piping of Indian 500 MW PHWR for LBB, using R-6 method

    International Nuclear Information System (INIS)

    Rastogi, Rohit; Bhasin, V.; Kushwaha, H.S.

    1997-01-01

    This document discusses the qualification of straight pipe portion of the primary heat transport (PHT) piping of Indian 500 MWe pressurised heavy water reactor (PHWR) for leak before break (LBB). The evaluation is done using R-6 [1] method. The results presented here are: the safety margins which exist on straight pipe components of main PHT piping of 500 MWe, under leakage size crack (LSC) and design basis accident loads; the sensitivity of safety margins with respect to different analysis parameters and the qualification of PHT piping for LBB based on criterion given by NUREG-1061 [2] and TECDOC-774 [3]. (author)

  5. Evaluation procedure of creep-fatigue defect growth in high temperature condition and application

    International Nuclear Information System (INIS)

    Park, Chang Gyu; Kim, Jong Bum; Lee, Jae Han

    2003-12-01

    This study proposed the evaluation procedure of creep-fatigue defect growth on the high-temperature cylindrical structure applicable to the KALIMER, which is developed by KAERI. Parameters used in creep defect growth and the evaluation codes with these parameters were analyzed. In UK, the evaluation procedure of defect initiation and growth were proposed with R5/R6 code. In Japan, simple evauation method was proposed by JNC. In France, RCC-MR A16 code which was evaluation procedure of the creep-fatigue defect initiation and growth related to leak before break was developed, and equations related to load conditions were modified lately. As an application example, the creep-fatigue defect growth on circumferential semi-elliptical surface defect in high temperature cylindrical structure was evaluated by RCC-MR A16

  6. Structural integrity of LMFBRs including leak before break

    International Nuclear Information System (INIS)

    Vinzens, K.; Laue, H.; Hosemann, B.

    1990-01-01

    Th German Basis Safety Concept is an approach which allows the possibility of catastrophic failures to be excluded. It was developed in Germany to render the probabilistic approach unnecessary for safety cases relating to nuclear power plants. The process of evaluation started in 1972, and in 1979 the Basis Safety Concept was officially published and thus became a legal requirement for LWR plants. With appropriate modifications in regard of the particular features of LMFBR, this concept has also been applied to SNR 300. The 'Structural Integrity Demonstration Concept' of SNR 300 is based on five principles: Principle of quality by design and fabrication, Principle of multiple examination, Principle of worst case consideration, Principle of operating surveillance and documentation, Principle of verification and continuous development. The same principles are taken over for SNR 2. The specific requirements on the components relevant to safety have to be defined at an early stage so that the components can be designed appropriately to the feasibility of the measures required by the concept. (orig.)

  7. Theory and verification manual for BARC-R6 software

    International Nuclear Information System (INIS)

    Rastogi, Rohit; Bhasin, Vivek; Vaze, K.K.; Kushwaha, H.S.

    2001-01-01

    This report presents the technical description of the BARC-R6 computer code that has been developed in Reactor Safety Division, BARC. The program has been designed to run on Windows95 based PCs. The R6 method is a tool, which can perform analysis considering fracture and plastic instability together as failure criteria. The R6 method for analyzing flawed components requires construction of number of graphs. The results of study are arrived at by analyzing these graphs. BARC- R6 is designed with a highly intuitive graphical user interface for input as well as output. This report presents the implementation details of the program. The current version has provision for any flaw orientation and type in pipes and elbows. This program will be highly useful for fracture assessment and Leak Before Break (LBB) qualification for Nuclear Power Plant (NPP) piping. The complete PHT piping of any typical NPP can be assessed with in a very short time. It is capable of handling Option-1 and Option-2 Failure Assessment Line (FAL) for both Category-1 and Category-3 type analysis. It has provision for exhaustive sensitivity analyses for judging the significance of margins with respect to variation in material properties, crack sizes etc. The report is divided into 6 sections. The first section introduces the document. The details offer method are presented in the second section. This is followed by the technical description of the program. The fourth section lists many benchmark problems solved to highlight its usage and validation. These benchmark problems cover the wide range of cases encountered in the practical situations. The user manual is provided in the fifth section. The sixth section contains the references used in this report. This is followed by an appendix containing the co-relations for stress intensity factor and limit loads, used in the BARC-R6 code. (author)

  8. Advanced structural integrity assessment procedures. Working material

    International Nuclear Information System (INIS)

    1994-01-01

    The purpose of the meeting was to provide an international forum for discussion on recent results in research and utility practice in the field of methodology for the structural integrity assessment of components including relevant non-codified procedures. The scope of the meeting included deterministic and probabilistic approaches. The papers covered the following topics: Leak-before-break concepts; non-destructive examination (NDE) and surveillance results; statistical evaluation of non-destructive examination data; pressurized thermal shock evaluation; fatigue effects (including vibration); and verification qualification. The meeting was attended by 32 specialists from 8 countries. Refs, figs and tabs

  9. Leak-before-break due to fatigue cracks in the cold leg piping system

    International Nuclear Information System (INIS)

    Mayfield, M.E.; Collier, R.P.

    1984-01-01

    This review paper presents the results of a deterministic assessment of the margin of safety against a large break in the cold leg piping system of pressurized water reactors. The paper focuses on the computation of leak rates resulting from fatigue cracks that penetrate the full wall thickness. Results are presented that illustrate the sensitivity of the leak rate to stress level, crack shape and crack orientation. Further, the leak rates for specific conditions are contrasted to detection levels, shutdown criteria, make-up capacity and the leak rate associated with final failure of the piping system. The results of these computations indicate that, in general, leaks far in excess of the present detection sensitivities would result at crack sizes well below the critical crack sizes for the upset loadings on the cold leg piping system

  10. Leak detection systems for VVER units based on leak before break concept. PowerPoint presentation

    International Nuclear Information System (INIS)

    Matal, Oldrich

    2010-01-01

    To comply with international standards, independent leak monitoring systems should be installed based on the monitoring of different physical parameters capable of detecting any small leak within one hour from the start of the leak. Such leak detection systems are based mainly on acoustic emission monitoring, humidity monitoring and/or radiation monitoring. Advanced systems integrate the monitoring of different physical parameters into one integrated leak detection system. The Integrated Leak Detection System (ILDS) for NPP Metsamor is described. This system consists of three independent leak detection subsystems, viz. LEMOP (LEak MOnitoring of Pipelines) based on acoustic emission monitoring, HUMOS (HUmidity MOnitoring System) based on humidity monitoring, and RAMOS (RAdiation MOnitoring System) based on radiation monitoring). The Integrated Leak Detection System (ILDS) collects data from the three systems, performs data evaluation, data storage, generates alarms and provides a user interface for the whole system including all subsystems. An example of DiagAssist user interface in the ILDS system in the pictorial form. (P.A.)

  11. Fast reactor sodium systems operation experience and 'leak-before-break' criterion

    International Nuclear Information System (INIS)

    Ivanenko, V.N.; Zybin, V.A.

    1996-01-01

    In the paper sodium leakage detection systems used at fast reactors are described. Requirements on their main characteristics (sensitivity, response lime) are formulated. Results of tests are presented on studying the parameters of sodium leak detection systems including experiments on the measurement of size distribution of aerosol particles that have passed through sodium systems thermal insulation after leak initiation. Comparison of these data with dispersion of particles formed at free burning is carried out. Experience of real leaks that occurred at fast reactor sodium systems is analyzed. It has been shown that initiation and development of real leaks do not always follow the theoretical scheme. A substantial role of human factor for sodium systems reliability relative to sodium leaks is stressed. (author)

  12. Leak before break analysis for cracking at multiple weld locations in BWR recirculation piping

    International Nuclear Information System (INIS)

    Zahoor, A.; Gamble, R.

    1984-01-01

    Periodically over the past decade, intergranular stress corrosion cracking (IGSCC) has been found in austenitic stainless steel piping at Boiling Water Reactor facilities. The effect of IGSCC on piping integrity has been evaluated previously in various BWR Owners Group and NRC studies. In these studies, the analyses were performed assuming the presence of a crack at a single weld location in the pipe run. The purpose of this investigation was to compare the leak rate and potential for unstable crack extension associated with a throughwall crack for the following two conditions in a BWR recirculation system: (1) the recirculation piping contains part through cracks at multiple weld locations and a single throughwall crack, and (2) the piping contains only a throughwall crack at one weld location. Two type BWRs were evaluated; namely, the ring header and five individual loop designs. The results from the analyses indicate that the potential for unstable crack extension at large bending loads, and leak rate at normal operation are not affected by the presence of part through cracks at multiple weld locations. The differences in the respective calculated L/sub eff/ and leak rates for the single and multiply cracked conditions are less than 2%

  13. Verification of failure avoidance concepts in R6 Rev3

    International Nuclear Information System (INIS)

    Milne, I.; Knee, N.

    1988-09-01

    The first part of this Report outlines how recent developments in fracture mechanics have led to a more accurate interpretation of the two-criteria approach to defect assessment. The implementation of these developments into Revision 3 of the Central Electricity Generating Board code of practice for the assessment of the defect tolerance of structures (R6) is described. One of the key elements of the revised version is the recommendation that the failure assessment line should be derived from the actual tensile stress/strain properties of the material. The second part of the Report addresses the validation of the method, which is a crucial step on the way to obtaining acceptance of R6 by, in particular, the regulatory bodies. The range of structures used to validate the procedure is illustrated by two examples. The use of conservative data and assumptions is fundamental to the R6 philosophy, which means that the procedure should not be used as a predictive tool. In the second example the importance of making these conservative assumptions is clearly illustrated. (author)

  14. Elastic-plastic fracture analysis of carbon steel piping using the latest CEGB R6 approach

    International Nuclear Information System (INIS)

    Kanno, S.; Hasegawa, K.; Shimizu, T.; Kobayashi, H.

    1991-01-01

    The elastic-plastic fracture of carbon steel piping having various pipe diameters and circumferential crack angles and subjected to a bending moment is analyzed using the latest United Kingdom Central Electricity Generating Board R6 approach. The elastic-plastic fracture criterion must be applied instead of the plastic collapse criterion with increase of the pipe diameter and the crack angle. A simplified elastic-plastic fracture analysis procedure based on the R6 approach is proposed. (author)

  15. Guidance for the application of the leak before break concept. Report of the IAEA extrabudgetary programme on the safety of WWER-440 model 230 nuclear power plants

    International Nuclear Information System (INIS)

    1994-11-01

    This document provides additional guidance on application of the LBB concept to WWER-440/230 NPPs and complements the IAEA-TECDOC-710. The objective of the report is to describe in detail the elements of the LBB concept, the necessary support as well as the condition to be fulfilled, and the verification programme. It should also provide a clear picture of all the activities and resources needed to implement the LBB successfully as a comprehensive concept

  16. Application of leak-before-break to primary loop piping to eliminate pipe whip restraints in a Spanish nuclear power plant

    International Nuclear Information System (INIS)

    Rodriguez, M.; Esteban, A.

    1990-01-01

    The Spanish plant described in this study is a 982 MWe PWR with a three-loop primary circuit of piping made from centrifugally-cast stainless steel SA351 CF8A. The licensee requested from Consejo de Seguridad Nuclear (CSN) an exemption from the general design criterion, GDC-4, so as to avoid the need to postulate a guillotine rupture of the primary loop piping. The request was based on the generic work performed for a US PWR plant group in order to have such an exemption. As the piping material in the Spanish plant is different from that in the plants included in the generic work, CSN performed a review of the applicability of the generic results to the Spanish plant. Also, aspects such as fatigue evaluation, net section collapse, crack growth and leak detection, specifically analyzed for the Spanish plant, were reviewed. CSN found that fracture toughness test results from generic work are applicable to the Spanish plant; sufficient margin exists against unstable crack extension, and adequate leak detection capability exists with the leakage detection systems available in the plant. Exemption from GDC-4 was approved and CSN authorized the licensee to remove protection devices against dynamic loads from guillotine breaks in the primary coolant loops. (author)

  17. Comparison of R6 and A16 J estimation methods under combined mechanical and thermal loads with FE results

    International Nuclear Information System (INIS)

    Nam, Hyun-Suk; Oh, Chang-Young; Kim, Yun-Jae; Jerng, Dong Wook; Ainsworth, Robert A.; Budden, Peter J.; Marie, Stéphane

    2015-01-01

    This paper compares elastic–plastic values of J calculated using the methods in the UK R6 and the French A16 fitness-for-service procedures with FE results for a vessel with a circumferential surface crack under axial tension and a radial thermal gradient. In the FE analyses, the relative magnitudes and loading sequence of mechanical and thermal loads are systematically varied, together with the material strain hardening exponent. Fully circumferential and semi-elliptical surface crack with two relative crack depths are considered. It is found that the R6 estimates are overall accurate but can be non-conservative at large L_r. The A16 estimates are more conservative than the R6 estimates at small L_r but are conservative even at large L_r. Possible sources of conservatism and non-conservatism in R6 and A16 are discussed. - Highlights: • Accuracy of existing J estimation methods for combined mechanical and thermal loading are compared with FE results. • The methods in the UK R6 and the French A16 procedures are considered. • The R6 estimates are overall accurate but can be non-conservative at large L_r. • The A16 estimates are more conservative than the R6 estimates at small L_r but are conservative even at large L_r. • Possible sources of conservatism and non-conservatism in R6 and A16 are discussed.

  18. R6 assessment of IPIRG-2 programme experiments

    International Nuclear Information System (INIS)

    Sharples, J.K.; France, C.C.; Budden, P.J.

    1999-01-01

    The International Piping Integrity Research Group (IPIRG) Programme was an international group programme managed by the US Nuclear Regulatory Commission (US NRC) and was aimed at developing a better understanding of the fracture behaviour of pressurised nuclear plant piping The second stage IPIRG experiments (IPIRG-2) included the development of data for the verification of fracture analyses for cracked pipes and fittings subjected to dynamic and/or cyclic load histories. This paper describes the results of work undertaken on analysing selected IPIRG-2 experiments using the UK R6 fracture assessment methodology. The level of conservatism of the R6 methodology is presented by comparing predicted applied bending moments at initiation and instability with the experimentally determined values. (author)

  19. R6 validation exercise: through thickness residual stress measurements on an experiment test vessel ring

    International Nuclear Information System (INIS)

    Mitchell, D.H.

    1988-06-01

    A series of bursting tests on thick-walled pressure vessels has been carried out as part of a validation exercise for the CEGB R6 failure assessment procedure. The objective of these tests was the examination of the behaviour of typical PWR primary vessel material subject to residual stresses in addition to primary loading with particular reference to the R6 assessment procedure. To this end, a semi-elliptic part-through defect was sited in the vessel longitudinal seam, which was a submerged arc weld in the non stress-relieved condition; it was then pressure tested to failure. Prior to the final assembly of this vessel, a ring of material was cut from it to act as a test-piece on which a residual stress survey could be made. Surface measurements using the centre-hole technique were made by CERL personnel, and this has been followed by two through- thickness measurements at BNL using the deep-hole technique. This paper describes these deep-hole measurements and presents the results from them. (author)

  20. Probabilistic fracture failure analysis of nuclear piping containing defects using R6 method

    International Nuclear Information System (INIS)

    Lin, Y.C.; Xie, Y.J.; Wang, X.H.

    2004-01-01

    Failure analysis of in-service nuclear piping containing defects is an important subject in the nuclear power plants. Considering the uncertainties in various internal operating loadings and external forces, including earthquake and wind, flaw sizes, material fracture toughness and flow stress, this paper presents a probabilistic assessment methodology for in-service nuclear piping containing defects, which is especially designed for programming. A general sampling computation method of the stress intensity factor (SIF), in the form of the relationship between the SIF and the axial force, bending moment and torsion, is adopted in the probabilistic assessment methodology. This relationship has been successfully used in developing the software, Safety Assessment System of In-service Pressure Piping Containing Flaws (SAPP-2003), based on a well-known engineering safety assessment procedure R6. A numerical example is given to show the application of the SAPP-2003 software. The failure probabilities of each defect and the whole piping can be obtained by this software

  1. Fracture mechanical evaluation of high temperature structure and creep-fatigue defect assessment

    Energy Technology Data Exchange (ETDEWEB)

    Park, Chang Gyu; Kim, Jong Bum; Lee, Jae Han

    2004-02-01

    This study proposed the evaluation procedure of high temperature structures from the viewpoint of fracture mechanics on the cylindrical structure applicable to the KALIMER, which is developed by KAERI. For the evaluation of structural integrity, linear and non-linear fracture mechanics parameters were analyzed. Parameters used in creep defect growth applicable to high temperature structure of liquid metal reactor and the evaluation codes with these parameters were analyzed. The evaluation methods of defect initiation and defect growth which were established in R5/R6 code(UK), JNC method (Japan) and RCC-MR A16(France) code were analyzed respectively. The evaluation procedure of leak before break applicable to KALIMER was preliminarily developed and proposed. As an application example of defect growth, the creep-fatigue defect growth on circumferential throughwall defect in high temperature cylindrical structure was evaluated by RCC-MR A16 and this application technology was established.

  2. Surface-enhanced resonance Raman scattering spectroscopy of single R6G molecules

    Institute of Scientific and Technical Information of China (English)

    Zhou Zeng-Hui; Liu Li; Wang Gui-Ying; Xu Zhi-Zhan

    2006-01-01

    Surface-enhanced resonance Raman scattering (SERRS) of Rhodamine 6G (R6G) adsorbed on colloidal silver clusters has been studied. Based on the great enhancement of the Raman signal and the quench of the fluorescence, the SERRS spectra of R6G were recorded for the samples of dye colloidal solution with different concentrations. Spectral inhomogeneity behaviours from single molecules in the dried sample films were observed with complementary evidences, such as spectral polarization, spectral diffusion, intensity fluctuation of vibrational lines and even "breathing" of the molecules. Sequential spectra observed from a liquid sample with an average of 0.3 dye molecules in the probed volume exhibited the expected Poisson distribution for actually measuring 0, 1 or 2 molecules. Difference between the SERRS spectra of R6G excited by linearly and circularly polarized light were experimentally measured.

  3. Ionic fluids with r-6 pair interactions have power-law electrostatic screening

    International Nuclear Information System (INIS)

    Kjellander, Roland; Forsberg, Bjoern

    2005-01-01

    The decay behaviour of radial distribution functions for large distances r is investigated for classical Coulomb fluids where the ions interact with an r -6 potential (e.g. a dispersion interaction) in addition to the Coulombic and the short-range repulsive potentials (e.g. a hard core). The pair distributions and the density-density (NN), charge-density (QN) and charge-charge (QQ) correlation functions are investigated analytically and by Monte Carlo simulations. It is found that the NN correlation function ultimately decays like r -6 for large r, just as it does for fluids of electroneutral particles interacting with an r -6 potential. The prefactor is proportional to the squared compressibility in both cases. The QN correlations decay in general like r -8 and the QQ correlations like r -10 in the ionic fluid. The average charge density around an ion decays generally like r -8 and the average electrostatic potential like r -6 . This behaviour is in stark contrast to the decay behaviour for classical Coulomb fluids in the absence of the r -6 potential, where all these functions decay exponentially for large r. The power-law decays are, however, the same as for quantum Coulomb fluids. This indicates that the inclusion of the dispersion interaction as an effective r -6 interaction potential in classical systems yields the same decay behaviour for the pair correlations as in quantum ionic systems. An exceptional case is the completely symmetric binary electrolyte for which only the NN correlation has a power-law decay but not the QQ correlations. These features are shown by an analysis of the bridge function

  4. Adaptation to experimental jet-lag in R6/2 mice despite circadian dysrhythmia.

    Directory of Open Access Journals (Sweden)

    Nigel I Wood

    Full Text Available The R6/2 transgenic mouse model of Huntington's disease (HD shows a disintegration of circadian rhythms that can be delayed by pharmacological and non-pharmacological means. Since the molecular machinery underlying the circadian clocks is intact, albeit progressively dysfunctional, we wondered if light phase shifts could modulate the deterioration in daily rhythms in R6/2 mice. Mice were subjected to four x 4 hour advances in light onset. R6/2 mice adapted to phase advances, although angles of entrainment increased with age. A second cohort was subjected to a jet-lag paradigm (6 hour delay or advance in light onset, then reversal after 2 weeks. R6/2 mice adapted to the original shift, but could not adjust accurately to the reversal. Interestingly, phase shifts ameliorated the circadian rhythm breakdown seen in R6/2 mice under normal LD conditions. Our previous finding that the circadian period (tau of 16 week old R6/2 mice shortens to approximately 23 hours may explain how they adapt to phase advances and maintain regular circadian rhythms. We tested this using a 23 hour period light/dark cycle. R6/2 mice entrained to this cycle, but onsets of activity continued to advance, and circadian rhythms still disintegrated. Therefore, the beneficial effects of phase-shifting are not due solely to the light cycle being closer to the tau of the mice. Our data show that R6/2 mice can adapt to changes in the LD schedule, even beyond the age when their circadian rhythms would normally disintegrate. Nevertheless, they show abnormal responses to changes in light cycles. These might be caused by a shortened tau, impaired photic re-synchronization, impaired light detection and/or reduced masking by evening light. If similar abnormalities are present in HD patients, they may suffer exaggerated jet-lag. Since the underlying molecular clock mechanism remains intact, light may be a useful treatment for circadian dysfunction in HD.

  5. Altered dopamine and serotonin metabolism in motorically asymptomatic R6/2 mice.

    Directory of Open Access Journals (Sweden)

    Fanny Mochel

    Full Text Available The pattern of cerebral dopamine (DA abnormalities in Huntington disease (HD is complex, as reflected by the variable clinical benefit of both DA antagonists and agonists in treating HD symptoms. In addition, little is known about serotonin metabolism despite the early occurrence of anxiety and depression in HD. Post-mortem enzymatic changes are likely to interfere with the in vivo profile of biogenic amines. Hence, in order to reliably characterize the regional and chronological profile of brain neurotransmitters in a HD mouse model, we used a microwave fixation system that preserves in vivo concentrations of dopaminergic and serotoninergic amines. DA was decreased in the striatum of R6/2 mice at 8 and 12 weeks of age while DA metabolites, 3-methoxytyramine and homovanillic acid, were already significantly reduced in 4-week-old motorically asymptomatic R6/2 mice. In the striatum, hippocampus and frontal cortex of 4, 8 and 12-week-old R6/2 mice, serotonin and its metabolite 5-hydroxyindoleacetic acid were significantly decreased in association with a decreased turnover of serotonin. In addition, automated high-resolution behavioural analyses displayed stress-like behaviours such as jumping and grooming and altered spatial learning in R6/2 mice at age 4 and 6 weeks respectively. Therefore, we describe the earliest alterations of DA and serotonin metabolism in a HD murine model. Our findings likely underpin the neuropsychological symptoms at time of disease onset in HD.

  6. Unraveling the symmetry ambiguity in a hexamer: Calculation of the R6 human insulin structure

    International Nuclear Information System (INIS)

    O'Donoghue, Sean I.; Chang Xiaoqing; Abseher, Roger; Nilges, Michael; Led, Jens J.

    2000-01-01

    Crystallographic and NMR studies of insulin have revealed a highly flexible molecule with a range of different aggregation and structural states; the importance of these states for the function of the hormone is still unclear. To address this question, we have studied the solution structure of the insulin R 6 symmetric hexamer using NMR spectroscopy. Structure determination of symmetric oligomers by NMR is complicated due to 'symmetry ambiguity' between intra- and intermonomer NOEs, and between different classes of intermonomer NOEs. Hence, to date, only two symmetric tetramers and one symmetric pentamer (VTB, B subunit of verotoxin) have been solved by NMR; there has been no other symmetric hexamer or higher-order oligomer. Recently, we reported a solution structure for R 6 insulin hexamer. However, in that study, a crystal structure was used as a reference to resolve ambiguities caused by the threefold symmetry; the same method was used in solving VTB. Here, we have successfully recalculated R 6 insulin using the symmetry-ADR method, a computational strategy in which ambiguities are resolved using the NMR data alone. Thus the obtained structure is a refinement of the previous R 6 solution structure. Correlated motions in the final structural ensemble were analysed using a recently developed principal component method; this suggests the presence of two major conformational substates. The study demonstrates that the solution structure of higher-order symmetric oligomers can be determined unambiguously from NMR data alone, using the symmetry-ADR method. This success bodes well for future NMR studies of higher-order symmetric oligomers. The correlated motions observed in the structural ensemble suggest a new insight into the mechanism of phenol exchange and the T 6 ↔ R 6 transition of insulin in solution

  7. Partial synthesis of (3R,6'R)-alpha-cryptoxanthin and (3R)-beta-cryptoxanthin from (3R,3'R,6'R)-lutein.

    Science.gov (United States)

    Khachik, Frederick; Chang, An-Ni; Gana, Audry; Mazzola, Eugene

    2007-02-01

    (3R,3'R,6'R)-Lutein (1), (3R,3'R)-zeaxanthin (2), (3R,6'R)-alpha-cryptoxanthin (3), and (3R)-beta-cryptoxanthin (4) are among dietary hydroxycarotenoids that have been identified in human serum, milk, and ocular tissues. While 1 containing 6% of 2 is commercially available, industrial production of optically active 3 and 4 has not yet been accomplished. Several processes have been developed that transform 1 into 3, 4, and minor quantities of (3R,5'RS,6'R)-3',4'-didehydro-5',6'-dihydro-beta,beta-caroten-3-ol (5) (a regioisomer of 3). In one process, lutein (1) was cleanly deoxygenated to 3 in the presence of trifluoroacetic acid (TFA) and Me3N.BH3 in CH2Cl2 at ambient temperature in nearly 90% yield. Reaction of lutein (1) with a Lewis acid (AlCl3, ZnBr2, ZnI2) and a hydride donor (Me3N.BH3, Na[BH3(OCOCF3)], NaCNBH3) in solvents such as CH2Cl2, THF, and TBME produced similar results. In a two-step process, high-temperature acid-catalyzed dehydration of 1 (propanol/water/acid, 90 degrees C) gave a mixture of anhydroluteins 6, 7, and 8 in 86% yield. In the second step, these dehydration products underwent ionic hydrogenation with TFA/Me3N.BH3 in CH2Cl2 to afford a mixture of 3 and 4 in nearly 80% yield that contained only 1% of 5.

  8. 26 CFR 1.414(r)-6 - Qualified separate line of business-administrative scrutiny requirement-individual determinations.

    Science.gov (United States)

    2010-04-01

    ...-administrative scrutiny requirement-individual determinations. 1.414(r)-6 Section 1.414(r)-6 Internal Revenue... Pension, Profit-Sharing, Stock Bonus Plans, Etc. § 1.414(r)-6 Qualified separate line of business... determined under § 1.414(r)-3) that does not satisfy any of the safe harbors in § 1.414(r)-5 for a testing...

  9. R6/2 Huntington's disease mice develop early and progressive abnormal brain metabolism and seizures.

    Science.gov (United States)

    Cepeda-Prado, Efrain; Popp, Susanna; Khan, Usman; Stefanov, Dimitre; Rodríguez, Jorge; Menalled, Liliana B; Dow-Edwards, Diana; Small, Scott A; Moreno, Herman

    2012-05-09

    A hallmark feature of Huntington's disease pathology is the atrophy of brain regions including, but not limited to, the striatum. Though MRI studies have identified structural CNS changes in several Huntington's disease (HD) mouse models, the functional consequences of HD pathology during the progression of the disease have yet to be investigated using in vivo functional MRI (fMRI). To address this issue, we first established the structural and functional MRI phenotype of juvenile HD mouse model R6/2 at early and advanced stages of disease. Significantly higher fMRI signals [relative cerebral blood volumes (rCBVs)] and atrophy were observed in both age groups in specific brain regions. Next, fMRI results were correlated with electrophysiological analysis, which showed abnormal increases in neuronal activity in affected brain regions, thus identifying a mechanism accounting for the abnormal fMRI findings. [(14)C] 2-deoxyglucose maps to investigate patterns of glucose utilization were also generated. An interesting mismatch between increases in rCBV and decreases in glucose uptake was observed. Finally, we evaluated the sensitivity of this mouse line to audiogenic seizures early in the disease course. We found that R6/2 mice had an increased susceptibility to develop seizures. Together, these findings identified seizure activity in R6/2 mice and show that neuroimaging measures sensitive to oxygen metabolism can be used as in vivo biomarkers, preceding the onset of an overt behavioral phenotype. Since fMRI-rCBV can also be obtained in patients, we propose that it may serve as a translational tool to evaluate therapeutic responses in humans and HD mouse models.

  10. Pappas' scheme of correlating R6 and R4 co-ordinate transformations

    International Nuclear Information System (INIS)

    Teli, M.T.

    1984-01-01

    Pappas has suggested that R 4 co-ordinates can be connected with those in the R 6 by taking t'sub(x)=t'sub(y)=t'sub(z)=t'. Such connection is here obtained by introducing the scaling of space-time co-ordinates xsub(i), tsub(i) in all the frames by the corresponding factor c/c'sub(i) and have shown that taking of t'sub(x)=t'sub(y)=t'sub(z)=t' for this purpose is not necessary. The scaling factors get ignored after the connection

  11. PARP-1 Inhibition Is Neuroprotective in the R6/2 Mouse Model of Huntington's Disease.

    Directory of Open Access Journals (Sweden)

    Antonella Cardinale

    Full Text Available Poly (ADP-ribose polymerase 1 (PARP-1 is a nuclear enzyme that is involved in physiological processes as DNA repair, genomic stability, and apoptosis. Moreover, published studies demonstrated that PARP-1 mediates necrotic cell death in response to excessive DNA damage under certain pathological conditions. In Huntington's disease brains, PARP immunoreactivity was described in neurons and in glial cells, thereby suggesting the involvement of apoptosis in HD. In this study, we sought to determine if the PARP-1 inhibitor exerts a neuroprotective effect in R6/2 mutant mice, which recapitulates, in many aspects, human HD. Transgenic mice were treated with the PARP-1 inhibitor INO-1001 mg/Kg daily starting from 4 weeks of age. After transcardial perfusion, histological and immunohistochemical studies were performed. We found that INO 1001-treated R6/2 mice survived longer and displayed less severe signs of neurological dysfunction than the vehicle treated ones. Primary outcome measures such as striatal atrophy, morphology of striatal neurons, neuronal intranuclear inclusions and microglial reaction confirmed a neuroprotective effect of the compound. INO-1001 was effective in significantly increasing activated CREB and BDNF in the striatal spiny neurons, which might account for the beneficial effects observed in this model. Our findings show that PARP-1 inhibition could be considered as a valid therapeutic approach for HD.

  12. Progressive Impairment of Lactate-based Gluconeogenesis in the Huntington's Disease Mouse Model R6/2

    DEFF Research Database (Denmark)

    Nielsen, Signe Marie Borch; Hasholt, Lis; Nørremølle, Anne

    2015-01-01

    of impairment of lactate-based hepatic gluconeogenesis in the transgenic HD mouse model R6/2 and determine that the defect manifests very early and progresses in severity with disease development, indicating a potential to explore this defect in a biomarker context. Moreover, R6/2 animals displayed lower blood...

  13. Distribution and characterization of Podosphaera macularis virulent on hop cultivars possessing R6-based resistance to powdery mildew

    Science.gov (United States)

    In 2012, an epidemic of powdery mildew occurred in Washington and Idaho on previously resistant cultivars whose resistance was putatively based on the gene designated R6. In 2013, isolates capable of causing severe disease on cultivars with R6-based resistance were confirmed in Oregon and became wid...

  14. The interaction between AMPKβ2 and the PP1-targeting subunit R6 is dynamically regulated by intracellular glycogen content.

    Science.gov (United States)

    Oligschlaeger, Yvonne; Miglianico, Marie; Dahlmans, Vivian; Rubio-Villena, Carla; Chanda, Dipanjan; Garcia-Gimeno, Maria Adelaida; Coumans, Will A; Liu, Yilin; Voncken, J Willem; Luiken, Joost J F P; Glatz, Jan F C; Sanz, Pascual; Neumann, Dietbert

    2016-04-01

    AMP-activated protein kinase (AMPK) is a metabolic stress-sensing kinase. We previously showed that glucose deprivation induces autophosphorylation of AMPKβ at Thr-148, which prevents the binding of AMPK to glycogen. Furthermore, in MIN6 cells, AMPKβ1 binds to R6 (PPP1R3D), a glycogen-targeting subunit of protein phosphatase type 1 (PP1), thereby regulating the glucose-induced inactivation of AMPK. In the present study, we further investigated the interaction of R6 with AMPKβ and the possible dependency on Thr-148 phosphorylation status. Yeast two-hybrid (Y2H) analyses and co-immunoprecipitation (IP) of the overexpressed proteins in human embryonic kidney (HEK) 293T) cells revealed that both AMPKβ1 and AMPK-β2 wild-type (WT) isoforms bind to R6. The AMPKβ-R6 interaction was stronger with the muscle-specific AMPKβ2-WT and required association with the substrate-binding motif of R6. When HEK293T cells or C2C12 myotubes were cultured in high-glucose medium, AMPKβ2-WT and R6 weakly interacted. In contrast, glycogen depletion significantly enhanced this protein interaction. Mutation of AMPKβ2 Thr-148 prevented the interaction with R6 irrespective of the intracellular glycogen content. Treatment with the AMPK activator oligomycin enhanced the AMPKβ2-R6 interaction in conjunction with increased Thr-148 phosphorylation in cells grown in low-glucose medium. These data are in accordance with R6 binding directly to AMPKβ2 when both proteins detach from the diminishing glycogen particle, which is simultaneous with increased AMPKβ2 Thr-148 autophosphorylation. Such a model points to a possible control of AMPK by PP1-R6 upon glycogen depletion in muscle. © 2016 Authors; published by Portland Press Limited.

  15. 海马神经元中TAT-GluR6-9c-dansyl小肽的荧光观察%Delivery of GluR6-9c into hippocampal neurons by TAT transduction domain

    Institute of Scientific and Technical Information of China (English)

    纵艳艳; 裴冬生; 孙亚峰; 张光毅

    2005-01-01

    目的研究TAT-GluR6-9c-dansyl荧光小肽是否可以进入细胞内部.方法在培养的海马神经元中加入TAT-GluR6-9c-dansyl荧光小肽和对照肽TAT38-48-dansyl.结果用10 μmol/L TAT-GluR6-9c-dansyl处理的海马神经元在荧光显微镜下可以观到绿色荧光的出现,而对照肽TAT38-48-dansyl无荧光出现.结论 TAT-GluR6-9c-dansyl荧光小肽可以进入细胞.

  16. Mitochondrial cristae remodelling is associated with disrupted OPA1 oligomerisation in the Huntington's disease R6/2 fragment model.

    Science.gov (United States)

    Hering, Tanja; Kojer, Kerstin; Birth, Nathalie; Hallitsch, Jaqueline; Taanman, Jan-Willem; Orth, Michael

    2017-02-01

    There is evidence of an imbalance of mitochondrial fission and fusion in patients with Huntington's disease (HD) and HD animal models. Fission and fusion are important for mitochondrial homeostasis including mitochondrial DNA (mtDNA) maintenance and may be relevant for the selective striatal mtDNA depletion that we observed in the R6/2 fragment HD mouse model. We aimed to investigate the fission/fusion balance and the integrity of the mitochondrial membrane system in cortex and striatum of end-stage R6/2 mice and wild-type animals. Mitochondrial morphology was determined using electron microscopy, and transcript and protein levels of factors that play a key role in fission and fusion, including DRP1, mitofusin 1 and 2, mitofilin and OPA1, and cytochrome c and caspase 3 were assessed by RT-qPCR and immunoblotting. OPA1 oligomerisation was evaluated using blue native gels. In striatum and cortex of R6/2 mice, mitochondrial cristae morphology was abnormal. Mitofilin and the overall levels of the fission and fusion factors were unaffected; however, OPA1 oligomerisation was abnormal in striatum and cortex of R6/2 mice. Mitochondrial and cytoplasmic cytochrome c levels were similar in R6/2 and wild-type mice with no significant increase of activated caspase 3. Our results indicate that the integrity of the mitochondrial cristae is compromised in striatum and cortex of the R6/2 mice and that this is most likely caused by impaired OPA1 oligomerisation. Copyright © 2016 Elsevier Inc. All rights reserved.

  17. Characterization of somatostatin receptors and associated signaling pathways in pancreas of R6/2 transgenic mice.

    Science.gov (United States)

    Somvanshi, Rishi K; Jhajj, Amrit; Heer, Michael; Kumar, Ujendra

    2018-02-01

    The present study describes the status of somatostatin receptors (SSTRs) and their colocalization with insulin (β), glucagon (α) and somatostatin (δ) producing cells in the pancreatic islets of 11weeks old R6/2 Huntington's Disease transgenic (HD tg) and age-matched wild type (wt) mice. We also determined expression of tyrosine hydroxylase (TH), glutamic acid decarboxylase (GAD) and presynaptic marker synaptophysin (SYP) in addition to signal transduction pathways associated with diabetes. In R6/2 mice, islets are relatively smaller in size, exhibit enhanced expression and nuclear inclusion of mHtt along with the loss of insulin, glucagon and somatostatin expression. In comparison to wt, R6/2 mice display enhanced mRNA for all SSTRs except SSTR2. In the pancreatic lysate, SSTR1, 4 and 5 immunoreactivity decreases whereas SSTR3 immunoreactivity increases with no discernible changes in SSTR2 immunoreactivity. Furthermore, at the cellular level, R6/2 mice exhibit a receptor specific distributional pattern of SSTRs like immunoreactivity and colocalization with β, α and δ cells. While GAD expression is increased, TH and SYP immunoreactivity was decreased in R6/2 mice, anticipating a cross-talk between the CNS and pancreas in diabetes pathophysiology. We also dissected out the changes in signaling pathway and found decreased activation and expression of PKA, AKT, ERK1/2 and STAT3 in R6/2 mice pancreas. These findings suggest that the impaired organization of SSTRs within islets may lead to perturbed hormonal regulation and signaling. These interconnected complex events might shed new light on the pathogenesis of diabetes in neurodegenerative diseases and the role of SSTRs in potential therapeutic intervention. Copyright © 2017 Elsevier B.V. All rights reserved.

  18. Progressive Impairment of Lactate-based Gluconeogenesis in the Huntington's Disease Mouse Model R6/2.

    Science.gov (United States)

    Nielsen, Signe Marie Borch; Hasholt, Lis; Nørremølle, Anne; Josefsen, Knud

    2015-04-20

    Huntington's disease (HD) is a neurodegenerative illness, where selective neuronal loss in the brain caused by expression of mutant huntingtin protein leads to motor dysfunction and cognitive decline in addition to peripheral metabolic changes. In this study we confirm our previous observation of impairment of lactate-based hepatic gluconeogenesis in the transgenic HD mouse model R6/2 and determine that the defect manifests very early and progresses in severity with disease development, indicating a potential to explore this defect in a biomarker context. Moreover, R6/2 animals displayed lower blood glucose levels during prolonged fasting compared to wild type animals.

  19. Genome Sequences of the Oxytetracycline Production Strain Streptomyces rimosus R6-500 and Two Mutants with Chromosomal Rearrangements

    KAUST Repository

    Baranasic, Damir

    2014-07-17

    The genome sequence of Streptomyces rimosus R6-500, an industrially improved strain which produces high titers of the important antibiotic oxytetracycline, is reported, as well as the genome sequences of two derivatives arising due to the genetic instability of the strain.

  20. Genome Sequences of the Oxytetracycline Production Strain Streptomyces rimosus R6-500 and Two Mutants with Chromosomal Rearrangements

    KAUST Repository

    Baranasic, Damir; Zucko, Jurica; Nair, Mridul; Pain, Arnab; Long, Paul F.; Hranueli, Daslav; Cullum, John; Starcevic, Antonio

    2014-01-01

    The genome sequence of Streptomyces rimosus R6-500, an industrially improved strain which produces high titers of the important antibiotic oxytetracycline, is reported, as well as the genome sequences of two derivatives arising due to the genetic instability of the strain.

  1. Amino methylation of 2-R-6-R_1-imidazo-[2.1-B]-1.3.4-thiadiazole

    International Nuclear Information System (INIS)

    Saidov, D.K.; Rakhmonov, R.O.; Khodzhiboev, Yu.; Kukaniev, M.A.; Bandaev, S.

    2015-01-01

    Present article is devoted to amino methylation of 2-R-6-R_1-imidazo-[2.1-B]-1.3.4-thiadiazole. The reaction of new modifications of derivatives of imidazo-[2.1-B]-1.3.4-thiadiazoles-2-bromine-6-p-bromophenyl and 2-alkyl alkylene sulfonyl-6-phenyl imidazo--[2.1-B]-1.3.4-thiadiazole on Mannich with secondary and heterocyclic amines was studied.

  2. Progressive Impairment of Lactate-based Gluconeogenesis in the Huntington?s Disease Mouse Model R6/2

    OpenAIRE

    Nielsen, Signe Marie Borch; Hasholt, Lis; N?rrem?lle, Anne; Josefsen, Knud

    2015-01-01

    Huntington?s disease (HD) is a neurodegenerative illness, where selective neuronal loss in the brain caused by expression of mutant huntingtin protein leads to motor dysfunction and cognitive decline in addition to peripheral metabolic changes. In this study we confirm our previous observation of impairment of lactate-based hepatic gluconeogenesis in the transgenic HD mouse model R6/2 and determine that the defect manifests very early and progresses in severity with disease development, indic...

  3. Striatal pre-enkephalin overexpression improves Huntington's disease symptoms in the R6/2 mouse model of Huntington's disease.

    Directory of Open Access Journals (Sweden)

    Stéphanie Bissonnette

    Full Text Available The reduction of pre-enkephalin (pENK mRNA expression might be an early sign of striatal neuronal dysfunction in Huntington's disease (HD, due to mutated huntingtin protein. Indeed, striatopallidal (pENK-containing neurodegeneration occurs at earlier stage of the disease, compare to the loss of striatonigral neurons. However, no data are available about the functional role of striatal pENK in HD. According to the neuroprotective properties of opioids that have been recognized recently, the objective of this study was to investigate whether striatal overexpression of pENK at early stage of HD can improve motor dysfunction, and/or reduce striatal neuronal loss in the R6/2 transgenic mouse model of HD. To achieve this goal recombinant adeno-associated-virus (rAAV2-containing green fluorescence protein (GFP-pENK was injected bilaterally in the striatum of R6/2 mice at 5 weeks old to overexpress opioid peptide pENK. Striatal injection of rAAV2-GFP was used as a control. Different behavioral tests were carried out before and/or after striatal injections of rAAV2. The animals were euthanized at 10 weeks old. Our results demonstrate that striatal overexpression of pENK had beneficial effects on behavioral symptoms of HD in R6/2 by: delaying the onset of decline in muscular force; reduction of clasping; improvement of fast motor activity, short-term memory and recognition; as well as normalization of anxiety-like behavior. The improvement of behavioral dysfunction in R6/2 mice having received rAAV2-GFP-pENK associated with upregulation of striatal pENK mRNA; the increased level of enkephalin peptide in the striatum, globus pallidus and substantia nigra; as well as the slight increase in the number of striatal neurons compared with other groups of R6/2. Accordingly, we suggest that at early stage of HD upregulation of striatal enkephalin might play a key role at attenuating illness symptoms.

  4. Metabolism of Lutein and Zeaxanthin in Rhesus Monkeys: Identification of (3R,6′R)- and (3R,6′S)-3′-Dehydro-lutein as Common Metabolites and Comparison to Humans

    Science.gov (United States)

    Albert, Gesa I.; Hoeller, Ulrich; Schierle, Joseph; Neuringer, Martha; Johnson, Elizabeth J.; Schalch, Wolfgang

    2012-01-01

    Lutein and zeaxanthin are xanthophylls that can be found highly concentrated in the macula of the retina. They are thought to protect the macula through their role as blue-light filters and because of their antioxidant and singlet oxygen quenching properties. Examination of metabolites unique to lutein and zeaxanthin such as 3′-dehydro-lutein, and of their stereochemistry may provide insight to the mechanism by which they are formed and by which they exert protection. To evaluate the formation of such metabolites, eleven monkeys were raised on a xanthophyll-free diet, and supplemented with pure lutein or pure zeaxanthin (2.2 mg/kg body weight/d). The period of supplementation ranged between 12 to 92 weeks. At study start and throughout the study, serum samples were taken and analyzed for xanthophylls using different HPLC systems. Xanthophyll metabolites were identified using UV/VIS and HR-MS detection. Lutein and zeaxanthin metabolites were found in detectable amounts with 3′-dehydro-lutein being a common metabolite of both. Using chiral-phase HPLC, two diastereomers, (3R,6′R)-3′-dehydro-lutein and (3R,6′S)-3′-dehydro-lutein, were identified and shown to be present in nearly equimolar amounts. A pathway for their formation from either lutein or zeaxanthin is proposed. These finding were comparable to results obtained with human plasma. PMID:18582588

  5. Neuroprotective properties of cannabigerol in Huntington's disease: studies in R6/2 mice and 3-nitropropionate-lesioned mice.

    Science.gov (United States)

    Valdeolivas, Sara; Navarrete, Carmen; Cantarero, Irene; Bellido, María L; Muñoz, Eduardo; Sagredo, Onintza

    2015-01-01

    Different plant-derived and synthetic cannabinoids have shown to be neuroprotective in experimental models of Huntington's disease (HD) through cannabinoid receptor-dependent and/or independent mechanisms. Herein, we studied the effects of cannabigerol (CBG), a nonpsychotropic phytocannabinoid, in 2 different in vivo models of HD. CBG was extremely active as neuroprotectant in mice intoxicated with 3-nitropropionate (3NP), improving motor deficits and preserving striatal neurons against 3NP toxicity. In addition, CBG attenuated the reactive microgliosis and the upregulation of proinflammatory markers induced by 3NP, and improved the levels of antioxidant defenses that were also significantly reduced by 3NP. We also investigated the neuroprotective properties of CBG in R6/2 mice. Treatment with this phytocannabinoid produced a much lower, but significant, recovery in the deteriorated rotarod performance typical of R6/2 mice. Using HD array analysis, we were able to identify a series of genes linked to this disease (e.g., symplekin, Sin3a, Rcor1, histone deacetylase 2, huntingtin-associated protein 1, δ subunit of the gamma-aminobutyric acid-A receptor (GABA-A), and hippocalcin), whose expression was altered in R6/2 mice but partially normalized by CBG treatment. We also observed a modest improvement in the gene expression for brain-derived neurotrophic factor (BDNF), insulin-like growth factor-1 (IGF-1), and peroxisome proliferator-activated receptor-γ (PPARγ), which is altered in these mice, as well as a small, but significant, reduction in the aggregation of mutant huntingtin in the striatal parenchyma in CBG-treated animals. In conclusion, our results open new research avenues for the use of CBG, alone or in combination with other phytocannabinoids or therapies, for the treatment of neurodegenerative diseases such as HD.

  6. DYSFUNCTIONAL KYNURENINE PATHWAY METABOLISM IN THE R6/2 MOUSE MODEL OF HUNTINGTON’S DISEASE

    Science.gov (United States)

    Sathyasaikumar, Korrapati V.; Stachowski, Erin K.; Amori, Laura; Guidetti, Paolo; Muchowski, Paul J.; Schwarcz, Robert

    2013-01-01

    Elevated concentrations of neurotoxic metabolites of the kynurenine pathway (KP) of tryptophan degradation may play a causative role in Huntington’s disease (HD). The brain levels of one of these compounds, 3-hydroxykynurenine (3-HK), are increased in both HD and several mouse models of the disease. In the present study, we examined this impairment in greater detail using the R6/2 mouse, a well-established animal model of HD. Initially, mutant and age-matched wild-type mice received an intrastriatal injection of 3H-tryptophan to assess the acute, local de novo production of kynurenine, the immediate bioprecursor of 3-HK, in vivo. No effect of genotype was observed between 4 and 12 weeks of age. In contrast, intrastriatally applied 3H-kynurenine resulted in significantly increased neosynthesis of 3H-3-HK, but not other tritiated KP metabolites, in the R6/2 striatum. Subsequent ex vivo studies in striatal, cortical and cerebellar tissue revealed substantial increases in the activity of the biosynthetic enzyme of 3-HK, kynurenine 3-monooxygenase (KMO) and significant reductions in the activity of its degradative enzyme, kynureninase, in HD mice starting at 4 weeks of age. Decreased kynureninase activity was most evident in the cortex and preceded the increase in KMO activity. The activity of other KP enzymes showed no consistent brain abnormalities in the mutant mice. These findings suggest that impairments in its immediate metabolic enzymes jointly account for the abnormally high brain levels of 3-HK in the R6/2 model of HD. PMID:20236387

  7. Detection of early behavioral markers of Huntington's disease in R6/2 mice employing an automated social home cage

    DEFF Research Database (Denmark)

    Rudenko, Olga; Tkach, Vadim; Berezin, Vladimir

    2009-01-01

    developed behavior screening system, the IntelliCage, allows automated testing of mouse behavior in the home cage employing individual recognition of animals living in social groups. The present study validates the ability of the IntelliCage system to detect behavioral and cognitive dysfunction in R6/2 mice......Huntington's disease (HD) is an autosomal-dominant neurodegenerative disorder, for which no known cure or effective treatment exists. To facilitate the search for new potential treatments of HD, an automated system for analyzing the behavior of transgenic HD mice is urgently needed. A recently...

  8. Further development and test of the calculation code PROST for the probabilistic and deterministic evaluation of piping and vessels in the frame of leak-before-break confirmation; Weiterentwicklung und Erprobung des Rechenprogramms PROST zur probabilistischen und deterministischen Bewertung von Rohrleitungen und Behaeltern im Rahmen von Leck-vor-Bruch Nachweisen

    Energy Technology Data Exchange (ETDEWEB)

    Heckmann, Klaus; Sievers, Juergen; Arndt, Jens; Blaesius, Christoph

    2016-07-15

    The structural mechanics computer code PROST of GRS was extended in the project RS1516 for more applications and improved usability. The fracture mechanical features were extended by supplementary structure types, additional crack geometries, refined failure criteria, and temperature-dependent parameters. The consideration of in-service inspections was revised, while upgraded fatigue analyses enhance the quality of the computed results. The modeling of leakage rates was ameliorated by coupling the WinLeck computer code of GRS for leak rate computation, leading to better predictions of these features. Additional probabilistic techniques were implemented in PROST, which allow a more accurate quantification of risks. PROST's validation was done within in the project by two international benchmark studies. Analytical techniques for fracture mechanical parameters and in-service inspections in probabilistic crack-growth analyses were in the focus of the comparative studies. In addition, diverse test cases are analyzed, allowing the comparison with published studies. The available methodology for leak rate analysis was used for the planning of upcoming measurements. The PROST code has a graphical user interface, is accompanied by a detailed documentation and is made available for external users. Thus, it is a qualified tool for fracture mechanical studies, taking into account nuclear safety standards.

  9. Formation of non-equilibrium structures in R6M5 steel under strong pulse beams action

    International Nuclear Information System (INIS)

    Rusin, Yu.G.; Plotnikov, S.V.

    2001-01-01

    Formation of non-equilibrium structures in R6M5 steel surface layer in the supply state under irradiation by strong pulse beams (SPB) is examined. Cylindric samples with diameter 10 mm and height 15 mm of R6M5 fast-cutting steel with following content (weight %): 0.85% C, 0.4% Mn, 0.5% Si, 4.0 Cr; 2.1% V; 5.3% Mo, 6.0% W; 0.4% Ni, Fe (the rest) were examined. Irradiation by SPB was conducted on the 'TEMP' modified accelerator operating in a technological regime with carbon beams parameters: energy from 0.3 up o 0.4 MeV, beam density in an impulse from 20 to 250 A/cm 2 , pulse duration from 60 tp 100 ns. The beam consists of 70 % carbon ions and 30 % hydrogen ions. Phase identification and its structural phase analysis have been studied on the DRON-3 X-ray diffractometer of common assignment. Topography of metallographic specimen surface has been examined on the REM-200 scanning electron microscope. Doping elements redistribution and phases quantitative characteristics after SPB action were studied with help of the X-ray spectral microanalysis (XRSA) on the MS-46 Camebax microanalyzer. Character of doping elements redistribution in the alloy (XRSA data) show its appreciably redistribution, moreover in the melted zone the increased content of molybdenum, tungsten, vanadium is observing, and in the zone of thermal action its increase relatively to matrix values

  10. Systemic delivery of recombinant brain derived neurotrophic factor (BDNF in the R6/2 mouse model of Huntington's disease.

    Directory of Open Access Journals (Sweden)

    Carmela Giampà

    Full Text Available Loss of huntingtin-mediated BDNF gene transcription has been shown to occur in HD and thus contribute to the degeneration of the striatum. Several studies have indicated that an increase in BDNF levels is associated with neuroprotection and amelioration of neurological signs in animal models of HD. In a recent study, an increase in BDNF mRNA and protein levels was recorded in mice administered recombinant BDNF peripherally. Chronic, indwelling osmotic mini-pumps containing either recombinant BDNF or saline were surgically placed in R6/2 or wild-type mice from 4 weeks of age until euthanasia. Neurological evaluation (paw clasping, rotarod performance, locomotor activity in an open field was performed. After transcardial perfusion, histological and immunohistochemical studies were performed. We found that BDNF- treated R6/2 mice survived longer and displayed less severe signs of neurological dysfunction than the vehicle treated ones. Primary outcome measures such as brain volume, striatal atrophy, size and morphology of striatal neurons, neuronal intranuclear inclusions and microglial reaction confirmed a neuroprotective effect of the compound. BDNF was effective in increasing significantly the levels of activated CREB and of BDNF the striatal spiny neurons. Moreover, systemically administered BDNF increased the synthesis of BDNF as demonstrated by RT-PCR, and this might account for the beneficial effects observed in this model.

  11. Comparison of COD, R6, and J-contour integral methods of defect assessment, modified to give critical flaw sizes

    International Nuclear Information System (INIS)

    Burdekin, F.M.; Turner, C.E.

    1982-01-01

    A comparative study of the application of different elastic-plastic fracture mechanics methods to the calculation of critical defect sizes in pressure vessels showed widely varying results. The present authors have investigated in detail the reasons for the variations resulting from the use of the CEGB R6, COD design curve, and J-design curve methods to the particular pressure vessel problems. To obtain reasonable agreement between the three methods for the calculation of critical flaw sizes in high stress gradient situations, the published COD method in PD6493 has to be modified to remove its inherent safety factor, and to allow for stress gradients, and a consistent treatment for gross yielding/collapse has to be adopted for all three methods. (author)

  12. Correlations of behavioral deficits with brain pathology assessed through longitudinal MRI and histopathology in the R6/1 mouse model of Huntington's disease.

    Directory of Open Access Journals (Sweden)

    Ivan Rattray

    Full Text Available Huntington's disease (HD is caused by the expansion of a CAG repeat in the huntingtin (HTT gene. The R6 mouse models of HD express a mutant version of exon 1 HTT and typically develop motor and cognitive impairments, a widespread huntingtin (HTT aggregate pathology and brain atrophy. Unlike the more commonly used R6/2 mouse line, R6/1 mice have fewer CAG repeats and, subsequently, a less rapid pathological decline. Compared to the R6/2 line, fewer descriptions of the progressive pathologies exhibited by R6/1 mice exist. The association between the molecular and cellular neuropathology with brain atrophy, and with the development of behavioral phenotypes remains poorly understood in many models of HD. In attempt to link these factors in the R6/1 mouse line, we have performed detailed assessments of behavior and of regional brain abnormalities determined through longitudinal, in vivo magnetic resonance imaging (MRI, as well as an end-stage, ex vivo MRI study and histological assessment. We found progressive decline in both motor and non-motor related behavioral tasks in R6/1 mice, first evident at 11 weeks of age. Regional brain volumes were generally unaffected at 9 weeks, but by 17 weeks there was significant grey matter atrophy. This age-related brain volume loss was validated using a more precise, semi-automated Tensor Based morphometry assessment. As well as these clear progressive phenotypes, mutant HTT (mHTT protein, the hallmark of HD molecular pathology, was widely distributed throughout the R6/1 brain and was accompanied by neuronal loss. Despite these seemingly concomitant, robust pathological phenotypes, there appeared to be little correlation between the three main outcome measures: behavioral performance, MRI-detected brain atrophy and histopathology. In conclusion, R6/1 mice exhibit many features of HD, but the underlying mechanisms driving these clear behavioral disturbances and the brain volume loss, still remain unclear.

  13. Application of the LBB concept to nuclear power plants with WWER 440 and WWER 1000 reactors

    Energy Technology Data Exchange (ETDEWEB)

    Zdarek, J.; Pecinka, L. [Nuclear Research Institute Rez (Czech Republic)

    1997-04-01

    Leak-before-break (LBB) analysis of WWER type reactors in the Czech and Sloval Republics is summarized in this paper. Legislative bases, required procedures, and validation and verification of procedures are discussed. A list of significant issues identified during the application of LBB analysis is presented. The results of statistical evaluation of crack length characteristics are presented and compared for the WWER 440 Type 230 and 213 reactors and for the WWER 1000 Type 302, 320 and 338 reactors.

  14. Application of the LBB concept to nuclear power plants with WWER 440 and WWER 1000 reactors

    International Nuclear Information System (INIS)

    Zdarek, J.; Pecinka, L.

    1997-01-01

    Leak-before-break (LBB) analysis of WWER type reactors in the Czech and Sloval Republics is summarized in this paper. Legislative bases, required procedures, and validation and verification of procedures are discussed. A list of significant issues identified during the application of LBB analysis is presented. The results of statistical evaluation of crack length characteristics are presented and compared for the WWER 440 Type 230 and 213 reactors and for the WWER 1000 Type 302, 320 and 338 reactors

  15. Failure to launch: the self-regulating Md-MYB10 R6 gene from apple is active in flowers but not leaves of Petunia.

    Science.gov (United States)

    Boase, Murray R; Brendolise, Cyril; Wang, Lei; Ngo, Hahn; Espley, Richard V; Hellens, Roger P; Schwinn, Kathy E; Davies, Kevin M; Albert, Nick W

    2015-10-01

    The Md - MYB10 R6 gene from apple is capable of self-regulating in heterologous host species and enhancing anthocyanin pigmentation, but the activity of MYB10 is dependent on endogenous protein partners. Coloured foliage due to anthocyanin pigments (bronze/red/black) is an attractive trait that is often lacking in many bedding, ornamental and horticultural plants. Apples (Malus × domestica) containing an allelic variant of the anthocyanin regulator, Md-MYB10 R6 , are highly pigmented throughout the plant, due to autoregulation by MYB10 upon its own promoter. We investigated whether Md-MYB10 R6 from apple is capable of functioning within the heterologous host Petunia hybrida to generate plants with novel pigmentation patterns. The Md-MYB10 R6 transgene (MYB10-R6 pro :MYB10:MYB10 term ) activated anthocyanin synthesis when transiently expressed in Antirrhinum rosea (dorsea) petals and petunia leaf discs. Stable transgenic petunias containing Md-MYB10 R6 lacked foliar pigmentation but had coloured flowers, complementing the an2 phenotype of 'Mitchell' petunia. The absence of foliar pigmentation was due to the failure of the Md-MYB10 R6 gene to self-activate in vegetative tissues, suggesting that additional protein partners are required for Md-MYB10 to activate target genes in this heterologous system. In petunia flowers, where endogenous components including MYB-bHLH-WDR (MBW) proteins were present, expression of the Md-MYB10 R6 promoter was initiated, allowing auto-regulation to occur and activating anthocyanin production. Md-MYB10 is capable of operating within the petunia MBW gene regulation network that controls the expression of the anthocyanin biosynthesis genes, AN1 (bHLH) and MYBx (R3-MYB repressor) in petals.

  16. Oxidative metabolism and Ca2+ handling in isolated brain mitochondria and striatal neurons from R6/2 mice, a model of Huntington's disease.

    Science.gov (United States)

    Hamilton, James; Pellman, Jessica J; Brustovetsky, Tatiana; Harris, Robert A; Brustovetsky, Nickolay

    2016-07-01

    Alterations in oxidative metabolism and defects in mitochondrial Ca 2+ handling have been implicated in the pathology of Huntington's disease (HD), but existing data are contradictory. We investigated the effect of human mHtt fragments on oxidative metabolism and Ca 2+ handling in isolated brain mitochondria and cultured striatal neurons from the R6/2 mouse model of HD. Non-synaptic and synaptic mitochondria isolated from the brains of R6/2 mice had similar respiratory rates and Ca 2+ uptake capacity compared with mitochondria from wild-type (WT) mice. Respiratory activity of cultured striatal neurons measured with Seahorse XF24 flux analyzer revealed unaltered cellular respiration in neurons derived from R6/2 mice compared with neurons from WT animals. Consistent with the lack of respiratory dysfunction, ATP content of cultured striatal neurons from R6/2 and WT mice was similar. Mitochondrial Ca 2+ accumulation was also evaluated in cultured striatal neurons from R6/2 and WT animals. Our data obtained with striatal neurons derived from R6/2 and WT mice show that both glutamate-induced increases in cytosolic Ca 2+ and subsequent carbonilcyanide p-triflouromethoxyphenylhydrazone-induced increases in cytosolic Ca 2+ were similar between WT and R6/2, suggesting that mitochondria in neurons derived from both types of animals accumulated comparable amounts of Ca 2+ Overall, our data argue against respiratory deficiency and impaired Ca 2+ handling induced by human mHtt fragments in both isolated brain mitochondria and cultured striatal neurons from transgenic R6/2 mice. © The Author 2016. Published by Oxford University Press. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

  17. Human Neural Stem Cell Transplantation Rescues Functional Deficits in R6/2 and Q140 Huntington's Disease Mice

    Directory of Open Access Journals (Sweden)

    Jack C. Reidling

    2018-01-01

    Full Text Available Huntington's disease (HD is an inherited neurodegenerative disorder with no disease-modifying treatment. Expansion of the glutamine-encoding repeat in the Huntingtin (HTT gene causes broad effects that are a challenge for single treatment strategies. Strategies based on human stem cells offer a promising option. We evaluated efficacy of transplanting a good manufacturing practice (GMP-grade human embryonic stem cell-derived neural stem cell (hNSC line into striatum of HD modeled mice. In HD fragment model R6/2 mice, transplants improve motor deficits, rescue synaptic alterations, and are contacted by nerve terminals from mouse cells. Furthermore, implanted hNSCs are electrophysiologically active. hNSCs also improved motor and late-stage cognitive impairment in a second HD model, Q140 knockin mice. Disease-modifying activity is suggested by the reduction of aberrant accumulation of mutant HTT protein and expression of brain-derived neurotrophic factor (BDNF in both models. These findings hold promise for future development of stem cell-based therapies.

  18. Alteration of rare-earth-metal cluster iodides R(R6I12Z) through cation substitution

    International Nuclear Information System (INIS)

    Jensen, E.A.; Corbett, J.D.

    2003-01-01

    Four examples of (A x R 1-x )R 6 I 12 Z phases further illustrate the flexibility of the rhombohedral R 7 X 12 Z structure to substitution of heterocations for the isolated R III atoms without destruction of the structure. The examples with R=La, Pr, Z=Fe, Co, Ir, and stoichiometric amounts of A=Na or Ca were prepared by traditional high temperature techniques and characterized by single crystal and Guinier powder X-ray diffraction techniques. Product compositions refined in the parent space group R3-bar from reactions of stoichiometry AR 6 I 12 Z were (Na 0.90 Pr 0.10 )Pr 6 I 12 Ir, (Na 0.954 La 0.046 )La 6 I 12 Fe, and (Ca 0.801 La 0.199 )La 6 I 12 Co. More general characteristics of and trends in the family of R 7 X 12 Z structures are also considered, including distortions of the ideal motif as a function of extremes in the components

  19. Brain Cholesterol Synthesis and Metabolism is Progressively Disturbed in the R6/1 Mouse Model of Huntington's Disease: A Targeted GC-MS/MS Sterol Analysis.

    Science.gov (United States)

    Kreilaus, Fabian; Spiro, Adena S; Hannan, Anthony J; Garner, Brett; Jenner, Andrew M

    2015-01-01

    Cholesterol has essential functions in neurological processes that require tight regulation of synthesis and metabolism. Perturbed cholesterol homeostasis has been demonstrated in Huntington's disease, however the exact role of these changes in disease pathogenesis is not fully understood. This study aimed to comprehensively examine changes in cholesterol biosynthetic precursors, metabolites and oxidation products in the striatum and cortex of the R6/1 transgenic mouse model of Huntington's disease. We also aimed to characterise the progression of the physical phenotype in these mice. GC-MS/MS was used to quantify a broad range of sterols in the striatum and cortex of R6/1 and wild type mice at 6, 12, 20, 24 and 28 weeks of age. Motor dysfunction was assessed over 28 weeks using the RotaRod and the hind-paw clasping tests. 24(S)-Hydroxycholesterol and 27-hydroxycholesterol were the major cholesterol metabolites that significantly changed in R6/1 mice. These changes were specifically localised to the striatum and were detected at the end stages of the disease. Cholesterol synthetic precursors (lathosterol and lanosterol) were significantly reduced in the cortex and striatum by 6 weeks of age, prior to the onset of motor dysfunction, as well as the cognitive and affective abnormalities previously reported. Elevated levels of desmosterol, a substrate of delta(24)-sterol reductase (DHCR24), were also detected in R6/1 mice at the end time-point. Female R6/1 mice exhibited a milder weight loss and hind paw clasping phenotype compared to male R6/1 mice, however, no difference in the brain sterol profile was detected between sexes. Several steps in cholesterol biosynthetic and metabolic pathways are differentially altered in the R6/1 mouse brain as the disease progresses and this is most severe in the striatum. This provides further insights into early molecular mediators of HD onset and disease progression and identifies candidate molecular targets for novel therapeutic

  20. Prostaglandin E2 EP2 activation reduces memory decline in R6/1 mouse model of Huntington's disease by the induction of BDNF-dependent synaptic plasticity.

    Science.gov (United States)

    Anglada-Huguet, Marta; Vidal-Sancho, Laura; Giralt, Albert; García-Díaz Barriga, Gerardo; Xifró, Xavier; Alberch, Jordi

    2016-11-01

    Huntington's disease (HD) patients and mouse models show learning and memory impairment even before the onset of motor symptoms. Deficits in hippocampal synaptic plasticity have been involved in the HD memory impairment. Several studies show that prostaglandin E2 (PGE2) EP2 receptor stimulates synaptic plasticity and memory formation. However, this role was not explored in neurodegenerative diseases. Here, we investigated the capacity of PGE2 EP2 receptor to promote synaptic plasticity and memory improvements in a model of HD, the R6/1 mice, by administration of the agonist misoprostol. We found that misoprostol increases dendritic branching in cultured hippocampal neurons in a brain-derived neurotrophic factor (BDNF)-dependent manner. Then, we implanted an osmotic mini-pump system to chronically administrate misoprostol to R6/1 mice from 14 to 18weeks of age. We observed that misoprostol treatment ameliorates the R6/1 long-term memory deficits as analyzed by the T-maze spontaneous alternation task and the novel object recognition test. Importantly, administration of misoprostol promoted the expression of hippocampal BDNF. Moreover, the treatment with misoprostol in R6/1 mice blocked the reduction in the number of PSD-95 and VGluT-1 positive particles observed in hippocampus of vehicle-R6/1 mice. In addition, we observed an increase of cAMP levels in the dentate ` of WT and R6/1 mice treated with misoprostol. Accordingly, we showed a reduction in the number of mutant huntingtin nuclear inclusions in the dentate gyrus of R6/1 mice. Altogether, these results suggest a putative therapeutic effect of PGE2 EP2 receptor in reducing cognitive deficits in HD. Copyright © 2016. Published by Elsevier Inc.

  1. Assessment of crack opening area for leak rates

    Energy Technology Data Exchange (ETDEWEB)

    Sharples, J.K.; Bouchard, P.J.

    1997-04-01

    This paper outlines the background to recommended crack opening area solutions given in a proposed revision to leak before break guidance for the R6 procedure. Comparisons with experimental and analytical results are given for some selected cases of circumferential cracks in cylinders. It is shown that elastic models can provide satisfactory estimations of crack opening displacement (and area) but they become increasingly conservative for values of L{sub r} greater than approximately 0.4. The Dugdale small scale yielding model gives conservative estimates of crack opening displacement with increasing enhancement for L{sub r} values greater than 0.4. Further validation of the elastic-plastic reference stress method for up to L{sub r} values of about 1.0 is presented by experimental and analytical comparisons. Although a more detailed method, its application gives a best estimate of crack opening displacement which may be substantially greater than small scale plasticity models. It is also shown that the local boundary conditions in pipework need to be carefully considered when evaluating crack opening area for through-wall bending stresses resulting from welding residual stresses or geometry discontinuities.

  2. Assessment of crack opening area for leak rates

    International Nuclear Information System (INIS)

    Sharples, J.K.; Bouchard, P.J.

    1997-01-01

    This paper outlines the background to recommended crack opening area solutions given in a proposed revision to leak before break guidance for the R6 procedure. Comparisons with experimental and analytical results are given for some selected cases of circumferential cracks in cylinders. It is shown that elastic models can provide satisfactory estimations of crack opening displacement (and area) but they become increasingly conservative for values of L r greater than approximately 0.4. The Dugdale small scale yielding model gives conservative estimates of crack opening displacement with increasing enhancement for L r values greater than 0.4. Further validation of the elastic-plastic reference stress method for up to L r values of about 1.0 is presented by experimental and analytical comparisons. Although a more detailed method, its application gives a best estimate of crack opening displacement which may be substantially greater than small scale plasticity models. It is also shown that the local boundary conditions in pipework need to be carefully considered when evaluating crack opening area for through-wall bending stresses resulting from welding residual stresses or geometry discontinuities

  3. A computing system for LBB considerations

    Energy Technology Data Exchange (ETDEWEB)

    Ikonen, K.; Miettinen, J.; Raiko, H.; Keskinen, R.

    1997-04-01

    A computing system has been developed at VTT Energy for making efficient leak-before-break (LBB) evaluations of piping components. The system consists of fracture mechanics and leak rate analysis modules which are linked via an interactive user interface LBBCAL. The system enables quick tentative analysis of standard geometric and loading situations by means of fracture mechanics estimation schemes such as the R6, FAD, EPRI J, Battelle, plastic limit load and moments methods. Complex situations are handled with a separate in-house made finite-element code EPFM3D which uses 20-noded isoparametric solid elements, automatic mesh generators and advanced color graphics. Analytical formulas and numerical procedures are available for leak area evaluation. A novel contribution for leak rate analysis is the CRAFLO code which is based on a nonequilibrium two-phase flow model with phase slip. Its predictions are essentially comparable with those of the well known SQUIRT2 code; additionally it provides outputs for temperature, pressure and velocity distributions in the crack depth direction. An illustrative application to a circumferentially cracked elbow indicates expectedly that a small margin relative to the saturation temperature of the coolant reduces the leak rate and is likely to influence the LBB implementation to intermediate diameter (300 mm) primary circuit piping of BWR plants.

  4. The Group 2 Metabotropic Glutamate Receptor Agonist LY379268 Rescues Neuronal, Neurochemical and Motor Abnormalities in R6/2 Huntington’s Disease Mice

    Science.gov (United States)

    Reiner, A.; Lafferty, D.C.; Wang, H.B.; Del Mar, N.; Deng, Y.P.

    2012-01-01

    Excitotoxic injury to striatum by dysfunctional cortical input or aberrant glutamate uptake may contribute to Huntington’s Disease (HD) pathogenesis. Since corticostriatal terminals possess mGluR2/3 autoreceptors, whose activation dampens glutamate release, we tested the ability of the mGluR2/3 agonist LY379268 to improve the phenotype in R6/2 HD mice with 120–125 CAG repeats. Daily subcutaneous injection of a maximum tolerated dose (MTD) of LY379268 (20mg/kg) had no evident adverse effects in WT mice, and diverse benefits in R6/2 mice, both in a cohort of mice tested behaviorally until the end of R6/2 lifespan and in a cohort sacrificed at 10 weeks of age for blinded histological analysis. MTD LY379268 yielded a significant 11% increase in R6/2 survival, an improvement on rotarod, normalization and/or improvement in locomotor parameters measured in open field (activity, speed, acceleration, endurance, and gait), a rescue of a 15–20% cortical and striatal neuron loss, normalization of SP striatal neuron neurochemistry, and to a lesser extent enkephalinergic striatal neuron neurochemistry. Deficits were greater in male than female R6/2 mice, and drug benefit tended to be greater in males. The improvements in SP striatal neurons, which facilitate movement, are consistent with the improved movement in LY379268-treated R6/2 mice. Our data indicate that mGluR2/3 agonists may be particularly useful for ameliorating the morphological, neurochemical and motor defects observed in HD. PMID:22472187

  5. Lack of Antidepressant Effects of (2R,6R)-Hydroxynorketamine in a Rat Learned Helplessness Model: Comparison with (R)-Ketamine.

    Science.gov (United States)

    Shirayama, Yukihiko; Hashimoto, Kenji

    2018-01-01

    (R)-Ketamine exhibits rapid and sustained antidepressant effects in animal models of depression. It is stereoselectively metabolized to (R)-norketamine and subsequently to (2R,6R)-hydroxynorketamine in the liver. The metabolism of ketamine to hydroxynorketamine was recently demonstrated to be essential for ketamine's antidepressant actions. However, no study has compared the antidepressant effects of these 3 compounds in animal models of depression. The effects of a single i.p. injection of (R)-ketamine, (R)-norketamine, and (2R,6R)-hydroxynorketamine in a rat learned helplessness model were examined. A single dose of (R)-ketamine (20 mg/kg) showed an antidepressant effect in the rat learned helplessness model. In contrast, neither (R)-norketamine (20 mg/kg) nor (2R,6R)-hydroxynorketamine (20 and 40 mg/kg) did so. Unlike (R)-ketamine, its metabolite (2R,6R)-hydroxynorketamine did not show antidepressant actions in the rat learned helplessness model. Therefore, it is unlikely that the metabolism of ketamine to hydroxynorketamine is essential for ketamine's antidepressant actions. © The Author 2017. Published by Oxford University Press on behalf of CINP.

  6. SAHA decreases HDAC 2 and 4 levels in vivo and improves molecular phenotypes in the R6/2 mouse model of Huntington's disease.

    Directory of Open Access Journals (Sweden)

    Michal Mielcarek

    Full Text Available Huntington's disease (HD is a progressive neurological disorder for which there are no disease-modifying treatments. Transcriptional dysregulation is a major molecular feature of HD, which significantly contributes to disease progression. Therefore, the development of histone deacetylase (HDAC inhibitors as therapeutics for HD has been energetically pursued. Suberoylanilide hydroxamic acid (SAHA - a class I HDAC as well an HDAC6 inhibitor, improved motor impairment in the R6/2 mouse model of HD. Recently it has been found that SAHA can also promote the degradation of HDAC4 and possibly other class IIa HDACs at the protein level in various cancer cell lines. To elucidate whether SAHA is a potent modifier of HDAC protein levels in vivo, we performed two independent mouse trials. Both WT and R6/2 mice were chronically treated with SAHA and vehicle. We found that prolonged SAHA treatment causes the degradation of HDAC4 in cortex and brain stem, but not hippocampus, without affecting its transcript levels in vivo. Similarly, SAHA also decreased HDAC2 levels without modifying the expression of its mRNA. Consistent with our previous data, SAHA treatment diminishes Hdac7 transcript levels in both wild type and R6/2 brains and unexpectedly was found to decrease Hdac11 in R6/2 but not wild type. We investigated the effects of SAHA administration on well-characterised molecular readouts of disease progression. We found that SAHA reduces SDS-insoluble aggregate load in the cortex and brain stem but not in the hippocampus of the R6/2 brains, and that this was accompanied by restoration of Bdnf cortical transcript levels.

  7. A missense mutation in Grm6 reduces but does not eliminate mGluR6 expression or rod depolarizing bipolar cell function.

    Science.gov (United States)

    Peachey, Neal S; Hasan, Nazarul; FitzMaurice, Bernard; Burrill, Samantha; Pangeni, Gobinda; Karst, Son Yong; Reinholdt, Laura; Berry, Melissa L; Strobel, Marge; Gregg, Ronald G; McCall, Maureen A; Chang, Bo

    2017-08-01

    GRM6 encodes the metabotropic glutamate receptor 6 (mGluR6) used by retinal depolarizing bipolar cells (DBCs). Mutations in GRM6 lead to DBC dysfunction and underlie the human condition autosomal recessive complete congenital stationary night blindness. Mouse mutants for Grm6 are important models for this condition. Here we report a new Grm6 mutant, identified in an electroretinogram (ERG) screen of mice maintained at The Jackson Laboratory. The Grm6 nob8 mouse has a reduced-amplitude b-wave component of the ERG, which reflects light-evoked DBC activity. Sequencing identified a missense mutation that converts a highly conserved methionine within the ligand binding domain to leucine (p.Met66Leu). Consistent with prior studies of Grm6 mutant mice, the laminar size and structure in the Grm6 nob8 retina were comparable to control. The Grm6 nob8 phenotype is distinguished from other Grm6 mutants that carry a null allele by a reduced but not absent ERG b-wave, decreased but present expression of mGluR6 at DBC dendritic tips, and mislocalization of mGluR6 to DBC somas. Consistent with a reduced but not absent b-wave, there were a subset of retinal ganglion cells whose responses to light onset have times to peak within the range of those in control retinas. These data indicate that the p.Met66Leu mutant mGluR6 is trafficked less than control. However, the mGluR6 that is localized to the DBC dendritic tips is able to initiate DBC signal transduction. The Grm6 nob8 mouse extends the Grm6 allelic series and will be useful for elucidating the role of mGluR6 in DBC signal transduction and in human disease. NEW & NOTEWORTHY This article describes a mouse model of the human disease complete congenital stationary night blindness in which the mutation reduces but does not eliminate GRM6 expression and bipolar cell function, a distinct phenotype from that seen in other Grm6 mouse models.

  8. Emergency procedures

    International Nuclear Information System (INIS)

    Abd Nasir Ibrahim; Azali Muhammad; Ab Razak Hamzah; Abd Aziz Mohamed; Mohammad Pauzi Ismail

    2004-01-01

    The following subjects are discussed - Emergency Procedures: emergency equipment, emergency procedures; emergency procedure involving X-Ray equipment; emergency procedure involving radioactive sources

  9. Assessment of CATHARE2 V1.5qR6 using the experimental data of BETHSY natural circulation tests

    International Nuclear Information System (INIS)

    Huang Yanping; Jia Dounan

    2003-01-01

    The assessment of CATHARE2 V1.5qR6 is carried out against the experimental data of BETHSY natural circulation test-4. 1a-TC. Results show that the experimental process under single phase natural circulation can be predicted very well by CATHARE2 V1.5qR6, the primary mass inventory at the transition points from single phase natural circulation to two-phase natural circulation and from two-phase natural circulation to reflux condensation mode are also predicted correctly. The predicted results for thermohydraulic parameters of two-phase natural circulation and reflux condensation mode are not so good. Generally speaking, the prediction capability of CATHARE2 V1.5 for strong and two-phase flow process should be improved further in future

  10. Environmental and nutritional factors that affect growth and metabolism of the pneumococcal serotype 2 strain D39 and its nonencapsulated derivative strain R6.

    Directory of Open Access Journals (Sweden)

    Sandra M Carvalho

    Full Text Available Links between carbohydrate metabolism and virulence in Streptococcus pneumoniae have been recurrently established. To investigate these links further we developed a chemically defined medium (CDM and standardized growth conditions that allowed for high growth yields of the related pneumococcal strains D39 and R6. The utilization of the defined medium enabled the evaluation of different environmental and nutritional factors on growth and fermentation patterns under controlled conditions of pH, temperature and gas atmosphere. The same growth conditions impacted differently on the nonencapsulated R6, and its encapsulated progenitor D39. A semi-aerobic atmosphere and a raised concentration of uracil, a fundamental component of the D39 capsule, improved considerably D39 growth rate and biomass. In contrast, in strain R6, the growth rate was enhanced by strictly anaerobic conditions and uracil had no effect on biomass. In the presence of oxygen, the difference in the growth rates was mainly attributed to a lower activity of pyruvate oxidase in strain D39. Our data indicate an intricate connection between capsule production in strain D39 and uracil availability. In this study, we have also successfully applied the in vivo NMR technique to study sugar metabolism in S. pneumoniae R6. Glucose consumption, end-products formation and evolution of intracellular metabolite pools were monitored online by (13C-NMR. Additionally, the pools of NTP and inorganic phosphate were followed by (31P-NMR after a pulse of glucose. These results represent the first metabolic profiling data obtained non-invasively for S. pneumoniae, and pave the way to a better understanding of regulation of central metabolism.

  11. Functional characterisation of homomeric ionotropic glutamate receptors GluR1-GluR6 in a fluorescence-based high throughput screening assay

    DEFF Research Database (Denmark)

    Strange, Mette; Bräuner-Osborne, Hans; Jensen, Anders A.

    2006-01-01

    We have constructed stable HEK293 cell lines expressing the rat ionotropic glutamate receptor subtypes GluR1(i), GluR2Q(i), GluR3(i), GluR4(i), GluR5Q and GluR6Q and characterised the pharmacological profiles of the six homomeric receptors in a fluorescence-based high throughput screening assay...... assay reported to date. We propose that high throughput screening of compound libraries at the six GluR-HEK293 cell lines could be helpful in the search for structurally and pharmacologically novel ligands acting at the receptors....

  12. Hdac6 knock-out increases tubulin acetylation but does not modify disease progression in the R6/2 mouse model of Huntington's disease.

    Directory of Open Access Journals (Sweden)

    Anna Bobrowska

    Full Text Available Huntington's disease (HD is a progressive neurodegenerative disorder for which there is no effective disease modifying treatment. Following-on from studies in HD animal models, histone deacetylase (HDAC inhibition has emerged as an attractive therapeutic option. In parallel, several reports have demonstrated a role for histone deacetylase 6 (HDAC6 in the modulation of the toxicity caused by the accumulation of misfolded proteins, including that of expanded polyglutamine in an N-terminal huntingtin fragment. An important role for HDAC6 in kinesin-1 dependent transport of brain-derived neurotrophic factor (BDNF from the cortex to the striatum has also been demonstrated. To elucidate the role that HDAC6 plays in HD progression, we evaluated the effects of the genetic depletion of HDAC6 in the R6/2 mouse model of HD. Loss of HDAC6 resulted in a marked increase in tubulin acetylation throughout the brain. Despite this, there was no effect on the onset and progression of a wide range of behavioural, physiological, molecular and pathological HD-related phenotypes. We observed no change in the aggregate load or in the levels of soluble mutant exon 1 transprotein. HDAC6 genetic depletion did not affect the efficiency of BDNF transport from the cortex to the striatum. Therefore, we conclude that HDAC6 inhibition does not modify disease progression in R6/2 mice and HDAC6 should not be prioritized as a therapeutic target for HD.

  13. The structures of T6, T3R3 and R6 bovine insulin: combining X-ray diffraction and absorption spectroscopy

    DEFF Research Database (Denmark)

    Frankær, Christian Grundahl; Knudsen, Marianne Vad; Noren, Katarina

    2012-01-01

    The crystal structures of three conformations, T6, T3R3 and R6, of bovine insulin were solved at 1.40, 1.30 and 1.80 Å resolution, respectively. All conformations crystallized in space group R3. In contrast to the T6 and T3R3 structures, different conformations of the N-terminal B-chain residue Phe......B1 were observed in the R6 insulin structure, resulting in an eightfold doubling of the unit-cell volume upon cooling. The zinc coordination in each conformation was studied by X-ray absorption spectroscopy (XAS), including both EXAFS and XANES. Zinc adopts a tetrahedral coordination in all R3 sites...... molecules, as well as in other high-resolution insulin structures. As the radiation dose for XRD experiments is two orders of magnitude higher compared with that of XAS experiments, the single crystals were exposed to a higher degree of radiation damage that affected the zinc coordination in the T3 sites...

  14. Inhibition of the striatal specific phosphodiesterase PDE10A ameliorates striatal and cortical pathology in R6/2 mouse model of Huntington's disease.

    Directory of Open Access Journals (Sweden)

    Carmela Giampà

    2010-10-01

    Full Text Available Huntington's disease is a devastating neurodegenerative condition for which there is no therapy to slow disease progression. The particular vulnerability of striatal medium spiny neurons to Huntington's pathology is hypothesized to result from transcriptional dysregulation within the cAMP and CREB signaling cascades in these neurons. To test this hypothesis, and a potential therapeutic approach, we investigated whether inhibition of the striatal-specific cyclic nucleotide phosphodiesterase PDE10A would alleviate neurological deficits and brain pathology in a highly utilized model system, the R6/2 mouse.R6/2 mice were treated with the highly selective PDE10A inhibitor TP-10 from 4 weeks of age until euthanasia. TP-10 treatment significantly reduced and delayed the development of the hind paw clasping response during tail suspension, deficits in rotarod performance, and decrease in locomotor activity in an open field. Treatment prolonged time to loss of righting reflex. These effects of PDE10A inhibition on neurological function were reflected in a significant amelioration in brain pathology, including reduction in striatal and cortical cell loss, the formation of striatal neuronal intranuclear inclusions, and the degree of microglial activation that occurs in response to the mutant huntingtin-induced brain damage. Striatal and cortical levels of phosphorylated CREB and BDNF were significantly elevated.Our findings provide experimental support for targeting the cAMP and CREB signaling pathways and more broadly transcriptional dysregulation as a therapeutic approach to Huntington's disease. It is noteworthy that PDE10A inhibition in the R6/2 mice reduces striatal pathology, consistent with the localization of the enzyme in medium spiny neurons, and also cortical pathology and the formation of neuronal nuclear inclusions. These latter findings suggest that striatal pathology may be a primary driver of these secondary pathological events. More

  15. Comprehensive behavioral testing in the R6/2 mouse model of Huntington's disease shows no benefit from CoQ10 or minocycline.

    Directory of Open Access Journals (Sweden)

    Liliana B Menalled

    2010-03-01

    Full Text Available Previous studies of the effects of coenzyme Q10 and minocycline on mouse models of Huntington's disease have produced conflicting results regarding their efficacy in behavioral tests. Using our recently published best practices for husbandry and testing for mouse models of Huntington's disease, we report that neither coenzyme Q10 nor minocycline had significant beneficial effects on measures of motor function, general health (open field, rotarod, grip strength, rearing-climbing, body weight and survival in the R6/2 mouse model. The higher doses of minocycline, on the contrary, reduced survival. We were thus unable to confirm the previously reported benefits for these two drugs, and we discuss potential reasons for these discrepancies, such as the effects of husbandry and nutrition.

  16. Night blindness and abnormal cone electroretinogram ON responses in patients with mutations in the GRM6 gene encoding mGluR6

    Science.gov (United States)

    Dryja, Thaddeus P.; McGee, Terri L.; Berson, Eliot L.; Fishman, Gerald A.; Sandberg, Michael A.; Alexander, Kenneth R.; Derlacki, Deborah J.; Rajagopalan, Aruna S.

    2005-01-01

    We report three unrelated patients with mutations in the GRM6 gene that normally encodes the glutamate receptor mGluR6. This neurotransmitter receptor has been shown previously to be present only in the synapses of the ON bipolar cell dendrites, and it mediates synaptic transmission from rod and cone photoreceptors to this type of second-order neuron. Despite the synaptic defect, best visual acuities were normal or only moderately reduced (20/15 to 20/40). The patients were night blind from an early age, and when maximally dark-adapted, they could perceive lights only with an intensity equal to or slightly dimmer than that normally detected by the cone system (i.e., 2-3 log units above normal). Electroretinograms (ERGs) in response to single brief flashes of light had clearly detectable a-waves, which are derived from photoreceptors, and greatly reduced b-waves, which are derived from the second-order inner retinal neurons. ERGs in response to sawtooth flickering light indicated a markedly reduced ON response and a nearly normal OFF response. There was no subjective delay in the perception of suddenly appearing white vs. black objects on a gray background. These patients exemplify a previously unrecognized, autosomal recessive form of congenital night blindness associated with a negative ERG waveform. PMID:15781871

  17. Quantization Procedures

    International Nuclear Information System (INIS)

    Cabrera, J. A.; Martin, R.

    1976-01-01

    We present in this work a review of the conventional quantization procedure, the proposed by I.E. Segal and a new quantization procedure similar to this one for use in non linear problems. We apply this quantization procedures to different potentials and we obtain the appropriate equations of motion. It is shown that for the linear case the three procedures exposed are equivalent but for the non linear cases we obtain different equations of motion and different energy spectra. (Author) 16 refs

  18. Assessments of fluid friction factors for use in leak rate calculations

    Energy Technology Data Exchange (ETDEWEB)

    Chivers, T.C. [Berkeley Technology Centre, Glos (United Kingdom)

    1997-04-01

    Leak before Break procedures require estimates of leakage, and these in turn need fluid friction to be assessed. In this paper available data on flow rates through idealized and real crack geometries are reviewed in terms of a single friction factor k It is shown that for {lambda} < 1 flow rates can be bounded using correlations in terms of surface R{sub a} values. For {lambda} > 1 the database is less precise, but {lambda} {approx} 4 is an upper bound, hence in this region flow calculations can be assessed using 1 < {lambda} < 4.

  19. The nature thickness pipe element testing method to validate the application of LBB conception

    Energy Technology Data Exchange (ETDEWEB)

    Vasilchenko, G.S.; Artemyev, V.I.; Merinov, G.N. [and others

    1997-04-01

    To validate the application of leak before break analysis to the VVER-1000 reactor, a procedure for testing a large-scale specimen on electrohydraulic machinery was developed. Steel pipe with a circular weld and stainless cladding inside was manufactured and large-scale longitudinal cross-sections were cut. The remaining parts of the weld after cut out were used to determination standard tensile mechanical properties, critical temperature of brittlness and for manufacture of compact specimens. Experimental mechanical properties of the weld are summarized.

  20. The nature thickness pipe element testing method to validate the application of LBB conception

    International Nuclear Information System (INIS)

    Vasilchenko, G.S.; Artemyev, V.I.; Merinov, G.N.

    1997-01-01

    To validate the application of leak before break analysis to the VVER-1000 reactor, a procedure for testing a large-scale specimen on electrohydraulic machinery was developed. Steel pipe with a circular weld and stainless cladding inside was manufactured and large-scale longitudinal cross-sections were cut. The remaining parts of the weld after cut out were used to determination standard tensile mechanical properties, critical temperature of brittlness and for manufacture of compact specimens. Experimental mechanical properties of the weld are summarized

  1. Synthesis, NMR spectral and antimicrobial studies of some [N-methyl-3t-alkyl-2r,6c-diarylpiperidin-4-ylidine]-5‧-methylthiazolidine-4-ones

    Science.gov (United States)

    Prakash, S. M.; Pandiarajan, K.; Kumar, S.

    2013-06-01

    Four new [N-methyl-3t-alkyl-2r,6c-diaryl-4-ylidine]-5'-methylthiozolidin-4-ones 9-12 have been synthesized by the condensation of N-methyl-3t-alkyl-2r,6c-diarylpiperidin-4-one thiosemicarbazones with ethyl 2-bromopropionate. These compounds have been characterized using FT-IR, 1H NMR, 13C NMR spectral techniques. HOMOCOSY, HSQC and HMBC spectral study have been done for [N-methyl-3,3-dimethyl-2r,6c-bis(p-methoxyphenyl)piperidin-4-ylidine]-5'-methylthiazolidine-4-one (12). Two geometrical isomers are formed in this reaction. In all these compounds piperidin rings adopt chair conformation. The rotation of the aryl group at C-2 is rather slow in 10-12. Antimicrobial activities have also been studied for 9-12. These compounds are active against all the tested bacterial and fungal strains.

  2. Oral treatment with herbal formula B307 alleviates cardiac failure in aging R6/2 mice with Huntington’s disease via suppressing oxidative stress, inflammation, and apoptosis

    Directory of Open Access Journals (Sweden)

    Lin CL

    2015-07-01

    Full Text Available Ching-Lung Lin,1 Sheue-Er Wang,2 Chih-Hsiang Hsu,1 Shuenn-Jyi Sheu,3 Chung-Hsin Wu1 1Department of Life Science, National Taiwan Normal University, Taipei, 2Department of Pathological Inspection, Soeurs de Saint Paul de Chartres Medical Corporate Body, Taoyuan City, 3Brion Research Institute of Taiwan, New Taipei City, Taiwan Abstract: Cardiac failure is often observed in aging patients with Huntington’s disease (HD. However, conventional pharmacological treatments for cardiac failure in HD patients have rarely been studied. Chinese herbal medicines, especially combined herbal formulas, have been widely used to treat cardiac dysfunctions over the centuries. Thus, we assess whether oral treatment with herbal formula B307 can alleviate cardiac failure in transgenic mice with HD. After oral B307 or vehicle treatment for 2 weeks, cardiac function and cardiomyocytes in 12-week-old male R6/2 HD mice and their wild-type littermate controls (WT were examined and then compared via echocardiography, immunohistochemistry, and Western blotting. We found that cardiac performance in aging R6/2 HD mice had significantly deteriorated in comparison with their WT (P<0.01. Cardiac expressions of superoxide dismutase 2 (SOD2 and B-cell lymphoma 2 (Bcl-2 in aging R6/2 HD mice were significantly lower than their WT (P<0.01, but cardiac expressions of tumor necrosis factor alpha (TNF-α, neurotrophin-3 (3-NT, 4-hydroxynonenal (4-HNE, Bcl-2-associated X protein (Bax, calpain, caspase 12, caspase 9, and caspase 3 of aging R6/2 HD mice were significantly higher than their WT (P<0.05. Furthermore, we found that cardiac performance in aging R6/2 HD mice had significantly improved under oral B307 treatment (P<0.05. Cardiac expressions of SOD2 and Bcl-2 of aging R6/2 HD mice were significantly higher under oral B307 treatment (P<0.01, but cardiac expressions of TNF-α, 3-NT, 4-HNE, Bax, calpain, caspase 12, caspase 9, and caspase 3 of aging R6/2 HD mice were significantly

  3. Environmental procedures

    International Nuclear Information System (INIS)

    1992-01-01

    The European Bank has pledged in its Agreement to place environmental management at the forefront of its operations to promote sustainable economic development in central and eastern Europe. The Bank's environmental policy is set out in the document titled, Environmental Management: The Bank's Policy Approach. This document, Environmental Procedures, presents the procedures which the European Bank has adopted to implement this policy approach with respect to its operations. The environmental procedures aim to: ensure that throughout the project approval process, those in positions of responsibility for approving projects are aware of the environmental implications of the project, and can take these into account when making decisions; avoid potential liabilities that could undermine the success of a project for its sponsors and the Bank; ensure that environmental costs are estimated along with other costs and liabilities; and identify opportunities for environmental enhancement associated with projects. The review of environmental aspects of projects is conducted by many Bank staff members throughout the project's life. This document defines the responsibilities of the people and groups involved in implementing the environmental procedures. Annexes contain Environmental Management: The Bank's Policy Approach, examples of environmental documentation for the project file and other ancillary information

  4. A lead-before-break strategy for primary heat transport piping of 500 MWe Indian PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Chattopadhyay, J.; Dutta, B.K.; Kushwaha, H.S. [Bhabha Atomic Research Centre, Bombay (India)] [and others

    1997-04-01

    Leak-Before-Break (LBB) is being used to design the primary heat transport piping system of 500 MWe Indian Pressurized Heavy Water Reactors (IPHWR). The work is categorized in three directions to demonstrate three levels of safety against sudden catastrophic break. Level 1 is inherent in the design procedure of piping system as per ASME Sec.III with a well defined factor of safety. Level 2 consists of fatigue crack growth study of a postulated part-through flaw at the inside surface of pipes. Level 3 is stability analysis of a postulated leakage size flaw under the maximum credible loading condition. Developmental work related to demonstration of level 2 and level 3 confidence is described in this paper. In a case study on fatigue crack growth on PHT straight pipes for level 2, negligible crack growth is predicted for the life of the reactor. For level 3 analysis, the R6 method has been adopted. A database to evaluate SIF of elbows with throughwall flaws under combined internal pressure and bending moment has been generated to provide one of the inputs for R6 method. The methodology of safety assessment of elbow using R6 method has been demonstrated for a typical pump discharge elbow. In this analysis, limit load of the cracked elbow has been determined by carrying out elasto-plastic finite element analysis. The limit load results compared well with those given by Miller. However, it requires further study to give a general form of limit load solution. On the experimental front, a set of small diameter pipe fracture experiments have been carried out at room temperature and 300{degrees}C. Two important observations of the experiments are - appreciable drop in maximum load at 300{degrees}C in case of SS pipes and out-of-plane crack growth in case of CS pipes. Experimental load deflection curves are finally compared with five J-estimation schemes predictions. A material database of PHT piping materials is also being generated for use in LBB analysis.

  5. A lead-before-break strategy for primary heat transport piping of 500 MWe Indian PHWR

    International Nuclear Information System (INIS)

    Chattopadhyay, J.; Dutta, B.K.; Kushwaha, H.S.

    1997-01-01

    Leak-Before-Break (LBB) is being used to design the primary heat transport piping system of 500 MWe Indian Pressurized Heavy Water Reactors (IPHWR). The work is categorized in three directions to demonstrate three levels of safety against sudden catastrophic break. Level 1 is inherent in the design procedure of piping system as per ASME Sec.III with a well defined factor of safety. Level 2 consists of fatigue crack growth study of a postulated part-through flaw at the inside surface of pipes. Level 3 is stability analysis of a postulated leakage size flaw under the maximum credible loading condition. Developmental work related to demonstration of level 2 and level 3 confidence is described in this paper. In a case study on fatigue crack growth on PHT straight pipes for level 2, negligible crack growth is predicted for the life of the reactor. For level 3 analysis, the R6 method has been adopted. A database to evaluate SIF of elbows with throughwall flaws under combined internal pressure and bending moment has been generated to provide one of the inputs for R6 method. The methodology of safety assessment of elbow using R6 method has been demonstrated for a typical pump discharge elbow. In this analysis, limit load of the cracked elbow has been determined by carrying out elasto-plastic finite element analysis. The limit load results compared well with those given by Miller. However, it requires further study to give a general form of limit load solution. On the experimental front, a set of small diameter pipe fracture experiments have been carried out at room temperature and 300 degrees C. Two important observations of the experiments are - appreciable drop in maximum load at 300 degrees C in case of SS pipes and out-of-plane crack growth in case of CS pipes. Experimental load deflection curves are finally compared with five J-estimation schemes predictions. A material database of PHT piping materials is also being generated for use in LBB analysis

  6. Rational design and enantioselective synthesis of (1R,4S,5R,6S)-3-azabicyclo[3.3.0]octane-4,6-dicarboxylic acid - a novel inhibitor at human glutamate transporter subtypes 1, 2, and 3

    DEFF Research Database (Denmark)

    Bunch, Lennart; Nielsen, Birgitte; Jensen, Anders A.

    2006-01-01

    The natural product kainic acid is used as template for the rational design of a novel conformationally restricted (S)-glutamic acid (Glu) analogue, (1R,4S,5R,6S)-3-azabicyclo[3.3.0]octane-4,6-dicarboxylic acid (1a). The target structure 1a was synthesized from commercially available (S)-pyroglut......The natural product kainic acid is used as template for the rational design of a novel conformationally restricted (S)-glutamic acid (Glu) analogue, (1R,4S,5R,6S)-3-azabicyclo[3.3.0]octane-4,6-dicarboxylic acid (1a). The target structure 1a was synthesized from commercially available (S...

  7. Enantioselective synthesis of (+-polyzonimine, defensive monoterpene alkaloid produced by a milliped Polyzonium rosalbum, and determination of its S absolute configuration by Its conversion to (4S,5R,6S-(+-nitropolyzonamine

    Directory of Open Access Journals (Sweden)

    Takagi Yasuyo

    2000-01-01

    Full Text Available Asymmetric Michael addition of the enamine derived from 2,2-dimethylcyclopentanecarbox-aldehyde and (S-prolinol methyl ether to nitroethylene afforded the adduct of 75-76% ee, which finally yielded enantiomerically pure (+-polyzonimine, a nitrogen-containing spirocyclic compound isolated from the defensive glands of a milliped, Polyzonium rosalbum. By converting (+-polyzonimine into (4S,5R,6S-(+-nitropolyzonamine, the hitherto uncertain absolute configuration of the former was established as S.

  8. Radiochemical procedures

    International Nuclear Information System (INIS)

    Lyon, W.S.

    1982-01-01

    The modern counting instrumentation has largely obviated the need for separation processes in the radiochemical analysis but problems in low-level radioactivity measurement, environmental-type analyses, and special situations caused in the last years a renaissance of the need for separation techniques. Most of the radiochemical procedures, based on the classic works of the Manhattan Project chemists of the 1940's, were published in the National Nuclear Energy Series (NNES). Improvements such as new solvent extraction and ion exchange separations have been added to these methods throughout the years. Recently the Los Alamos Group have reissued their collected Radiochemical Procedures containing a short summary and review of basic inorganic chemistry - 'Chemistry of the Elements on the Basis of Electronic Configuration'. (A.L.)

  9. Pretreatment procedures

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    It is frequently in the patient's best interest that radiation treatments are initiated soon after the decision to treat is made. However, it is essential to good radiation therapy that the patient's treatment course be planned and beam-modifying devices be fabricated with utmost care prior to treatment. The objectives of the treatment, along with the treatment parameters and techniques necessary to achieve these objectives, must be discussed prior to initiating planning procedures. Determination of the target volume is made by the radiation oncologist; this is based on knowledge of the history of the tumor, the patterns of spread of the disease, and on diagnostic findings during the work-up of each patient. It is then necessary to obtain several measurements of the patient and also to identify the position of the target volume and of adjacent normal organs with respect to known external skin marks before the actual treatment planning is begun. Such localization can be done through several methods. The two most commonly used methods are radiographic and computed tomography (CT), both of which are discussed in this chapter. The measurements often include contours of the patient's external surface, usually in the axial plane of the central axis of the beam, and often in multiple levels within the region to be treated. Three dimensional localization and treatment planning requires thorough understanding of geometry as well as of patient positioning and immobilization. This chapter attempts to clarify some of these complicated but essential preparations for treatment

  10. The mTOR kinase inhibitor Everolimus decreases S6 kinase phosphorylation but fails to reduce mutant huntingtin levels in brain and is not neuroprotective in the R6/2 mouse model of Huntington's disease

    Directory of Open Access Journals (Sweden)

    Frentzel Stefan

    2010-06-01

    Full Text Available Abstract Background Huntington's disease (HD is a progressive neurodegenerative disorder caused by a CAG repeat expansion within the huntingtin gene. Mutant huntingtin protein misfolds and accumulates within neurons where it mediates its toxic effects. Promoting mutant huntingtin clearance by activating macroautophagy is one approach for treating Huntington's disease (HD. In this study, we evaluated the mTOR kinase inhibitor and macroautophagy promoting drug everolimus in the R6/2 mouse model of HD. Results Everolimus decreased phosphorylation of the mTOR target protein S6 kinase indicating brain penetration. However, everolimus did not activate brain macroautophagy as measured by LC3B Western blot analysis. Everolimus protected against early declines in motor performance; however, we found no evidence for neuroprotection as determined by brain pathology. In muscle but not brain, everolimus significantly decreased soluble mutant huntingtin levels. Conclusions Our data suggests that beneficial behavioral effects of everolimus in R6/2 mice result primarily from effects on muscle. Even though everolimus significantly modulated its target brain S6 kinase, this did not decrease mutant huntingtin levels or provide neuroprotection.

  11. Residual stress effects in LMFBR fracture assessment procedures

    International Nuclear Information System (INIS)

    Hooton, D.G.

    1984-01-01

    Two post-yield fracture mechanics methods, which have been developed into fully detailed failure assessment procedures for ferritic structures, have been reviewed from the point of view of the manner in which as-welded residual stress effects are incorporated, and comparisons then made with finite element and theoretical models of centre-cracked plates containing residual/thermal stresses in the form of crack-driving force curves. Applying the procedures to austenitic structures, comparisons are made in terms of failure assessment curves and it is recommended that the preferred method for the prediction of critical crack sizes in LMFBR austenitic structures containing as-welded residual stresses is the CEGB-R6 procedure based on a flow stress defined at 3% strain in the parent plate. When the prediction of failure loads in such structures is required, it is suggested that the CEGB-R6 procedure be used with residual/thermal stresses factored to give a maximum total stress of flow stress magnitude

  12. An efficient conversion of (3R,3'R,6'R)-lutein to (3R,3'S,6'R)-lutein (3'-epilutein) and (3R,3'R)-zeaxanthin.

    Science.gov (United States)

    Khachik, Frederick

    2003-01-01

    Two dietary carotenoids, (3R,3'R,6'R)-lutein (1) and (3R,3'R)-zeaxanthin (2), and their metabolite (3R,3'S,6'R)-lutein (3'-epilutein) (3) accumulate in human serum, milk, and ocular tissues. There is increasing evidence that compounds 1 and 2 play an important role in the prevention of age-related macular degeneration. Therefore, the availability of these carotenoids for metabolic studies and clinical trials is essential. Compound 1 is isolated from extracts of marigold flowers (Tagete erecta) and is commercially available, whereas 2 is only accessible by a lengthy total synthesis, and a viable method for synthesis of 3 has not yet been developed. This report describes an efficient conversion of technical grade 1 to 2 via 3. Acid-catalyzed epimerization of 1 yields an equimolar mixture of diastereomers 1 and 3. The mixture was separated by enzyme-mediated acylation with lipase AK from Pseudomonas fluorescens that preferentially esterified 3 and after alkaline hydrolysis yielded this carotenoid in 90% diastereomeric excess (de). Compound 3 was also separated from 1 in 56-88% de by solvent extraction and low-temperature crystallization, Soxhlet extraction, or supercritical fluid extraction. Base-catalyzed isomerization of 3 gave 2 in excellent yield, providing a convenient alternative to the total synthesis of this important dietary carotenoid.

  13. HASL procedures manual

    International Nuclear Information System (INIS)

    Harley, J.H.

    1977-08-01

    Additions and corrections to the following sections of the HASL Procedures Manual are provided: General, Sampling, Field Measurements; General Analytical Chemistry, Chemical Procedures, Data Section, and Specifications

  14. Análisis de incertidumbre en calibración de medidores de presión según DKD-R 6-1. Cinco métodos de cálculo

    Directory of Open Access Journals (Sweden)

    Luis Pablo Constantino

    2014-12-01

    Full Text Available Este trabajo presenta un estudio de las contribuciones de incertidumbre e incertidumbre expandida que tienen lugar en la calibración de un medidor digital de presión por comparación directa con una balanza de presión. Se discute la ecuación propuesta por la guía DKD-R 6-1 para la estimación de incertidumbre, según plataforma GUM y Monte Carlo, proponiendo un modelo alternativo. Se determinan las diferencias que existen en las incertidumbres resultantes obtenidas  según estos métodos y en qué forma los distintos componentes del modelo influyen en estas diferencias, según la magnitud de su incertidumbre estándar y la distribución de probabilidad (DDP asociada que se le asigna.El desarrollo se realiza según el método GUM utilizando la metodología analítica. Adicionalmente  se repite el ejercicio en forma comparativa utilizando cuatro diferentes herramientas de cálculo. Dos de estas herramientas están basadas en aproximaciones numéricas del método clásico: software GUM Workbench © y método numérico de Kragten. Las otras dos son consistentes con el suplemento 1 de la Guía de la Expresión de la Incertidumbre de Medida según el método de Monte Carlo (MCM. en un caso el lenguaje R y por otra parte MCM Alchimia, aplicación desarrollada por uno de los autores.  

  15. Computer assisted procedure maintenance

    International Nuclear Information System (INIS)

    Bisio, R.; Hulsund, J. E.; Nilsen, S.

    2004-04-01

    The maintenance of operating procedures in a NPP is a tedious and complicated task. Through the whole life cycle of the procedures they will be dynamic, 'living' documents. Several aspects of the procedure must be considered in a revision process. Pertinent details and attributes of the procedure must be checked. An organizational structure must be created and responsibilities allotted for drafting, revising, reviewing and publishing procedures. Available powerful computer technology provides solutions within document management and computerisation of procedures. These solutions can also support the maintenance of procedures. Not all parts of the procedure life cycle are equally amenable to computerized support. This report looks at the procedure life cycle in todays NPPs and discusses the possibilities associated with introduction of computer technology to assist the maintenance of procedures. (Author)

  16. Application of break preclusion concept in German nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Roos, E. [Energie-Versorgung Schwaben AG, Stuttgart (Germany); Maier, V. [Bayernwerk AG, Muenchen (Germany); Nagel, G. [PraussenElektra AG, Hannover (Germany)] [and others

    1997-04-01

    The break preclusion concept is based on {open_quotes}KTA rules{close_quotes}, {open_quotes}RSK guidelines{close_quotes} and {open_quotes}Rahmenspeziflkation Basissicherheit{close_quotes}. These fundamental rules containing for example requirements on material, design, calculation, manufacturing and testing procedures are explained and the technical realisation is shown by means of examples. The proof of the quality of these piping systems can be executed by means of fracture mechanics calculations by showing that in every case the leakage monitoring system already detect cracks which are clearly smaller than the critical crack. Thus the leak before break behavior and the break preclusion concept is implicitly affirmed. In order to further diminish conservativities in the fracture mechanics procedures, specific research projects are executed which are explained in this contribution.

  17. Computerized procedures system

    Science.gov (United States)

    Lipner, Melvin H.; Mundy, Roger A.; Franusich, Michael D.

    2010-10-12

    An online data driven computerized procedures system that guides an operator through a complex process facility's operating procedures. The system monitors plant data, processes the data and then, based upon this processing, presents the status of the current procedure step and/or substep to the operator. The system supports multiple users and a single procedure definition supports several interface formats that can be tailored to the individual user. Layered security controls access privileges and revisions are version controlled. The procedures run on a server that is platform independent of the user workstations that the server interfaces with and the user interface supports diverse procedural views.

  18. Human factoring administrative procedures

    International Nuclear Information System (INIS)

    Grider, D.A.; Sturdivant, M.H.

    1991-01-01

    In nonnuclear business, administrative procedures bring to mind such mundane topics as filing correspondence and scheduling vacation time. In the nuclear industry, on the other hand, administrative procedures play a vital role in assuring the safe operation of a facility. For some time now, industry focus has been on improving technical procedures. Significant efforts are under way to produce technical procedure requires that a validated technical, regulatory, and administrative basis be developed and that the technical process be established for each procedure. Producing usable technical procedures requires that procedure presentation be engineered to the same human factors principles used in control room design. The vital safety role of administrative procedures requires that they be just as sound, just a rigorously formulated, and documented as technical procedures. Procedure programs at the Tennessee Valley Authority and at Boston Edison's Pilgrim Station demonstrate that human factors engineering techniques can be applied effectively to technical procedures. With a few modifications, those same techniques can be used to produce more effective administrative procedures. Efforts are under way at the US Department of Energy Nuclear Weapons Complex and at some utilities (Boston Edison, for instance) to apply human factors engineering to administrative procedures: The techniques being adapted include the following

  19. Procedures in diagnostic radiology

    International Nuclear Information System (INIS)

    Doyle, T.; Hare, W.S.C.; Thomson, K.; Tess, B.

    1989-01-01

    This book outlines the various procedures necessary for the successful practice of diagnostic radiology. Topics covered are: general principles, imaging of the urinary and gastrointestinal tracts, vascular radiology, arthrography, and miscellaneous diagnostic radiologic procedures

  20. Procedural Media Representation

    OpenAIRE

    Henrysson, Anders

    2002-01-01

    We present a concept for using procedural techniques to represent media. Procedural methods allow us to represent digital media (2D images, 3D environments etc.) with very little information and to render it photo realistically. Since not all kind of content can be created procedurally, traditional media representations (bitmaps, polygons etc.) must be used as well. We have adopted an object-based media representation where an object can be represented either with a procedure or with its trad...

  1. Classification of radiological procedures

    International Nuclear Information System (INIS)

    1989-01-01

    A classification for departments in Danish hospitals which use radiological procedures. The classification codes consist of 4 digits, where the first 2 are the codes for the main groups. The first digit represents the procedure's topographical object and the second the techniques. The last 2 digits describe individual procedures. (CLS)

  2. CANDU pressure tube leak detection by annulus gas dew point measurement. A critical review

    Energy Technology Data Exchange (ETDEWEB)

    Greening, F.R. [CTS-NA, Tiverton, ON (Canada)

    2017-03-15

    In the event of a pressure tube leak from a small through-wall crack during CANDU reactor operations, there is a regulatory requirement - referred to as Leak Before Break (LBB) - for the licensee to demonstrate that there will be sufficient time for the leak to be detected and the reactor shut down before the crack grows to the critical size for fast-uncontrolled rupture. In all currently operating CANDU reactors, worldwide, this LBB requirement is met via continuous dew point measurements of the CO{sub 2} gas circulating in the reactor's Annulus Gas System (AGS). In this paper the historical development and current status of this leak detection capability is reviewed and the use of moisture injection tests as a verification procedure is critiqued. It is concluded that these tests do not represent AGS conditions that are to be expected in the event of a real pressure tube leak.

  3. Development of technology on the material surveillance of CANDU pressure tubes

    Energy Technology Data Exchange (ETDEWEB)

    Noh, Kye Hoh; Han, Jung Hoh; Lee, Duk Hyun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-05-01

    Material degradation of pressure tubes, which are the most important components in CANDU fuel channel, can only be evaluated by removing and examining them(material surveillance). This study aimed at establishment of overall evaluation technology including the evaluation of the material degradation for the integrity of pressure tubes of Wolsung units. Material tests for pressure tubes were performed as follows; (1) Evaluation on life limiting factors of pressure tubes (2) Review on leak-before-break and integrity maintenance technology of pressure tubes (3) Survey on selection criteria for tubes to be inspected and on related regulations for material surveillance (4) Analysis of material surveillance test procedure (5) Basic examinations of Wolsung unit 1 pressure tube material(TEM, texture, chemical component etc) (6) Manufacture of test equipments and test (DHCV, hydriding, grip and tensile specimen etc). 23 figs, 6 tabs, 59 refs. (Author).

  4. CANDU pressure tube leak detection by annulus gas dew point measurement. A critical review

    International Nuclear Information System (INIS)

    Greening, F.R.

    2017-01-01

    In the event of a pressure tube leak from a small through-wall crack during CANDU reactor operations, there is a regulatory requirement - referred to as Leak Before Break (LBB) - for the licensee to demonstrate that there will be sufficient time for the leak to be detected and the reactor shut down before the crack grows to the critical size for fast-uncontrolled rupture. In all currently operating CANDU reactors, worldwide, this LBB requirement is met via continuous dew point measurements of the CO_2 gas circulating in the reactor's Annulus Gas System (AGS). In this paper the historical development and current status of this leak detection capability is reviewed and the use of moisture injection tests as a verification procedure is critiqued. It is concluded that these tests do not represent AGS conditions that are to be expected in the event of a real pressure tube leak.

  5. Development of technology on the material surveillance of CANDU pressure tubes

    International Nuclear Information System (INIS)

    Noh, Kye Hoh; Han, Jung Hoh; Lee, Duk Hyun

    1995-05-01

    Material degradation of pressure tubes, which are the most important components in CANDU fuel channel, can only be evaluated by removing and examining them(material surveillance). This study aimed at establishment of overall evaluation technology including the evaluation of the material degradation for the integrity of pressure tubes of Wolsung units. Material tests for pressure tubes were performed as follows; (1) Evaluation on life limiting factors of pressure tubes (2) Review on leak-before-break and integrity maintenance technology of pressure tubes (3) Survey on selection criteria for tubes to be inspected and on related regulations for material surveillance (4) Analysis of material surveillance test procedure (5) Basic examinations of Wolsung unit 1 pressure tube material(TEM, texture, chemical component etc) (6) Manufacture of test equipments and test (DHCV, hydriding, grip and tensile specimen etc). 23 figs, 6 tabs, 59 refs. (Author)

  6. Evaluation of throughwall crack pipes under displacement controlled loading

    Energy Technology Data Exchange (ETDEWEB)

    Zahoor, A.

    1987-02-01

    Tearing modulus solutions are developed for flawed throughwall pipes subjected to displacement controlled loading. Two cases of loading were considered: (1) a displacement controlled bending loading, and (2) a displacement controlled axial tension loading. A revised version of the EPRI J-integral estimation scheme is used in the development of the solutions. These solutions can be used for the entire range of elastic-plastic loading, from linear elastic, contained yielding, to large scale yielding of the crack section. Experimental data from pipes in bending were used to assess the accuracy of the compliant loading solutions. The evaluations were performed using elastic plastic J-integral (J) and tearing modulus (T) analysis methods. These solutions are shown to have good accuracy when used to predict the experimental results. The methodology and procedure can also be applied to part-throughwall cracks. These solutions have application to the leak before break fracture mechanics analyses.

  7. Evaluation of J-integral estimation scheme for flawed throughwall pipes

    Energy Technology Data Exchange (ETDEWEB)

    Zahoor, A.

    1987-02-01

    The accuracy of the EPRI J-integral estimation scheme for pipes with throughwall cracks and subjected to pure bending was assessed using available experimental data on circumferentially flawed throughwall pipes. The evaluations were performed using elastic plastic J-integral (J) and tearing modulus (T) analysis methods. The results indicated that the EPRI J estimation scheme solutions are unnecessarily conservative compared to results from pipe experiments. As a result of these evaluations an improved J estimation scheme is developed, which is shown to have improved accuracy compared to the original EPRI J estimation scheme. These results imply that the flaw evaluation procedures in the ASME Code on austenitic piping welds are conservative. These results also have applications to the leak before break fracture mechanics analyses.

  8. Evaluation of throughwall crack pipes under displacement controlled loading

    International Nuclear Information System (INIS)

    Zahoor, A.

    1987-01-01

    Tearing modulus solutions are developed for flawed throughwall pipes subjected to displacement controlled loading. Two cases of loading were considered: (1) a displacement controlled bending loading, and (2) a displacement controlled axial tension loading. A revised version of the EPRI J-integral estimation scheme is used in the development of the solutions. These solutions can be used for the entire range of elastic-plastic loading, from linear elastic, contained yielding, to large scale yielding of the crack section. Experimental data from pipes in bending were used to assess the accuracy of the compliant loading solutions. The evaluations were performed using elastic plastic J-integral (J) and tearing modulus (T) analysis methods. These solutions are shown to have good accuracy when used to predict the experimental results. The methodology and procedure can also be applied to part-throughwall cracks. These solutions have application to the leak before break fracture mechanics analyses. (orig.)

  9. Evaluation of J-integral estimation scheme for flawed throughwall pipes

    International Nuclear Information System (INIS)

    Zahoor, A.

    1987-01-01

    The accuracy of the EPRI J-integral estimation scheme for pipes with throughwall cracks and subjected to pure bending was assessed using available experimental data on circumferentially flawed throughwall pipes. The evaluations were performed using elastic plastic J-integral (J) and tearing modulus (T) analysis methods. The results indicated that the EPRI J estimation scheme solutions are unnecessarily conservative compared to results from pipe experiments. As a result of these evaluations an improved J estimation scheme is developed, which is shown to have improved accuracy compared to the original EPRI J estimation scheme. These results imply that the flaw evaluation procedures in the ASME Code on austenitic piping welds are conservative. These results also have applications to the leak before break fracture mechanics analyses. (orig.)

  10. Procedure generation and verification

    International Nuclear Information System (INIS)

    Sheely, W.F.

    1986-01-01

    The Department of Energy has used Artificial Intelligence of ''AI'' concepts to develop two powerful new computer-based techniques to enhance safety in nuclear applications. The Procedure Generation System, and the Procedure Verification System, can be adapted to other commercial applications, such as a manufacturing plant. The Procedure Generation System can create a procedure to deal with the off-normal condition. The operator can then take correct actions on the system in minimal time. The Verification System evaluates the logic of the Procedure Generator's conclusions. This evaluation uses logic techniques totally independent of the Procedure Generator. The rapid, accurate generation and verification of corrective procedures can greatly reduce the human error, possible in a complex (stressful/high stress) situation

  11. A procedure for safety assessment of components with cracks - Handbook

    International Nuclear Information System (INIS)

    Andersson, P.; Bergman, M.; Brickstad, B.; Dahlberg, L.; Nilsson, F.; Sattari-Far, I.

    1996-01-01

    In this handbook a procedure is described which can be used both for assessment of detected cracks or crack like defects or for defect tolerance analysis. The procedure can be used to calculate possible crack growth due to fatigue or stress corrosion and to calculate the reserve margin for failure due to fracture and plastic collapse. For ductile materials, the procedure gives the reserve margin for initiation of stable crack growth. Thus, an extra reserve margin, unknown to size, exists for failure in components made of ductile materials. The procedure was developed for operative use with the following objectives in mind: The procedure should be able to handle both linear and non-linear problems without any a priori division; The procedure shall ensure uniqueness of the safety assessment; The procedure should be well defined and easy to use; The conservatism of the procedure should be well validated; The handbook that documents the procedure should be so complete that for most assessments access to any other fracture mechanics literature should not be necessary. The method utilized is based on the R6-method developed at Nuclear Electric plc. This method can in principle be used for all metallic materials. It is, however, more extensively verified for steel alloys only. The method is not intended for use in temperatures where creep deformation is of importance. The first edition of the handbook was released in 1990 and the second in 1991. This third edition has been extensively revised. A Windows-based program (SACC) has been developed which can perform the assessments described in the book including calculation of crack growth due to stress corrosion and fatigue. 52 refs., 27 figs., 35 tabs

  12. Approach of Czech regulatory body to LBB

    Energy Technology Data Exchange (ETDEWEB)

    Tendera, P.

    1997-04-01

    At present there are two NPPs equipped with PWR units in Czech Republic. The Dukovany, NPP is about ten years in operation (four units 440 MW - WWBFL model 213) and Tomelin NPP is under construction (two units 1000 MW - WWER model 320). Both NPPs were built to Soviet design and according to Soviet regulations and standards but most of equipment for primary circuits was supplied by home manufacturers. The objective of the Czech LBB program is to prove the LBB status of the primary piping systems of there NPPs and the LBB concept is a part of strategy to meet western style safety standards. The reason for the Czech LBB project is a lack of some standard safety Facilities too. For both Dukovany and Tomelin NPPs a full LBB analysis should be carried out. The application of LBB to the piping system should be also a cost effective means to avoid installations of pipe whip restraints and jet shields. The Czech regulatory body issued non-mandatory requirement, {open_quotes}Leak Before Break{close_quotes} which is in compliance with national legal documents and which is based on the US NRC Regulatory Procedures and US standards (ASMF CODE, ANSI). The requirement has been published in the document {open_quotes}Safety of Nuclear Facilities{close_quotes} No 1/1991 as {open_quotes}Requirements on the Content and Format of Safety Reports and their Supplements{close_quote} and consist of two parts (1) procedure for obtaining proof of evidence {open_quotes}Leak Before Break{close_quotes} (2) leak detection systems for the pressurized reactor primary circuit. At present some changes concerning both parts of the above document will be introduced. The reasons for this modifications will be presented.

  13. Approach for Czech regulatory body to LBB

    Energy Technology Data Exchange (ETDEWEB)

    Tendera, P. [State Office for Nuclear Safety (SONS), Prague (Czech Republic)

    1997-04-01

    At present there are two NPPs equipped with PWR units in Czech Republic. The Dukovany NPP is about ten years in operation (four units 440 MW - WWER model 213) and Temelin NPP is under construction (two units 1000 MW-WWER model 320). Both NPPs were built to Soviet design and according to Soviet regulations and standards but most of equipment for primary circuits was supplied by home manufactures. The objective for the Czech LBB programme is to prove the LBB status of the primary piping systems of these NPPs and the LBB concept is a part of strategy to meet western style safety standards. The reason for the Czech LBB project is a lack of some standard safety facilities, too. For both Dukovany and Temolin NPPs a full LBB analysis should be carried out. The application of LBB to the piping system should be also a cost effective means to avoid installations of pipe whip restraints and jet shields. The Czech regulatory body issued non-mandatory requirement {open_quotes}Leak Before Break{close_quotes} which is in compliance with national legal documents and which is based on the US NRC Regulatory Procedures and US standards (ASME, CODE, ANSI). The requirement has been published in the document {open_quotes}Safety of Nuclear Facilities{close_quotes} No. 1/1991 as {open_quotes}Requirements on the Content and Format of Safety Reports and their Supplements{close_quotes} and consists of two parts (1) procedure for obtaining proof of evidence {open_quotes}Leak Before Break{close_quotes} (2) leak detection systems for the pressurized reactor primary circuit. At present some changes concerning both parts of the above document will be introduced. The reasons for this modifications will be presented.

  14. Civil Procedure In Denmark

    DEFF Research Database (Denmark)

    Werlauff, Erik

    scientific activities conducted by the author, partly based on the author's experience as a member, through a number of years, of the Danish Standing Committee on Procedural Law (Retsplejeraadet), which on a continuous basis evaluates the need for civil procedural reforms in Denmark, and finally also based......The book contains an up-to-date survey of Danish civil procedure after the profound Danish procedural reforms in 2007. It deals with questions concerning competence and function of Danish courts, commencement and preparation of civil cases, questions of evidence and burden of proof, international...... procedural questions, including relations to the Brussels I Regulation and Denmark's participation in this Regulation via a parallel convention with the EU countries, impact on Danish civil procedure of the convention on human rights, preparation and pronouncement of judgment and verdict, questions of appeal...

  15. Spline-procedures

    International Nuclear Information System (INIS)

    Schmidt, R.

    1976-12-01

    This report contains a short introduction to spline functions as well as a complete description of the spline procedures presently available in the HMI-library. These include polynomial splines (using either B-splines or one-sided basis representations) and natural splines, as well as their application to interpolation, quasiinterpolation, L 2 -, and Tchebycheff approximation. Special procedures are included for the case of cubic splines. Complete test examples with input and output are provided for each of the procedures. (orig.) [de

  16. Procedural sedation analgesia

    OpenAIRE

    Sheta, Saad A

    2010-01-01

    The number of noninvasive and minimally invasive procedures performed outside of the operating room has grown exponentially over the last several decades. Sedation, analgesia, or both may be needed for many of these interventional or diagnostic procedures. Individualized care is important when determining if a patient requires procedural sedation analgesia (PSA). The patient might need an anti-anxiety drug, pain medicine, immobilization, simple reassurance, or a combination of these interve...

  17. Handbook of radiologic procedures

    International Nuclear Information System (INIS)

    Hedgcock, M.

    1986-01-01

    This book is organized around radiologic procedures with each discussed from the points of view of: indications, contraindications, materials, method of procedures and complications. Covered in this book are: emergency radiology chest radiology, bone radiology, gastrointestinal radiology, GU radiology, pediatric radiology, computerized tomography, neuroradiology, visceral and peripheral angiography, cardiovascular radiology, nuclear medicine, lymphangiography, and mammography

  18. Decision-making Procedures

    DEFF Research Database (Denmark)

    Aldashev, Gani; Kirchsteiger, Georg; Sebald, Alexander Christopher

    2009-01-01

    define procedures as mechanisms that influence the probabilities of reaching different endnodes. We show that for such procedural games a sequential psychological equilibrium always exists. Applying this approach within a principal-agent context we show that the way less attractive jobs are allocated...

  19. Maintenance procedure upgrade programs

    International Nuclear Information System (INIS)

    Campbell, J.J.; Zimmerman, C.M.

    1988-01-01

    This paper describes a systematic approach to upgrading nuclear power plant maintenance procedures. The approach consists of four phases: diagnosis, program planning, program implementation, and program evaluation. Each phase is explained as a series of steps to ensure that all factors in a procedure upgrade program are considered

  20. Actor-Network Procedures

    NARCIS (Netherlands)

    Pavlovic, Dusko; Meadows, Catherine; Ramanujam, R.; Ramaswamy, Srini

    2012-01-01

    In this paper we propose actor-networks as a formal model of computation in heterogenous networks of computers, humans and their devices, where these new procedures run; and we introduce Procedure Derivation Logic (PDL) as a framework for reasoning about security in actor-networks, as an extension

  1. Analytical procedures. Pt. 1

    International Nuclear Information System (INIS)

    Weber, G.

    1985-01-01

    In analytical procedures (Boole procedures) there is certain to be a close relationship between the safety assessment and reliability assessment of technical facilities. The paper gives an overview of the organization of models, fault trees, the probabilistic evaluation of systems, evaluation with minimum steps or minimum paths regarding statistically dependent components and of systems liable to suffer different kinds of outages. (orig.) [de

  2. Play vs. Procedures

    DEFF Research Database (Denmark)

    Hammar, Emil

    Through the theories of play by Gadamer (2004) and Henricks (2006), I will show how the relationship between play and game can be understood as dialectic and disruptive, thus challenging understandings of how the procedures of games determine player activity and vice versa. As such, I posit some...... analytical consequences for understandings of digital games as procedurally fixed (Boghost, 2006; Flannagan, 2009; Bathwaite & Sharp, 2010). That is, if digital games are argued to be procedurally fixed and if play is an appropriative and dialectic activity, then it could be argued that the latter affects...... and alters the former, and vice versa. Consequently, if the appointed procedures of a game are no longer fixed and rigid in their conveyance of meaning, qua the appropriative and dissolving nature of play, then understandings of games as conveying a fixed meaning through their procedures are inadequate...

  3. HASL procedures manual

    International Nuclear Information System (INIS)

    1980-08-01

    Addition and corrections to the following sections of the HASL Procedures Manual are provided: Table of Contents; Bibliography; Fallout Collection Methods; Wet/Dry Fallout Collection; Fluoride in Soil and Sediment; Strontium-90; Natural Series; Alpha Emitters; and Gamma Emitters

  4. EML procedures manual

    International Nuclear Information System (INIS)

    Volchok, H.L.; de Planque, G.

    1982-01-01

    This manual contains the procedures that are used currently by the Environmental Measurements Laboratory of the US Department of Energy. In addition a number of analytical methods from other laboratories have been included. These were tested for reliability at the Battelle, Pacific Northwest Laboratory under contract with the Division of Biomedical and Environmental Research of the AEC. These methods are clearly distinguished. The manual is prepared in loose leaf form to facilitate revision of the procedures and inclusion of additional procedures or data sheets. Anyone receiving the manual through EML should receive this additional material automatically. The contents are as follows: (1) general; (2) sampling; (3) field measurements; (4) general analytical chemistry; (5) chemical procedures; (6) data section; (7) specifications

  5. Cosmetic Procedure Questions

    Science.gov (United States)

    ... for Every Season How to Choose the Best Skin Care Products In This Section Dermatologic Surgery What is dermatologic ... for Every Season How to Choose the Best Skin Care Products Cosmetic Procedure Questions Want to look younger? Start ...

  6. Modified arthroscopic Brostrom procedure.

    Science.gov (United States)

    Lui, Tun Hing

    2015-09-01

    The open modified Brostrom anatomic repair technique is widely accepted as the reference standard for lateral ankle stabilization. However, there is high incidence of intra-articular pathologies associated with chronic lateral ankle instability which may not be addressed by an isolated open Brostrom procedure. Arthroscopic Brostrom procedure with suture anchor has been described for anatomic repair of chronic lateral ankle instability and management of intra-articular lesions. However, the complication rates seemed to be higher than open Brostrom procedure. Modification of the arthroscopic Brostrom procedure with the use of bone tunnel may reduce the risk of certain complications. Copyright © 2015 European Foot and Ankle Society. Published by Elsevier Ltd. All rights reserved.

  7. Assisted Medical Procedures (AMP)

    Data.gov (United States)

    National Aeronautics and Space Administration — DOCUMENTATION, DEVELOPMENT, AND PROGRESS The AMP was initially being developed as part the Advanced Integrated Clinical System (AICS)-Guided Medical Procedure System...

  8. Cosmetic Procedure Questions

    Science.gov (United States)

    ... Back Injectable Deoxycholic Acid Injectable Hyaluronic Acid Injectable Poly-l-lactic Acid Injectable Polymethylmethacrylate + Bovine Collagen Filler ... time of their procedure. 6. What are my pain management and anesthesia options? To help avoid the ...

  9. Special Blood Donation Procedures

    Science.gov (United States)

    ... Blood Products Special Blood Donation Procedures Precautions and Adverse Reactions During Blood Transfusion (See Overview of Blood Transfusion .) Plateletpheresis (platelet donation) In plateletpheresis, a donor gives only platelets rather than whole blood. Whole ...

  10. Dynamic alarm response procedures

    International Nuclear Information System (INIS)

    Martin, J.; Gordon, P.; Fitch, K.

    2006-01-01

    The Dynamic Alarm Response Procedure (DARP) system provides a robust, Web-based alternative to existing hard-copy alarm response procedures. This paperless system improves performance by eliminating time wasted looking up paper procedures by number, looking up plant process values and equipment and component status at graphical display or panels, and maintenance of the procedures. Because it is a Web-based system, it is platform independent. DARP's can be served from any Web server that supports CGI scripting, such as Apache R , IIS R , TclHTTPD, and others. DARP pages can be viewed in any Web browser that supports Javascript and Scalable Vector Graphics (SVG), such as Netscape R , Microsoft Internet Explorer R , Mozilla Firefox R , Opera R , and others. (authors)

  11. Radiochemical procedures and techniques

    International Nuclear Information System (INIS)

    Flynn, K.

    1975-04-01

    A summary is presented of the radiochemical procedures and techniques currently in use by the Chemistry Division Nuclear Chemistry Group at Argonne National Laboratory for the analysis of radioactive samples. (U.S.)

  12. Soil Sampling Operating Procedure

    Science.gov (United States)

    EPA Region 4 Science and Ecosystem Support Division (SESD) document that describes general and specific procedures, methods, and considerations when collecting soil samples for field screening or laboratory analysis.

  13. Bariatric Surgery Procedures

    Science.gov (United States)

    ... Meetings of Interest Online Education Job Board CME Policies CBN Fellowship Certificate Research Grant Program Resources All Resources Approved Procedures Patient Safety Vignettes Dr. Mason Historical Library Governing Documents Guidelines Access and Insurance Position and ...

  14. Nuclear materials management procedures

    International Nuclear Information System (INIS)

    Veevers, K.; Silver, J.M.; Quealy, K.J.; Steege, E. van der.

    1987-10-01

    This manual describes the procedures for the management of nuclear materials and associated materials at the Lucas Heights Research Laboratories. The procedures are designed to comply with Australia's nuclear non-proliferation obligations to the International Atomic Energy Agency (IAEA), bilateral agreements with other countries and ANSTO's responsibilities under the Nuclear Non-Proliferation (Safeguards) Act, 1987. The manual replaces those issued by the Australian Atomic Energy Commission in 1959, 1960 and 1969

  15. Procedural learning and dyslexia.

    Science.gov (United States)

    Nicolson, R I; Fawcett, A J; Brookes, R L; Needle, J

    2010-08-01

    Three major 'neural systems', specialized for different types of information processing, are the sensory, declarative, and procedural systems. It has been proposed (Trends Neurosci., 30(4), 135-141) that dyslexia may be attributable to impaired function in the procedural system together with intact declarative function. We provide a brief overview of the increasing evidence relating to the hypothesis, noting that the framework involves two main claims: first that 'neural systems' provides a productive level of description avoiding the underspecificity of cognitive descriptions and the overspecificity of brain structural accounts; and second that a distinctive feature of procedural learning is its extended time course, covering from minutes to months. In this article, we focus on the second claim. Three studies-speeded single word reading, long-term response learning, and overnight skill consolidation-are reviewed which together provide clear evidence of difficulties in procedural learning for individuals with dyslexia, even when the tasks are outside the literacy domain. The educational implications of the results are then discussed, and in particular the potential difficulties that impaired overnight procedural consolidation would entail. It is proposed that response to intervention could be better predicted if diagnostic tests on the different forms of learning were first undertaken. 2010 John Wiley & Sons, Ltd.

  16. Procedural sedation analgesia

    Directory of Open Access Journals (Sweden)

    Sheta Saad

    2010-01-01

    Full Text Available The number of noninvasive and minimally invasive procedures performed outside of the operating room has grown exponentially over the last several decades. Sedation, analgesia, or both may be needed for many of these interventional or diagnostic procedures. Individualized care is important when determining if a patient requires procedural sedation analgesia (PSA. The patient might need an anti-anxiety drug, pain medicine, immobilization, simple reassurance, or a combination of these interventions. The goals of PSA in four different multidisciplinary practices namely; emergency, dentistry, radiology and gastrointestinal endoscopy are discussed in this review article. Some procedures are painful, others painless. Therefore, goals of PSA vary widely. Sedation management can range from minimal sedation, to the extent of minimal anesthesia. Procedural sedation in emergency department (ED usually requires combinations of multiple agents to reach desired effects of analgesia plus anxiolysis. However, in dental practice, moderate sedation analgesia (known to the dentists as conscious sedation is usually what is required. It is usually most effective with the combined use of local anesthesia. The mainstay of success for painless imaging is absolute immobility. Immobility can be achieved by deep sedation or minimal anesthesia. On the other hand, moderate sedation, deep sedation, minimal anesthesia and conventional general anesthesia can be all utilized for management of gastrointestinal endoscopy.

  17. Anesthesia for radiologic procedures

    International Nuclear Information System (INIS)

    Forestner, J.E.

    1987-01-01

    Anesthetic techniques for neurodiagnostic studies and radiation therapy have been recently reviewed, but anesthetic involvement in thoracic and abdominal radiology has received little attention. Patient reactions to radiologic contrast media may be of concern to the anesthesiologist, who is often responsible for injecting these agents during diagnostic procedures, and thus is included in this discussion. Finally, the difficulties of administering anesthesia for magnetic resonance imaging (MRI) scans are outlined, in an effort to help anesthesiologist to anticipate problems with this new technologic development. Although there are very few indications for the use of general anesthesia for diagnostic radiologic studies in adults, most procedures performed with children, the mentally retarded, or the combative adult require either heavy sedation or general anesthesia. In selecting an anesthetic technique for a specific procedure, both the patient's disease process and the requirements of the radiologist must be carefully balanced

  18. Motive Criminal Procedure Evidence

    Directory of Open Access Journals (Sweden)

    В. В. Вапнярчук

    2015-03-01

    Full Text Available In the article the need for such a level of mental regulation of behavior of proving motivation. The latter refers to internal motivation conscious entity Criminal Procedure proof, due to specific needs, interests and goals that cause a person to act rishymist. Detailed attention is given to the first two determinants, namely the nature of needs and interests. In particular, analyzes highlighted in the literature variety of needs (physiological, ekzistentsionalni, social, prestige, cognitive, aesthetic and spiritual and the manifestation of some of them in the criminal procedural proof.

  19. 76 FR 62092 - Filing Procedures

    Science.gov (United States)

    2011-10-06

    ... INTERNATIONAL TRADE COMMISSION Filing Procedures AGENCY: International Trade Commission. ACTION: Notice of issuance of Handbook on Filing Procedures. SUMMARY: The United States International Trade Commission (``Commission'') is issuing a Handbook on Filing Procedures to replace its Handbook on Electronic...

  20. Electronic procedure distribution

    International Nuclear Information System (INIS)

    Slone, B.J. III; Richardson, C.E.

    1993-01-01

    Printed procedures can offer a mix of text and graphic information that improves readability and increases understanding. A typical procedure uses illustrations and graphics to clarify concepts, a variety of type styles and weights to make it easier to find different topics and sections, white space to improve readability, and familiar navigational clues such as page numbers and topic headers. Initially, electronic procedure systems had limited typeface options, often only a single typeface, with no capability for enhancing readability by varying type size bolding, italicizing, or underlining, and no ability to include graphics. Even recently, many text-only electronic procedures were originally created in a modern What-You-See-Is-What-You-Get (WYSI-WYG) document authoring system, only to be converted to pages and pages of plain type for electronic distribution. Given the choice of paper or on-line producers, most users have chosen paper for its readability. But current-generation electronic document systems that use formatted text and embedded graphics offer users vastly improved readability. Further, they are offering ever-better search tools to enable rapid location of material of interest

  1. The nuclear licensing procedure

    International Nuclear Information System (INIS)

    Wagner, H.

    1976-01-01

    To begin with, the present nuclear licensing procedure is illustrated by a diagram. The relationship between the state and the Laender, the various experts (GRS - IRS + LRA -, TUEV, DWD, university institutes, firms of consulting engineers, etc), participation of the public, e.g. publication of the relevant documents, questions, objections (made by individuals or by groups such as citizens' initiatives), public discussion, official notice, appeals against the decision, the right of immediate execution of the decision are shortly dealt with. Finally, ways to improve the licensing procedure are discussed, from the evaluation of the documents to be submitted, published, and examined by the authorities (and their experts) up to an improvement of the administrative procedure. An improved licensing procedure should satisfy the well-founded claims of the public for more transparency as well as the equally justifiable claims of industry and utilities in order to ensure that the citizens' legal right to have safe and adequate electric power is guaranteed. The updated energy programme established by the Federal Government is mentioned along with the effectiveness of dealing with nuclear problems on the various levels of a Land government. (orig.) [de

  2. OCRWM international procedures

    International Nuclear Information System (INIS)

    1986-03-01

    These international procedures provide guidance and assistance for the Office of Civilian Radioactive Waste Management (OCRWM) and for OCRWM Project Offices, contractors and subcontractors in conducting international activities. They supplement the relevant Department of Energy (DOE) orders (which are referenced), not supplant them

  3. Pneumomediastinum after odontologic procedure

    International Nuclear Information System (INIS)

    Olivella C, Fabio Alejandro; Bermudez G, Mary; Hidalgo M, Patricia; Sanchez M, Jully Mariana; Solarte R, Ivan; Uriza C, Felipe

    2005-01-01

    The sudden increase in alveolar pressure is a frequent cause of pneumomediastinum, but there are other reasons that could lead to it such as airway or esophagus trauma. The pneumomediastinum, which has been produced after dental procedures, is very rare and product deserves special attention by dentists and medical personnel in order to get its soon recognition and handling

  4. Educational Accounting Procedures.

    Science.gov (United States)

    Tidwell, Sam B.

    This chapter of "Principles of School Business Management" reviews the functions, procedures, and reports with which school business officials must be familiar in order to interpret and make decisions regarding the school district's financial position. Among the accounting functions discussed are financial management, internal auditing,…

  5. Robust procedures in chemometrics

    DEFF Research Database (Denmark)

    Kotwa, Ewelina

    properties of the analysed data. The broad theoretical background of robust procedures was given as a very useful supplement to the classical methods, and a new tool, based on robust PCA, aiming at identifying Rayleigh and Raman scatters in excitation-mission (EEM) data was developed. The results show...

  6. IXM gas sampling procedure

    International Nuclear Information System (INIS)

    Pingel, L.A.

    1995-01-01

    Ion Exchange Modules (IXMs) are used at the 105-KE and -KW Fuel Storage Basins to control radionuclide concentrations in the water. A potential safety concern relates to production of hydrogen gas by radiolysis of the water trapped in the ion exchange media of spent IXMs. This document provides a procedure for sampling the gases in the head space of the IXM

  7. 3. Procedures and Recursion

    Indian Academy of Sciences (India)

    Home; Journals; Resonance – Journal of Science Education; Volume 1; Issue 6. Algorithms Procedures and Recursion. R K Shyamasundar. Series Article Volume 1 ... Author Affiliations. R K Shyamasundar1. Computer Science Group, Tata Institute of Fundamental Research, Homi Bhabha Road Mumbai 400 005, India.

  8. The TOMAX-procedure

    NARCIS (Netherlands)

    Overgoor, M.L.E.

    2015-01-01

    Most patients with a low spinal lesion (LSL) have intact erectile function but no penile sensation, which can lead to frustration. To tackle this problem, we designed TOMAX, TOMAXimize sensation, sexuality and quality of life, a surgical procedure in which a functional "groin” nerve is connected to

  9. Experiments with Cloze Procedure

    Science.gov (United States)

    Evans, Gordon; Haastrup, Kirsten

    1976-01-01

    The Nordic Test Development Group prepared proficiency tests of English designed to provide reliable information on which to base decisions as to whether a candidate would be able to function in a job as described or whether he could be trained to do so. Two subtests used a modified cloze procedure. (Author/CFM)

  10. Formalizing physical security procedures

    NARCIS (Netherlands)

    Meadows, C.; Pavlovic, Dusko

    Although the problems of physical security emerged more than 10,000 years before the problems of computer security, no formal methods have been developed for them, and the solutions have been evolving slowly, mostly through social procedures. But as the traffic on physical and social networks is now

  11. Probabilistic analysis of crack containing structures with the PARIS code

    International Nuclear Information System (INIS)

    Brueckner-Foit, A.

    1987-10-01

    The basic features of the PARIS code which has been developed for the calculation of failure probabilities of crack containing structures are explained. An important issue in the reliability analysis of cracked components is the probabilistic leak-before-break behaviour. Formulae for the leak and break probabilities are derived and it is shown how a leak detection system influences the results. An example taken from nuclear applications illustrates the details of the probabilistic leak-before-break analysis. (orig.) [de

  12. Cancer pancreatis, diagnostic procedures

    International Nuclear Information System (INIS)

    Graadal, Oe.; Schlichting, E.; Aasen, A.O.; Stadaas, J.O.

    1990-01-01

    151 patients treated for carcinoma of the pancreas at Ullevaal Hospital (Oslo University) during the period 1980-89 were studied. The most common initial symptom was abdominal pain. Other frequent debut symptoms were loss of weight and jaundice. ERCP and PTC were found to be the best diagnostic procedures. CT or ultrasonography were normal in 10-20% of the patients. Nearly all tumors of the pancreas were found by the ERCP procedure. Also angiography was used to evaluate operability of the pancreas tumor, but was found to be a very uncertain diagnostic method. This method will not be used in the future evaluation of patients with cancer of the pancreas. 13 refs., 1 fig., 2 tabs

  13. Subsea HIPPS design procedure

    International Nuclear Information System (INIS)

    Aaroe, R.; Lund, B.F.; Onshus, T.

    1995-01-01

    The paper is based on a feasibility study investigating the possibilities of using a HIPPS (High Integrity Pressure Protection System) to protect a subsea pipeline that is not rated for full wellhead shut-in pressure. The study was called the Subsea OPPS Feasibility Study, and was performed by SINTEF, Norway. Here, OPPS is an acronym for Overpressure Pipeline Protection System. A design procedure for a subsea HIPPS is described, based on the experience and knowledge gained through the ''Subsea OPPS Feasibility Study''. Before a subsea HIPPS can be applied, its technical feasibility, reliability and profitability must be demonstrated. The subsea HIPPS design procedure will help to organize and plan the design activities both with respect to development and verification of a subsea HIPPS. The paper also gives examples of how some of the discussed design steps were performed in the Subsea OPPS Feasibility Study. Finally, further work required to apply a subsea HIPPS is discussed

  14. Headache and endovascular procedures.

    Science.gov (United States)

    de Biase, Stefano; Longoni, Marco; Gigli, Gian Luigi; Agostoni, Elio

    2017-05-01

    The International Classification of Headache Disorders (ICHD-3 beta) includes headache attributed to intracranial endovascular procedures (EVPs). The aim of this review is to describe the clinical and pathophysiological aspects of headache related to vascular lesions and EVPs. Current studies regarding this issue are contradictory, although generally favouring headache improvement after EVPs. Further large studies are needed to adequately assess the effect of EVPs on headache.

  15. Internal Control Organization Procedure

    OpenAIRE

    Radu Dorin Lenghel

    2013-01-01

    Internal control represents the totality of policies and procedures adopted by management, which contribute: to the fulfilment of managerial objectives, to the prevention and detection of frauds or errors, to the accuracy and exhaustiveness of accounting entries, as well as to the preparation in due course of financial accounting information. Internal control represents a managerial instrument which assures the fulfilment of objectives of the entity, being an ongoing process in which administ...

  16. Analytical Procedures for Testability.

    Science.gov (United States)

    1983-01-01

    Beat Internal Classifications", AD: A018516. "A System of Computer Aided Diagnosis with Blood Serum Chemistry Tests and Bayesian Statistics", AD: 786284...6 LIST OF TALS .. 1. Truth Table ......................................... 49 2. Covering Problem .............................. 93 3. Primary and...quential classification procedure in a coronary care ward is evaluated. In the toxicology field "A System of Computer Aided Diagnosis with Blood Serum

  17. The TOMAX-procedure

    OpenAIRE

    Overgoor, M.L.E.

    2015-01-01

    Most patients with a low spinal lesion (LSL) have intact erectile function but no penile sensation, which can lead to frustration. To tackle this problem, we designed TOMAX, TOMAXimize sensation, sexuality and quality of life, a surgical procedure in which a functional "groin” nerve is connected to the non-functional “penile” nerve on one side to bypass the LSL. Our goal was to increase LSL patients’ sexual health by restoring penile sensation: we show that TOMAX can achieve dramatic improvem...

  18. Start-up procedure

    International Nuclear Information System (INIS)

    Marchl, A.; Krebs, W.D.; Aleite, W.

    1975-01-01

    The start-up procedure will be shown on a pressurized water reactor, although most of the activities will occur similarly in other reactor types. The commissioning time can be divided into 5 sections, the phases A to E together lasting 26 months. Subsequently there are a test run of one month and the handling-over of the plant to the operator. A survey of the commissioning sections with several important main events is shown. (orig./TK) [de

  19. R6 FIFRA e-Notice of Arrival

    Data.gov (United States)

    U.S. Environmental Protection Agency — This database processes approximately 3,000 Notice of Arrival (NOA) reporting forms from importers and exporters of pesticide products. This is an electronic version...

  20. Coal pillar design procedures

    CSIR Research Space (South Africa)

    York, G

    2000-03-01

    Full Text Available Final Project Report Coal pillar design procedures G. York, I. Canbulat, B.W. Jack Research agency: CSIR Mining Technology Project number: COL 337 Date: March 2000 2 Executive Summary Examination of collapsed pillar cases outside of the empirical... in strength occurs with increasing specimen size. 45 40 35 30 25 20 15 10 5 0 20 40 60 80 100 120 140 160 UNIAX IA L COMPR EHEN SIV E S TR ENG TH (M Pa ) CUBE SIZE (cm) Figure 1...

  1. Emergency procedures in London

    International Nuclear Information System (INIS)

    Cree, D.

    1984-01-01

    This chapter discusses the following: emergency services (fire brigade, ambulance and police) that would be involved in dealing with an accident to a nuclear fuel flask in transport through London, with special reference to procedures used by the Metropolitan Police; geographical area covered by Metropolitan Police; initiation of action; decision whether to evacuate the area of the accident; examples of action taken to deal with non-radiation accidents (in absence of any example of relevant radiation accident); specific instructions, or advice, to police relating to the movement of irradiated fuel; training exercises. (U.K.)

  2. Regulations and Procedures Manual

    Energy Technology Data Exchange (ETDEWEB)

    Young, Lydia J. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2011-07-25

    The purpose of the Regulations and Procedures Manual (RPM) is to provide LBNL personnel with a reference to University and Lawrence Berkeley National Laboratory (LBNL or Laboratory) policies and regulations by outlining normal practices and answering most policy questions that arise in the day-to-day operations of Laboratory organizations. Much of the information in this manual has been condensed from detail provided in LBNL procedure manuals, Department of Energy (DOE) directives, and Contract DE-AC02-05CH11231. This manual is not intended, however, to replace any of those documents. RPM sections on personnel apply only to employees who are not represented by unions. Personnel policies pertaining to employees represented by unions may be found in their labor agreements. Questions concerning policy interpretation should be directed to the LBNL organization responsible for the particular policy. A link to the Managers Responsible for RPM Sections is available on the RPM home page. If it is not clear which organization is responsible for a policy, please contact Requirements Manager Lydia Young or the RPM Editor.

  3. Regulations and Procedures Manual

    Energy Technology Data Exchange (ETDEWEB)

    Young, Lydia [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2010-09-30

    The purpose of the Regulations and Procedures Manual (RPM) is to provide Laboratory personnel with a reference to University and Lawrence Berkeley National Laboratory policies and regulations by outlining the normal practices and answering most policy questions that arise in the day-to-day operations of Laboratory departments. Much of the information in this manual has been condensed from detail provided in Laboratory procedure manuals, Department of Energy (DOE) directives, and Contract DE-AC02-05CH11231. This manual is not intended, however, to replace any of those documents. The sections on personnel apply only to employees who are not represented by unions. Personnel policies pertaining to employees represented by unions may be found in their labor agreements. Questions concerning policy interpretation should be directed to the department responsible for the particular policy. A link to the Managers Responsible for RPM Sections is available on the RPM home page. If it is not clear which department should be called, please contact the Associate Laboratory Director of Operations.

  4. Radiation dose electrophysiology procedures

    International Nuclear Information System (INIS)

    Hernandez-Armas, J.; Rodriguez, A.; Catalan, A.; Hernandez Armas, O.; Luque Japon, L.; Moral, S.; Barroso, L.; Rfuez-Hdez, R.

    2006-01-01

    The aim of this paper has been to measure and analyse some of the parameters which are directly related with the doses given to patients in two electrophysiology procedures: diagnosis and ablation with radiofrequency. 16 patients were considered in this study. 13 them had an ablation with radiofrequency at the Unit of Electrophysiology at the University Hospital of the Canaries, La Laguna., Tenerife. The results of skin doses, in the ablation cases, were higher than 2 Gy (threshold of some deterministic effects). The average value was 1.1 Gy. The personal doses, measured under the lead apron, for physician and nurses were 4 and 3 micro Sievert. These results emphasised the necessity of radiation protection measures in order to reduce, ad much as possible, the doses to patients. (Author)

  5. Decommissioning licensing procedure

    International Nuclear Information System (INIS)

    Perello, M.

    1979-01-01

    Decommissioning or closure of a nuclear power plant, defined as the fact that takes place from the moment that the plant stops producing for the purpose it was built, is causing preocupation. So this specialist meeting on Regulatory Review seems to be the right place for presenting and discusing the need of considering the decommissioning in the safety analysis report. The main goal of this paper related to the licensing procedure is to suggest the need of a new chapter in the Preliminary Safety Analysis Report (P.S.A.R.) dealing with the decommissioning of the nuclear power plant. Therefore, after a brief introduction the problem is exposed from the point of view of nuclear safety and finally a format of the new chapter is proposed. (author)

  6. Toddler test or procedure preparation

    Science.gov (United States)

    ... a test or procedure: Explain the procedure in language your child understands, using plain words. Avoid abstract terms. Make sure your child understands the exact body part involved in the test, and that the ...

  7. Preschooler test or procedure preparation

    Science.gov (United States)

    ... your child during and after the procedure with books, songs, counting, deep breathing, or blowing bubbles. PLAY ... can be present during the procedure. Ask if anesthesia can be used to reduce your child's discomfort. ...

  8. Automation of the testing procedure

    International Nuclear Information System (INIS)

    Haas, H.; Fleischer, M.; Bachner, E.

    1979-01-01

    For the judgement of technologies applied and the testing of specific components of the HTR primary circuit, complex test procedures and data evaluations are required. Extensive automation of these test procedures is indispensable. (orig.) [de

  9. Quantization Procedures; Sistemas de cuantificacion

    Energy Technology Data Exchange (ETDEWEB)

    Cabrera, J. A.; Martin, R.

    1976-07-01

    We present in this work a review of the conventional quantization procedure, the proposed by I.E. Segal and a new quantization procedure similar to this one for use in non linear problems. We apply this quantization procedures to different potentials and we obtain the appropriate equations of motion. It is shown that for the linear case the three procedures exposed are equivalent but for the non linear cases we obtain different equations of motion and different energy spectra. (Author) 16 refs.

  10. Application of safeguards procedures

    International Nuclear Information System (INIS)

    1977-01-01

    The earliest applications of safeguards procedures took place in a political and technical climate far different from that of today. In the early 1960's there was a fear of the proliferation possibilities which could arise as more and more countries acquired nuclear power plants. Today nuclear power is being produced in some 20 countries without resulting in nuclear weapons proliferation. The export of equipment and technology for the nuclear fuel cycle, however, has become the subject of current concern. In view of these developments, it is not surprising that techniques in the application of safeguards have also changed. In order to appreciate the nature of these changes, it is important to be aware of the original general attitude towards the technical problems of safeguards applications. Originally, the common attitude was that the objectives of safeguards were self-evident and the methods, while in need of development, were known at least in outline. Today, it has become evident that before a safeguards procedure can be applied, the objectives must first be carefully defined, and the criteria against which success in meeting those objectives can be measured must also be developed. In line with this change, a significant part of the effort of the safeguards inspectorate is concerned with work preliminary and subsequent to the actual inspection work in the field. Over the last two years, for example, a considerable part of the work of experienced safeguards staff has been spent in analysing the possibilities of diverting material at each facility to be safeguarded. These analyses are carried out in depth by a 'facility officer' and are subjected to constructive criticism by teams composed of staff responsible for similar types of facilities as well as other technical experts. The analyses consider the measures currently considered practicable, to meet the diversion possibilities and where necessary list the development work needed to overcome any present

  11. BWR emergency procedure guidelines

    International Nuclear Information System (INIS)

    Post, J.S.; Karner, E.F.; Stratman, R.A.

    1984-01-01

    This chapter describes plans for dealing with reactor accidents developed by the Boiling Water Reactor (BWR) Owners' Group in response to post-Three Mile Island US NRC requirements. The devised Emergency Procedure Guidelines (EPGs), applicable to all BWRs, are symptom-based rather than event-based. According to the EPGs, the operator does not need to identify what event is occurring in the plant in order to decide what action to take, but need only observe the symptoms (values and trends of key control parameters) which exist and take appropriate action to control these symptoms. The original objective was to provide reactor operator guidance in responding to a small break loss-of-coolant accident (LOCA), but subsequent revisions have included other types of reactor accidents. Topics considered include the reactor pressure vessel (RPV) control guideline, the primary containment control guideline, the secondary containment control guideline, the radioactivity release control guideline, multiple failures vs. the design basis, safe limits vs. technical specifications, the technical status, licensing, and implementation. The EPGs are based upon maintaining both adequate core cooling and primary containment integrity

  12. Automated emergency operating procedures

    International Nuclear Information System (INIS)

    Perez-Ramirez, G.; Nelson, P.F.

    1990-01-01

    This paper describes the development of a training tool for the symptom oriented emergency operating procedures used at the Laguna Verde Nuclear Power Plant. EOPs and operator training are intended to assist the operator for managing accident situations. A prototype expert system based on the EOPs has been developed for operator training. The demonstration expert system was developed using a commercial shell. The knowledge base consists of two parts. The specific operator actions to be executed for 5 selected accident sequences and the EOPs steps for the reactor pressure vessel control of the water level, pressure, and power. The knowledge is expressed in the form of IF-THEN production rules. A typical training session will display a set of conditions and will prompt the trainee to indicate the appropriate step to perform. This mode will guide the trainee through selected accident sequences. A second mode of the expert system will prompt the trainee for the current plant conditions and the expert system will respond with the EOPs which are required to be performed under these conditions. This allows the trainee to study What if situations

  13. Computer software review procedures

    International Nuclear Information System (INIS)

    Mauck, J.L.

    1993-01-01

    This article reviews the procedures which are used to review software written for computer based instrumentation and control functions in nuclear facilities. The utilization of computer based control systems is becoming much more prevalent in such installations, in addition to being retrofit into existing systems. Currently, the Nuclear Regulatory System uses Regulatory Guide 1.152, open-quotes Criteria for Programmable Digital Computer System Software in Safety-Related Systems of Nuclear Power Plantsclose quotes and ANSI/IEEE-ANS-7-4.3.2-1982, open-quotes Application Criteria for Programmable Digital Computer Systems in Safety Systems of Nuclear Power Generating Stationsclose quotes for guidance when performing reviews of digital systems. There is great concern about the process of verification and validation of these codes, so when inspections are done of such systems, inspectors examine very closely the processes which were followed in developing the codes, the errors which were detected, how they were found, and the analysis which went into tracing down the causes behind the errors to insure such errors were not propagated again in the future

  14. Analytical procedures. Pt. 4

    International Nuclear Information System (INIS)

    Rackwitz, R.

    1985-01-01

    The semi-analytical procedures are summarized under the heading 'first or second-order reliability method'. The asymptotic aggravation of the theory was repeatedly hinted at. In supporting structures the probability of outage of components always is also a function of the condition of all other components. It depends moreover on the stress affecting mostly all components. This fact causes a marked reduction of the effect of redundant component arrangements in the system. It moreover requires very special formulations. Although theoretically interesting and practically important developments will leave their mark on the further progress of the theory, the statements obtained by those approaches will continue to depend on how closely the chosen physical relationships and stoachstic models can come to the scatter quantities. Sensitivity studies show that these are partly aspects of substantially higher importance with a view to decision criteria than the refinement of the (probabilistic) method. Questions of relevance and reliability of data and their adequate treatment in reliability analyses seem to rank higher in order of sequence than exaggerated demands on methodics. (orig./HP) [de

  15. [Costing nuclear medicine diagnostic procedures].

    Science.gov (United States)

    Markou, Pavlos

    2005-01-01

    To the Editor: Referring to a recent special report about the cost analysis of twenty-nine nuclear medicine procedures, I would like to clarify some basic aspects for determining costs of nuclear medicine procedure with various costing methodologies. Activity Based Costing (ABC) method, is a new approach in imaging services costing that can provide the most accurate cost data, but is difficult to perform in nuclear medicine diagnostic procedures. That is because ABC requires determining and analyzing all direct and indirect costs of each procedure, according all its activities. Traditional costing methods, like those for estimating incomes and expenses per procedure or fixed and variable costs per procedure, which are widely used in break-even point analysis and the method of ratio-of-costs-to-charges per procedure may be easily performed in nuclear medicine departments, to evaluate the variability and differences between costs and reimbursement - charges.

  16. Radiation dose during angiographic procedures

    International Nuclear Information System (INIS)

    Lavoie, Ch.; Rasuli, P.

    2001-01-01

    The use of angiographic procedures is becoming more prevalent as new techniques and equipment are developed. There have been concerns in the scientific community about the level of radiation doses received by patients, and indirectly by staff, during some of these radiological procedures. The purpose of this study was to assess the level of radiation dose from angiographic procedures to patient at the Ottawa Hospital, General Campus. Radiation dose measurements, using Thermo-Luminescent Dosimeters (TLDs), were performed on more than 100 patients on various procedures. The results show that while the patient dose from the great majority of angiographic procedures is less than 2 Gy, a significant number of procedures, especially interventional procedures may have doses greater than 2 Gy and may lead to deterministic effects. (author)

  17. Administrative Procedure Act and mass procedures (illustrated by the nuclear licensing procedure)

    International Nuclear Information System (INIS)

    Naumann, R.

    1977-01-01

    The report deals with the administrative procedure law of 25.5.76 of the Fed. Government, esp. with its meaning for the administrative procedures for the permission for nuclear power plants, as fas ar so-called mass procedures are concerned. (UN) [de

  18. Safeguards management inspection procedures

    International Nuclear Information System (INIS)

    Barth, M.J.; Dunn, D.R.

    1984-08-01

    The objective of this inspection module is to independently assess the contributions of licensee management to overall safeguards systems performance. The inspector accomplishes this objective by comparing the licensee's safeguards management to both the 10 CFR, parts 70 and 73, requirements and to generally accepted management practices. The vehicle by which this comparison is to be made consists of assessment questions and key issues which point the inspector to areas of primary concern to the NRC and which raise additional issues for the purpose of exposing management ineffectiveness. Further insight into management effectiveness is obtained through those assessment questions specifically directed toward the licensee's safeguards system performance. If the quality of the safeguards is poor, then the inspector should strongly suspect that management's role is ineffective and should attempt to determine management's influence (or lack thereof) on the underlying safeguards deficiencies. (The converse is not necessarily true, however.) The assessment questions in essence provide an opportunity for the inspector to identify, to single out, and to probe further, questionable management practices. Specific issues, circumstances, and concerns which point to questionable or inappropriate practices should be explicitly identified and referenced against the CFR and the assessment questions. The inspection report should also explain why the inspector feels certain management practices are poor, counter to the CFR, and/or point to ineffecive management. Concurrent with documenting the inspection results, the inspector should provide recommendations for alleviating observed management practices that are detrimental to effective safeguards. The recommendations could include: specific changes in the practices of the licensee, followup procedures on the part of NRC, and proposed license changes

  19. AGREED-UPON PROCEDURES, PROCEDURES FOR AUDITING EUROPEAN GRANTS

    Directory of Open Access Journals (Sweden)

    Daniel Petru VARTEIU

    2016-12-01

    The audit of EU-funded projects is an audit based on agreed-upon procedures, which are established by the Managing Authority or the Intermediate Body. Agreed-upon procedures can be defined as engagements made in accordance with ISRS 4400, applicable to agreed-upon procedures, where the auditor undertakes to carry out the agreed-upon procedures and issue a report on factual findings. The report provided by the auditor does not express any assurance. It allows users to form their own opinions about the conformity of the expenses with the project budget as well as the eligibility of the expenses.

  20. Aesthetic procedures in office practice.

    Science.gov (United States)

    Small, Rebecca

    2009-12-01

    Since the approval of botulinum toxin, dermal fillers, and lasers for cosmetic use, minimally invasive aesthetic procedures have rapidly become the treatments of choice for age-related facial changes. In the past 10 years, aesthetic procedures have increased nearly five-fold. Of the 10.2 million aesthetic treatments performed in 2008, 83 percent were minimally invasive procedures. Botulinum toxin and dermal filler injections, laser hair reduction, chemical peels, laser skin resurfacing, microdermabrasion, and intense pulsed light photorejuvenation were the most commonly performed procedures in 2008. These procedures are effective and associated with minimal discomfort, and they have a low incidence of adverse effects and short recovery times. High patient and physician satisfaction have contributed to their growing popularity and availability in the primary care setting. As patient demand for aesthetic treatments increases, family physicians should be familiar with common minimally invasive aesthetic procedures when advising patients or incorporating aesthetic care into office practice.

  1. Characteristics of Mobile Payment Procedures

    OpenAIRE

    Kreyer, Nina; Pousttchi, Key; Turowski, Klaus

    2002-01-01

    Companies are not going to invest into the development of innovative applications or services unless these can be charged for appropriately. Thus, the existence of standardized and widely accepted mobile payment procedures is crucial for successful business-to-customer mobile commerce. The acceptance of mobile payment procedures depends on costs, security and convenience issues. For the latter, it is important that a procedure can be used over the different payment scenarios mobile commerce, ...

  2. Coding for urologic office procedures.

    Science.gov (United States)

    Dowling, Robert A; Painter, Mark

    2013-11-01

    This article summarizes current best practices for documenting, coding, and billing common office-based urologic procedures. Topics covered include general principles, basic and advanced urologic coding, creation of medical records that support compliant coding practices, bundled codes and unbundling, global periods, modifiers for procedure codes, when to bill for evaluation and management services during the same visit, coding for supplies, and laboratory and radiology procedures pertinent to urology practice. Detailed information is included for the most common urology office procedures, and suggested resources and references are provided. This information is of value to physicians, office managers, and their coding staff. Copyright © 2013 Elsevier Inc. All rights reserved.

  3. Acquisition Policy and Procedures Program

    National Research Council Canada - National Science Library

    2001-01-01

    This Instruction establishes policies, responsibilities, and procedures for the procurement of goods and services to include supplies, equipment, publications, furniture, and information technology...

  4. Electronic Procedures for Medical Operations

    Science.gov (United States)

    2015-01-01

    Electronic procedures are replacing text-based documents for recording the steps in performing medical operations aboard the International Space Station. S&K Aerospace, LLC, has developed a content-based electronic system-based on the Extensible Markup Language (XML) standard-that separates text from formatting standards and tags items contained in procedures so they can be recognized by other electronic systems. For example, to change a standard format, electronic procedures are changed in a single batch process, and the entire body of procedures will have the new format. Procedures can be quickly searched to determine which are affected by software and hardware changes. Similarly, procedures are easily shared with other electronic systems. The system also enables real-time data capture and automatic bookmarking of current procedure steps. In Phase II of the project, S&K Aerospace developed a Procedure Representation Language (PRL) and tools to support the creation and maintenance of electronic procedures for medical operations. The goal is to develop these tools in such a way that new advances can be inserted easily, leading to an eventual medical decision support system.

  5. Pollutant Assessments Group procedures manual: Volume 2, Technical procedures

    Energy Technology Data Exchange (ETDEWEB)

    1992-03-01

    This is volume 2 of the manuals that describes the technical procedures currently in use by the Pollution Assessments Group. This manual incorporates new developments in hazardous waste assessment technology and administrative policy. Descriptions of the equipment, procedures and operations of such things as radiation detection, soil sampling, radionuclide monitoring, and equipment decontamination are included in this manual. (MB)

  6. Proof Rules for Recursive Procedures

    NARCIS (Netherlands)

    Hesselink, Wim H.

    1993-01-01

    Four proof rules for recursive procedures in a Pascal-like language are presented. The main rule deals with total correctness and is based on results of Gries and Martin. The rule is easier to apply than Martin's. It is introduced as an extension of a specification format for Pascal-procedures, with

  7. Laparoscopic reversal of Hartmann's procedure

    DEFF Research Database (Denmark)

    Svenningsen, Peter Olsen; Bulut, Orhan; Jess, Per

    2010-01-01

    of Hartmann's procedure as safely as in open surgery and with a faster recovery, shorter hospital stay and less blood loss despite a longer knife time. It therefore seems reasonable to offer patients a laparoscopic procedure at departments which are skilled in laparoscopic surgery and use it for standard...

  8. Developing Competency in Payroll Procedures

    Science.gov (United States)

    Jackson, Allen L.

    1975-01-01

    The author describes a sequence of units that provides for competency in payroll procedures. The units could be the basis for a four to six week minicourse and are adaptable, so that the student, upon completion, will be able to apply his learning to any payroll procedures system. (Author/AJ)

  9. Failure to Follow Written Procedures

    Science.gov (United States)

    2017-12-01

    Most tasks in aviation have a mandated written procedure to be followed specifically under the Code of Federal Regulations (CFR) Part 14, Section 43.13(a). However, the incidence of Failure to Follow Procedure (FFP) events continues to be a major iss...

  10. Procedure for taking physical inventories

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    This session is intended to apprise one of the various aspects of procedures and routines that Exxon Nuclear uses with respect to its nuclear materials physical inventory program. The presentation describes how plant physical inventories are planned and taken. The description includes the planning and preparation for taking the inventory, the clean-out procedures for converting in-process material to measurable items, the administrative procedures for establishing independent inventory teams and for inventorying each inventory area, the verification procedures used to include previously measured tamper-safed items in the inventory, and lastly, procedures used to reconcile the inventory and calculate MUF (materials unaccounted for). The purpose of the session is to enable participants to: (1) understand the planning and pre-inventorty procedures and their importance; (2) understand the need for and the required intensity of clean-out procedures; (3) understand how inventory teams are formed, and how the inventory is conducted; (4) understand the distinction between inventory previously measured tamper-safed items and other materials not so characterized; (5) understand the reconciliation procedures; and (6) calculate a MUF given the book and inventory results

  11. Biomass Compositional Analysis Laboratory Procedures | Bioenergy | NREL

    Science.gov (United States)

    Biomass Compositional Analysis Laboratory Procedures Biomass Compositional Analysis Laboratory Procedures NREL develops laboratory analytical procedures (LAPs) for standard biomass analysis. These procedures help scientists and analysts understand more about the chemical composition of raw biomass

  12. Simplified Laboratory Runoff Procedure (SLRP): Procedure and Application

    National Research Council Canada - National Science Library

    Price, Richard

    2000-01-01

    The Simplified Laboratory Runoff Procedure (SLRP) was developed to provide a faster, less expensive approach to evaluate surface runoff water quality from dredged material placed in an upland environment...

  13. Pelvic denervation procedures for dysmenorrhea.

    Science.gov (United States)

    Ramirez, Christina; Donnellan, Nicole

    2017-08-01

    Chronic pelvic pain and dysmenorrhea are common conditions affecting reproductive-age women. Surgical pelvic denervation procedures may be a treatment option for women with midline dysmenorrhea, in which medical management is declined by the patient, ineffective at managing symptoms, or medically contraindicated. This review describes the surgical techniques and complications associated with pelvic denervation procedures as well as the current evidence for these procedures in women with primary dysmenorrhea and dysmenorrhea secondary to endometriosis. Presacral neurectomy is the preferred pelvic denervation procedure in patients with primary dysmenorrhea and midline chronic pelvic pain associated with endometriosis. In patients with endometriosis presacral neurectomy is a useful adjunct to excision or ablation of all endometrial lesions to improve postoperative pain relief. There is no additional patient benefit of performing combined presacral neurectomy and uterine nerve ablation procedures. Pelvic denervation procedures can be performed safely and quickly with a low risk of complication if the surgeon is knowledgeable and skilled in operating in the presacral space. Patients should be adequately counseled on expected success rates and potential complications associated with pelvic denervation procedures.

  14. Specified assurance level sampling procedure

    International Nuclear Information System (INIS)

    Willner, O.

    1980-11-01

    In the nuclear industry design specifications for certain quality characteristics require that the final product be inspected by a sampling plan which can demonstrate product conformance to stated assurance levels. The Specified Assurance Level (SAL) Sampling Procedure has been developed to permit the direct selection of attribute sampling plans which can meet commonly used assurance levels. The SAL procedure contains sampling plans which yield the minimum sample size at stated assurance levels. The SAL procedure also provides sampling plans with acceptance numbers ranging from 0 to 10, thus, making available to the user a wide choice of plans all designed to comply with a stated assurance level

  15. ANAESTHESIA FOR OPHTHALMIC SURGICAL PROCEDURES

    African Journals Online (AJOL)

    Objective: To review factors influencing the choice of anaesthesia for ophthalmic surgical procedures. ... as risk associated with general anaesthesia (8) they are more .... Wilson ME, Pandey SK, Thakur J. Paediatric cataract blindness in the ...

  16. Adequate procedures for specific exams

    International Nuclear Information System (INIS)

    Staevie, G.L.G.; Gattringer, D.K.; Dal Mas, C.R.; Tessman, M.

    1996-01-01

    Some ideal procedures for specific radiographic exams are briefly presented. The aim is to improve the quality standard, establishing a specific method for each exam in order to decrease films waste and reduce the patient dose exposure

  17. An Analytical Cost Estimation Procedure

    National Research Council Canada - National Science Library

    Jayachandran, Toke

    1999-01-01

    Analytical procedures that can be used to do a sensitivity analysis of a cost estimate, and to perform tradeoffs to identify input values that can reduce the total cost of a project, are described in the report...

  18. Soil Gas Sampling Operating Procedure

    Science.gov (United States)

    EPA Region 4 Science and Ecosystem Support Division (SESD) document that describes general and specific procedures, methods, and considerations when collecting soil gas samples for field screening or laboratory analysis.

  19. Construction inspection manual of procedures

    Science.gov (United States)

    2009-01-01

    This manual provides highway construction personnel with relevant, practical information in order to perform accurate inspections and provide relevant construction procedural information for the various roadway and structures items of work. It is the...

  20. Fusion Imaging for Procedural Guidance.

    Science.gov (United States)

    Wiley, Brandon M; Eleid, Mackram F; Thaden, Jeremy J

    2018-05-01

    The field of percutaneous structural heart interventions has grown tremendously in recent years. This growth has fueled the development of new imaging protocols and technologies in parallel to help facilitate these minimally-invasive procedures. Fusion imaging is an exciting new technology that combines the strength of 2 imaging modalities and has the potential to improve procedural planning and the safety of many commonly performed transcatheter procedures. In this review we discuss the basic concepts of fusion imaging along with the relative strengths and weaknesses of static vs dynamic fusion imaging modalities. This review will focus primarily on echocardiographic-fluoroscopic fusion imaging and its application in commonly performed transcatheter structural heart procedures. Copyright © 2017 Sociedad Española de Cardiología. Published by Elsevier España, S.L.U. All rights reserved.

  1. Surface Environmental Surveillance Procedures Manual

    Energy Technology Data Exchange (ETDEWEB)

    Hanf, RW; Dirkes, RL

    1990-02-01

    This manual establishes the procedures for the collection of environmental samples and the performance of radiation surveys and other field measurements. Responsibilities are defined for those personnel directly involved in the collection of samples and the performance of field measurements.

  2. FFTF reactor plant procedures plan

    International Nuclear Information System (INIS)

    1972-01-01

    The document presented defines the plan to be used to coordinate the preparation, review, approval, and issuance of the operating procedure documents required to ensure safe and efficient operation of FFTF

  3. Adolescent test or procedure preparation

    Science.gov (United States)

    ... someone else) during the procedure Playing hand-held video games Using guided imagery Trying other distractions, such as ... effects the test may cause. Older teens may benefit from videos that show adolescents of the same age explaining ...

  4. Environmental protection and procedural law

    International Nuclear Information System (INIS)

    Mutschler, U.

    1978-01-01

    For the power industry which is 'independent of licensing', the Ule/Laubinger statement as well as its discussion on the 52th German legal experts' day are of considerable importance. It is therefore absolutely necessary to critically investigate the statements of this expert's opinion and the considerations on which they are based. This investigation is limited to those licensing procedures which in the terminology of experts, are 'similar to the plan approval procedure'. This applies mainly to the procedures according to paragraph 4 ff of the Federal Act on the Protection Against Nuisances and paragraph 7 of the Atomic Energy Law: Preliminaries publication of documents, inspection of files, public hearing, taking of evidence, persons with special responsibilities, administrative proceedings, actions by associations. The deficiencies in the execution of environmental procedural law is briefly mentioned. The notes in the article refer only to air pollution. (orig./HP) [de

  5. Urinary incontinence - vaginal sling procedures

    Science.gov (United States)

    ... this page: //medlineplus.gov/ency/article/007376.htm Urinary incontinence - vaginal sling procedures To use the sharing features ... are types of surgeries that help control stress urinary incontinence . This is urine leakage that happens when you ...

  6. Loop Electrosurgical Excision Procedure (LEEP)

    Science.gov (United States)

    ... applied to your cervix to stop any bleeding. Electrocautery also may be used to control bleeding. The ... the uterus at the top of the vagina. Electrocautery: A procedure in which an instrument works with ...

  7. Safety analysis procedures for PHWR

    International Nuclear Information System (INIS)

    Min, Byung Joo; Kim, Hyoung Tae; Yoo, Kun Joong

    2004-03-01

    The methodology of safety analyses for CANDU reactors in Canada, a vendor country, uses a combination of best-estimate physical models and conservative input parameters so as to minimize the uncertainty of the plant behavior predictions. As using the conservative input parameters, the results of the safety analyses are assured the regulatory requirements such as the public dose, the integrity of fuel and fuel channel, the integrity of containment and reactor structures, etc. However, there is not the comprehensive and systematic procedures for safety analyses for CANDU reactors in Korea. In this regard, the development of the safety analyses procedures for CANDU reactors is being conducted not only to establish the safety analyses system, but also to enhance the quality assurance of the safety assessment. In the first phase of this study, the general procedures of the deterministic safety analyses are developed. The general safety procedures are covered the specification of the initial event, selection of the methodology and accident sequences, computer codes, safety analysis procedures, verification of errors and uncertainties, etc. Finally, These general procedures of the safety analyses are applied to the Large Break Loss Of Coolant Accident (LBLOCA) in Final Safety Analysis Report (FSAR) for Wolsong units 2, 3, 4

  8. Collected radiochemical and geochemical procedures

    Energy Technology Data Exchange (ETDEWEB)

    Kleinberg, J [comp.

    1990-05-01

    This revision of LA-1721, 4th Ed., Collected Radiochemical Procedures, reflects the activities of two groups in the Isotope and Nuclear Chemistry Division of the Los Alamos National Laboratory: INC-11, Nuclear and radiochemistry; and INC-7, Isotope Geochemistry. The procedures fall into five categories: I. Separation of Radionuclides from Uranium, Fission-Product Solutions, and Nuclear Debris; II. Separation of Products from Irradiated Targets; III. Preparation of Samples for Mass Spectrometric Analysis; IV. Dissolution Procedures; and V. Geochemical Procedures. With one exception, the first category of procedures is ordered by the positions of the elements in the Periodic Table, with separate parts on the Representative Elements (the A groups); the d-Transition Elements (the B groups and the Transition Triads); and the Lanthanides (Rare Earths) and Actinides (the 4f- and 5f-Transition Elements). The members of Group IIIB-- scandium, yttrium, and lanthanum--are included with the lanthanides, elements they resemble closely in chemistry and with which they occur in nature. The procedures dealing with the isolation of products from irradiated targets are arranged by target element.

  9. Measuring variability of procedure progression in proceduralized scenarios

    International Nuclear Information System (INIS)

    Kim, Yochan; Park, Jinkyun; Jung, Wondea

    2012-01-01

    Highlights: ► The VPP measure was developed to quantify how differently operators follow the procedures. ► Sources that cause variability of ways to follow a given procedure were identified. ► The VPP values for the scenarios are positively related to the scenario performance time. ► The VPP measure is meaningful for explaining characteristics of several PSFs. -- Abstract: Various performance shaping factors (PSFs) have been presented to explain the contributors to unsafe acts in a human failure event or predict a human error probability of new human performance. However, because most of these parameters of an HRA depend on the subjective knowledge and experience of HRA analyzers, the results of an HRA insufficiently provide unbiased standards to explain human performance variations or compare collected data with other data from different analyzers. To secure the validity of the HRA results, we propose a quantitative measure, which represents the variability of procedure progression (VPP) in proceduralized scenarios. A VPP measure shows how differently the operators follow the steps of the procedures. This paper introduces the sources of the VPP measure and relevance to PSFs. The assessment method of the VPP measure is also proposed, and the application examples are shown with a comparison of the performance time. Although more empirical studies should be conducted to reveal the relationship between the VPP measure and other PSFs, it is believed that the VPP measure provides evidence to quantitatively evaluate human performance variations and to cross-culturally compare the collected data.

  10. Proof of integrity and ageing management of mechanical components in nuclear power plants

    International Nuclear Information System (INIS)

    Roos, E.; Herter, K.-H.; Kockelmann, H.; Schuler, X.

    2005-01-01

    Demands and requirements for a safe operation of mechanical components during the whole operation life time (plant life management) to assure aging phenomena (aging management) and to prove the integrity (prove of integrity, e.g. in order to exclude large breaks) can be found in guidelines, codes and standards. In the present paper a general concept to proof the integrity as part of the ageing management of pressurized components and systems is presented. The concept is based on the actual material characteristics, the actual as-built configurations and the design of the components and systems including the knowledge of possible failure mechanism during operation. An important part of the assessment is the leak before break behavior and the break preclusion concept. Based on essential research results the developed procedures and methodologies for the assessment of the critical crack sizes as well as the critical loading conditions are reported and discussed. In detail the following aspects have to be treated: (a) evaluation of the as-built status of quality (design, construction, material, fabrication; results of recurrent non destructive examinations up to now, operational experience); (b) determination of the relevant loading conditions by means of in-service monitoring (monitoring of the mode of operation, the water chemistry, the mechanical and thermal stresses, the dynamic loading), emergency and faulted condition loads as specified; (c) evaluation of the actual status of quality with respect to the relevant loading conditions (stress analysis-limitation of the stresses; fatigue analysis-determination of the usage factor; fracture mechanics analysis-determination of crack growth, critical crack sizes and loading conditions); (d) evaluation and extent of the in-service monitoring and recurrent inspections to guarantee the succeeding operation (recurrent non destructive examination - minimum detectable flaw sizes, examination area, examination intervals; leak

  11. Program Baseline Change Control Procedure

    International Nuclear Information System (INIS)

    1993-02-01

    This procedure establishes the responsibilities and process for approving initial issues of and changes to the technical, cost, and schedule baselines, and selected management documents developed by the Office of Civilian Radioactive Waste Management (OCRWM) for the Civilian Radioactive Waste Management System. This procedure implements the OCRWM Baseline Management Plan and DOE Order 4700.1, Chg 1. It streamlines the change control process to enhance integration, accountability, and traceability of Level 0 and Level I decisions through standardized Baseline Change Proposal (BCP) forms to be used by the Level 0, 1, 2, and 3 Baseline Change Control Boards (BCCBs) and to be tracked in the OCRWM-wide Configuration Information System (CIS) Database.This procedure applies to all technical, cost, and schedule baselines controlled by the Energy System Acquisition Advisory Board (ESAAB) BCCB (Level 0) and, OCRWM Program Baseline Control Board (PBCCB) (Level 1). All baseline BCPs initiated by Level 2 or lower BCCBs, which require approval from ESAAB or PBCCB, shall be processed in accordance with this procedure. This procedure also applies to all Program-level management documents controlled by the OCRWM PBCCB

  12. Designing Flightdeck Procedures: Literature Resources

    Science.gov (United States)

    Feldman, Jolene; Barshi, Immanuel; Degani, Asaf; Loukopoulou, Loukia; Mauro, Robert

    2017-01-01

    This technical publication contains the titles, abstracts, summaries, descriptions, and/or annotations of available literature sources on procedure design and development, requirements, and guidance. It is designed to provide users with an easy access to available resources on the topic of procedure design, and with a sense of the contents of these sources. This repository of information is organized into the following publication sources: Research (e.g., journal articles, conference proceedings), Manufacturers' (e.g., operation manuals, newsletters), and Regulatory and/or Government (e.g., advisory circulars, reports). An additional section contains synopses of Accident/Incident Reports involving procedures. This work directly supports a comprehensive memorandum by Barshi, Mauro, Degani, & Loukopoulou (2016) that summarizes the results of a multi-year project, partially funded by the FAA, to develop technical reference materials that support guidance on the process of developing cockpit procedures (see "Designing Flightdeck Procedures" https://ntrs.nasa.gov/archive/nasa/casi.ntrs.nasa.gov/20160013263.pdf). An extensive treatment of this topic is presented in a forthcoming book by the same authors.

  13. New procedure for departure formalities

    CERN Multimedia

    HR & GS Departments

    2011-01-01

    As part of the process of simplifying procedures and rationalising administrative processes, the HR and GS Departments have introduced new personalised departure formalities on EDH. These new formalities have applied to students leaving CERN since last year and from 17 October 2011 this procedure will be extended to the following categories of CERN personnel: Staff members, Fellows and Associates. It is planned to extend this electronic procedure to the users in due course. What purpose do departure formalities serve? The departure formalities are designed to ensure that members of the personnel contact all the relevant services in order to return any necessary items (equipment, cards, keys, dosimeter, electronic equipment, books, etc.) and are aware of all the benefits to which they are entitled on termination of their contract. The new departure formalities on EDH have the advantage of tailoring the list of services that each member of the personnel must visit to suit his individual contractual and p...

  14. Design Procedure for Hybrid Ventilation

    DEFF Research Database (Denmark)

    Heiselberg, Per; Tjelflaat, Per Olaf

    Mechanical and natural ventilation systems have developed separately during many years. The natural next step in this development is development of ventilation concepts that utilises and combines the best features from each system into a new type of ventilation system - Hybrid Ventilation....... Buildings with hybrid ventilation often include other sustainable technologies and an energy optimisation requires an integrated approach in the design of the building and its mechanical systems. Therefore, the hybrid ventilation design procedure differs from the design procedure for conventional HVAC....... The first ideas on a design procedure for hybrid ventilation is presented and the different types of design methods, that is needed in different phases of the design process, is discussed....

  15. Acute Procedural Pain in Children

    DEFF Research Database (Denmark)

    Kristensen, Helle Nygård; Lundbye-Christensen, Søren; Haslund-Thomsen, Helle

    2018-01-01

    INTRODUCTION: Hospitalized children often describe needle-related procedures as the worst pain possible and such procedures may be emotionally traumatic. The use of hospital clowns related to painful medical procedures in children may offer pain relief, but this has not been systematically...... evaluated. The objective of this study was to assess the effect of a therapeutic clown in comparison to standard care on the experience of pain for children receiving venipuncture. METHODS: A sample of 116 children aged 4-15 years consecutively admitted to the hospital was allocated to either......: Without the clown present, the mean pain score (2.7±2.8) was not significantly different between the two age groups. Children aged 7-15 years had lower pain scores when the clown was present compared to the control group (P=0.025). Children aged 4-6 years had higher pain scores with the clown present...

  16. MITG test procedure and results

    International Nuclear Information System (INIS)

    Eck, M.E.; Mukunda, M.

    1983-01-01

    Elements and modules for Radioisotope Thermoelectric Generator have been performance tested since the inception of the RTG program. These test articles seldom resembled flight hardware and often lacked adequate diagnostic instrumentation. Because of this, performance problems were not identified in the early stage of program development. The lack of test data in an unexpected area often hampered the development of a problem solution. A procedure for conducting the MITG Test was developed in an effort to obtain data in a systematic, unambiguous manner. This procedure required the development of extensive data acquisition software and test automation. The development of a facility to implement the test procedure, the facility hardware and software requirements, and the results of the MITG testing are the subject of this paper

  17. Radiation control standards and procedures

    Energy Technology Data Exchange (ETDEWEB)

    1956-12-14

    This manual contains the Radiation Control Standards'' and Radiation Control Procedures'' at Hanford Operations which have been established to provide the necessary control radiation exposures within Irradiation Processing Department. Provision is also made for including, in the form of Bulletins'', other radiological information of general interest to IPD personnel. The purpose of the standards is to establish firm radiological limits within which the Irradiation Processing Department will operate, and to outline our radiation control program in sufficient detail to insure uniform and consistent application throughout all IPD facilities. Radiation Control Procedures are intended to prescribe the best method of accomplishing an objective within the limitations of the Radiation Control Standards. A procedure may be changed at any time provided the suggested changes is generally agreeable to management involved, and is consistent with department policies and the Radiation Control Standards.

  18. MR diagnostics after Ross procedure

    International Nuclear Information System (INIS)

    Steffens, J.C.; Link, J.; Harringer, W.; Haverich, A.; Heller, M.

    1996-01-01

    Purpose: To determine the ability of MRI to diagnose morphological and functional changes in patients after Ross procedure. Material and methods: During one year, 5 patients after Ross procedure were studied by MRI. T 1 -weighted spin-echo sequences in different orientations as well as cine sequences and a VENC-sequence were used. Results: In all patients the morphology including the postoperative changes could be visualised by MRI. The cine sequences provided functional information on valvular and ventricular function. VENC-MR yielded an exact quantification of the regurgitant fraction. Conclusion: MRI is capable of providing all important diagnostic information in patients after Ross procedure such as valvular and ventricular function and valvular and outflow tract morphology in a single examination. (orig.) [de

  19. Transversal of Procedure Elements in a Computerized Procedure System

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Yeonsub [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    APR1400 MCR(Main Control Room) has introduced CPS(Computerized Procedure System). APR400 CPS is framed with overview pane, step detail pane, and monitoring pane. The overview shows the step in one dimensional array. Diagram in the step detail pane is called as flowlogic diagram. The flowlogic diagram has advantage of being intuitive and not being segmented so that the interfaces are easy to follow and understand. While developing CPS software or training operators these interfaces, however, there is still areas to refine behaviors of flowlogic diagram. If flowlogic diagram has contingency instructions, it is sometime difficult to interpret it properly. Therefore this paper is trying to explain behavior of flowlogic diagram in view of procedure elements. Procedure execution can be called as transversal of steps and instructions in flowlogic diagram. Both hierarchy of procedures elements and flowlogic diagram provides useful framework to test transversal with completeness. Navigation button behaviors are interpreted in view of flowlogic diagram. The framework and flowlogic diagram can be further applied to improve CPS user interfaces.

  20. Procedures monitoring and MAAP analysis

    International Nuclear Information System (INIS)

    May, R.S.

    1991-01-01

    Numerous studies of severe accidents in light water reactors have shown that operator response can play a crucial role in the predicted outcomes of dominant accident scenarios. MAAP provides the capability to specify certain operator actions as input data. However, making reasonable assumptions about the nature and timing of operator response requires substantial knowledge about plant practices and procedures and what they imply for the event being analyzed. The appearance of knowledge based software technology in the mid-1980s provided a natural format for representing and maintaining procedures as IF-THEN rules. The boiling water reactor (BWR) Emergency Operating Procedures Tracking System (EOPTS) was composed of a rule base of procedures and a dedicated inference engine (problem-solver). Based on the general approach and experience of EOPTS, the authors have developed a prototype procedures monitoring system that reads MAAP transient output files and evaluate the EOP messages and instructions that would be implied during each transient time interval. The prototype system was built using the NEXPERT OBJECT expert system development system, running on a 386-class personal computer with 4 MB of memory. The limited scope prototype includes a reduced set of BWR6 EOPs procedures evaluation on a coarse time interval, a simple text-based user interface, and a summary-report generator. The prototype, which is limited to batch-mode analysis of MAAP output, is intended to demonstrate the concept and aid in the design of a production system, which will involve a direct link to MAAP and interactive capabilities

  1. Interventional chest procedures in pregnancy.

    LENUS (Irish Health Repository)

    Morgan, Ross K

    2012-02-01

    Interventional pulmonology encompasses diagnostic and therapeutic bronchoscopic procedures, and pleural interventions. In the last 10 years older techniques have been refined and exciting new technologies have extended the reach and application of the instruments used. The main areas within pulmonary medicine for which these interventions have a role are malignant and nonmalignant airway disease, pleural effusion, pneumothorax, and artificial airways. There are no data from well-designed prospective trials to guide recommendations for interventional pulmonary procedures in pregnancy. The recommendations provided in this article are based on critical review of reported case series, opinion from recognized experts, and personal observations.

  2. Interventional chest procedures in pregnancy.

    LENUS (Irish Health Repository)

    Morgan, Ross K

    2011-03-01

    Interventional pulmonology encompasses diagnostic and therapeutic bronchoscopic procedures, and pleural interventions. In the last 10 years older techniques have been refined and exciting new technologies have extended the reach and application of the instruments used. The main areas within pulmonary medicine for which these interventions have a role are malignant and nonmalignant airway disease, pleural effusion, pneumothorax, and artificial airways. There are no data from well-designed prospective trials to guide recommendations for interventional pulmonary procedures in pregnancy. The recommendations provided in this article are based on critical review of reported case series, opinion from recognized experts, and personal observations.

  3. FFTF operations procedures preparation guide. Revision 2

    International Nuclear Information System (INIS)

    1976-12-01

    The Guide is intended to provide guidelines for the initial preparation of FFTF Operating Procedures. The Procedures Preparation Guide was developed from the plan presented and approved in the FFTF Reactor Plant Procedures Plan, PC-1, Revision 3

  4. Role of the C-E owner group in the nuclear industry

    International Nuclear Information System (INIS)

    Gasper, J.K.

    1988-01-01

    The Combustion Engineering (C-E) owner group was formed in 1979 to address the technical and regulatory issues for plants with nuclear steam supply systems supplied by C-E that resulted from the accident at the Three Mile Island plant. The group addressed many of the immediate concerns from the accident including the response of C-E owner-group plants to small-break loss-of-coolant accidents, the use of power-operated relief valves, emergency operating procedure upgrades, as well as transient and accident responses. The group was successful in addressing these technical and regulatory issues with the US Nuclear Regulatory Commission in such a manner that C-E owner-group plants were not required to shut down or operate at reduced power levels. In recent years, the group has increasingly pursued programs for the benefit of its members rather than because of a regulatory commitment. The major current activities of the group are programs to support the design basis reconstruction of our member plants, improvements to emergency procedure guidelines, which are the basis for the emergency operating procedures used in our plants, a charging pump performance improvement program, various activities to reduce the number of unplanned reactor scrams at our plants, modeling of steam generator corrosion mechanisms to improve steam generator performance, and leak-before-break justification of reactor coolant system piping

  5. Evaluation of flawed-pipe experiments: Final report

    Energy Technology Data Exchange (ETDEWEB)

    Zahoor, A.; Gamble, R.M.

    1986-11-01

    The purpose of this work was to perform elastic plastic fracture mechanics evaluations of experimental data that have become available from the NRC Degraded Pipe Program, Phase II (DPII) and other NRC and EPRI sponsored programs. These evaluations were used to assess flaw evaluation procedures for austenitic and ferritic steel piping. The results also have application to leak before break fracture mechanics analysis. An improved relationship was developed for computing the J-Integral for pipes containing throughwall flaws and loaded in pure bending. The results from several DPII experiments were compared to predictions based on new J estimation scheme solutions for circumferential, finite length part-throughwall flaws in pipes with bending loading. Comparisons of experimental maximum loads with those predicted using procedures in Paragraph IWB-3640, Section XI of the ASME Code indicate that the Code flaw evaluation procedures and allowables for austenitic steel pipe are appropriate and conservative. However, the comparisons also indicate that the base metal Code allowable loads may be about 15 to 20% high for small diameter piping (less than 8-inch diameter) at allowable a/t larger than about 0.5. The work further indicates that there is justification for reducing the conservatism in IWB-3640 allowable flaw sizes and loads for austenitic steel pipe with submerged or shielded metal arc welds.

  6. Guide to Alabama Court Procedures.

    Science.gov (United States)

    Alabama Administrative Office of Courts, Montgomery.

    Designed to assist the public in understanding the judicial system and judicial process in Alabama, this handbook (1) presents an overview of Alabama's courts and their jurisdictions, (2) identifies the officers of the courts and the contributions each makes to the judicial process, and (3) narrates in general terms the procedures most common to…

  7. On Procedural Freedom of Choice

    NARCIS (Netherlands)

    Arlegi, R.; Dimitrov, D.A.

    2004-01-01

    Numerous works in the last decade have analyzed the question of how to compare opportunity sets as a way to measure and evaluate individual freedom of choice.This paper defends that, in many contexts, external procedural aspects that are associated to an opportunity set should be taken into account

  8. Core calculational techniques and procedures

    International Nuclear Information System (INIS)

    Romano, J.J.

    1977-10-01

    Described are the procedures and techniques employed by B and W in core design analyses of power peaking, control rod worths, and reactivity coefficients. Major emphasis has been placed on current calculational tools and the most frequently performed calculations over the operating power range

  9. Environmental Impact Assessment: A Procedure.

    Science.gov (United States)

    Stover, Lloyd V.

    Prepared by a firm of consulting engineers, this booklet outlines the procedural "whys and hows" of assessing environmental impact, particularly for the construction industry. Section I explores the need for environmental assessment and evaluation to determine environmental impact. It utilizes a review of the National Environmental Policy Act and…

  10. International evaluation procedure for Supergrants

    OpenAIRE

    2010-01-01

    Sergey Ivanets, director of the department of international integration at the Ministry of Education and Science, talks about the specifics of the evaluation procedures for inviting leading scientists (Decree of the Government of the Russian Federation dated April 9, 2010, N 220: "On Measures for Attracting Leading Scientists into Russian Higher Professional Educational Institutions")

  11. Cognitive Procedures and Hyperbolic Discounting

    NARCIS (Netherlands)

    Nir, A.

    2004-01-01

    "Hyperbolic discount functions are characterized by a relatively high discount rate over short horizons and a relatively low discount rate over long horizons" (Laibson 1997).We suggest two cognitive procedures where individuals perceive future utility as decreasing at a decreasing rate as a function

  12. Safety procedures for radiography works

    International Nuclear Information System (INIS)

    Abd Nasir Ibrahim; Azali Muhammad; Ab Razak Hamzah; Abd Aziz Mohamed; Mohammad Pauzi Ismail

    2004-01-01

    The following subjects are discussed - Work preparation: before exposure, during exposure, after work completion. Radiographic work at the open site: types of open sites, establishment of radiographic boundary, storage of radiographic equipment at sites. Safety procedures for radiography works; radiographic works in exposure room

  13. Postoperative Complications of Beger Procedure

    Directory of Open Access Journals (Sweden)

    Nayana Samejima Peternelli

    2015-01-01

    Full Text Available Introduction. Chronic pancreatitis (CP is considered an inflammatory disease that may cause varying degrees of pancreatic dysfunction. Conservative and surgical treatment options are available depending on dysfunction severity. Presentation of Case. A 36-year-old male with history of heavy alcohol consumption and diagnosed CP underwent a duodenal-preserving pancreatic head resection (DPPHR or Beger procedure after conservative treatment failure. Refractory pain was reported on follow-up three months after surgery and postoperative imaging uncovered stones within the main pancreatic duct and intestinal dilation. The patient was subsequently subjected to another surgical procedure and intraoperative findings included protein plugs within the main pancreatic duct and pancreaticojejunal anastomosis stricture. A V-shaped enlargement and main pancreatic duct dilation in addition to the reconstruction of the previous pancreaticojejunal anastomosis were performed. The patient recovered with no further postoperative complications in the follow-up at an outpatient clinic. Discussion. Main duct and pancreaticojejunal strictures are an unusual complication of the Beger procedure but were identified intraoperatively as the cause of patient’s refractory pain and explained intraductal protein plugs accumulation. Conclusion. Patients that undergo Beger procedures should receive close outpatient clinical follow-up in order to guarantee postoperative conservative treatment success and therefore guarantee an early detection of postoperative complications.

  14. Procedural learning during declarative control.

    Science.gov (United States)

    Crossley, Matthew J; Ashby, F Gregory

    2015-09-01

    There is now abundant evidence that human learning and memory are governed by multiple systems. As a result, research is now turning to the next question of how these putative systems interact. For instance, how is overall control of behavior coordinated, and does learning occur independently within systems regardless of what system is in control? Behavioral, neuroimaging, and neuroscience data are somewhat mixed with respect to these questions. Human neuroimaging and animal lesion studies suggest independent learning and are mostly agnostic with respect to control. Human behavioral studies suggest active inhibition of behavioral output but have little to say regarding learning. The results of two perceptual category-learning experiments are described that strongly suggest that procedural learning does occur while the explicit system is in control of behavior and that this learning might be just as good as if the procedural system was controlling the response. These results are consistent with the idea that declarative memory systems inhibit the ability of the procedural system to access motor output systems but do not prevent procedural learning. (c) 2015 APA, all rights reserved).

  15. Current procedural terminology; a primer.

    Science.gov (United States)

    Hirsch, Joshua A; Leslie-Mazwi, Thabele M; Nicola, Gregory N; Barr, Robert M; Bello, Jacqueline A; Donovan, William D; Tu, Raymond; Alson, Mark D; Manchikanti, Laxmaiah

    2015-04-01

    In 1966, The American Medical Association (AMA) working with multiple major medical specialty societies developed an iterative coding system for describing medical procedures and services using uniform language, the Current Procedural Terminology (CPT) system. The current code set, CPT IV, forms the basis of reporting most of the services performed by healthcare providers, physicians and non-physicians as well as facilities allowing effective, reliable communication among physician and other providers, third parties and patients. This coding system and its maintenance has evolved significantly since its inception, and now goes well beyond its readily perceived role in reimbursement. Additional roles include administrative management, tracking new and investigational procedures, and evolving aspects of 'pay for performance'. The system also allows for local, regional and national utilization comparisons for medical education and research. Neurointerventional specialists use CPT category I codes regularly--for example, 36,215 for first-order cerebrovascular angiography, 36,216 for second-order vessels, and 37,184 for acute stroke treatment by mechanical means. Additionally, physicians add relevant modifiers to the CPT codes, such as '-26' to indicate 'professional charge only,' or '-59' to indicate a distinct procedural service performed on the same day. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

  16. SSR240612 [(2R)-2-[((3R)-3-(1,3-benzodioxol-5-yl)-3-[[(6-methoxy-2-naphthyl)sulfonyl]amino]propanoyl)amino]-3-(4-[[2R,6S)-2,6-dimethylpiperidinyl]methyl]phenyl)-N-isopropyl-N-methylpropanamide hydrochloride], a new nonpeptide antagonist of the bradykinin B1 receptor: biochemical and pharmacological characterization.

    Science.gov (United States)

    Gougat, Jean; Ferrari, Bernard; Sarran, Lionel; Planchenault, Claudine; Poncelet, Martine; Maruani, Jeanne; Alonso, Richard; Cudennec, Annie; Croci, Tiziano; Guagnini, Fabio; Urban-Szabo, Katalin; Martinolle, Jean-Pierre; Soubrié, Philippe; Finance, Olivier; Le Fur, Gérard

    2004-05-01

    The biochemical and pharmacological properties of a novel non-peptide antagonist of the bradykinin (BK) B(1) receptor, SSR240612 [(2R)-2-[((3R)-3-(1,3-benzodioxol-5-yl)-3-[[(6-methoxy-2-naphthyl)sulfonyl]amino]propanoyl)amino]-3-(4-[[2R,6S)-2,6-dimethylpiperidinyl]methyl]phenyl)-N-isopropyl-N-methylpropanamide hydrochloride] were evaluated. SSR240612 inhibited the binding of [(3)H]Lys(0)-des-Arg(9)-BK to the B(1) receptor in human fibroblast MRC5 and to recombinant human B(1) receptor expressed in human embryonic kidney cells with inhibition constants (K(i)) of 0.48 and 0.73 nM, respectively. The compound selectivity for B(1) versus B(2) receptors was in the range of 500- to 1000-fold. SSR240612 inhibited Lys(0)-desAr(9)-BK (10 nM)-induced inositol monophosphate formation in human fibroblast MRC5, with an IC(50) of 1.9 nM. It also antagonized des-Arg(9)-BK-induced contractions of isolated rabbit aorta and mesenteric plexus of rat ileum with a pA(2) of 8.9 and 9.4, respectively. Antagonistic properties of SSR240612 were also demonstrated in vivo. SSR240612 inhibited des-Arg(9)-BK-induced paw edema in mice (3 and 10 mg/kg p.o. and 0.3 and 1 mg/kg i.p.). Moreover, SSR240612 reduced capsaicin-induced ear edema in mice (0.3, 3 and 30 mg/kg p.o.) and tissue destruction and neutrophil accumulation in the rat intestine following splanchnic artery occlusion/reperfusion (0.3 mg/kg i.v.). The compound also inhibited thermal hyperalgesia induced by UV irradiation (1 and 3 mg/kg p.o.) and the late phase of nociceptive response to formalin in rats (10 and 30 mg/kg p.o.). Finally, SSR240612 (20 and 30 mg/kg p.o.) prevented neuropathic thermal pain induced by sciatic nerve constriction in the rat. In conclusion, SSR240612 is a new, potent, and orally active specific non-peptide bradykinin B(1) receptor antagonist.

  17. Procedural Personas for Player Decision Modeling and Procedural Content Generation

    DEFF Research Database (Denmark)

    Holmgård, Christoffer

    2016-01-01

    ." These methods for constructing procedural personas are then integrated with existing procedural content generation systems, acting as critics that shape the output of these systems, optimizing generated content for different personas and by extension, different kinds of players and their decision making styles......How can player models and artificially intelligent (AI) agents be useful in early-stage iterative game and simulation design? One answer may be as ways of generating synthetic play-test data, before a game or level has ever seen a player, or when the sampled amount of play test data is very low....... This thesis explores methods for creating low-complexity, easily interpretable, generative AI agents for use in game and simulation design. Based on insights from decision theory and behavioral economics, the thesis investigates how player decision making styles may be defined, operationalised, and measured...

  18. Pediatric procedural sedation and analgesia

    Directory of Open Access Journals (Sweden)

    Meredith James

    2008-01-01

    Full Text Available Procedural sedation and analgesia (PSA is an evolving field in pediatric emergency medicine. As new drugs breach the boundaries of anesthesia in the Pediatric Emergency Department, parents, patients, and physicians are finding new and more satisfactory methods of sedation. Short acting, rapid onset agents with little or no lingering effects and improved safety profiles are replacing archaic regimens. This article discusses the warning signs and areas of a patient′s medical history that are particularly pertinent to procedural sedation and the drugs used. The necessary equipment is detailed to provide the groundwork for implementing safe sedation in children. It is important for practitioners to familiarize themselves with a select few of the PSA drugs, rather than the entire list of sedatives. Those agents most relevant to PSA in the pediatric emergency department are presented.

  19. Investigative procedures in thyroid cancer

    International Nuclear Information System (INIS)

    Samuel, A.M.

    1999-01-01

    One of the main objectives of the procedures is to establish the likelihood of malignancy in the thyroid gland prior to surgery and detect metastases after surgery. Thyroid imaging is discussed in the context of (a) its role in the diagnosis of the primary disease (b) in the investigation of post-operative residual disease and (c) its role in the follow-up of patients after radioiodine therapy

  20. New procedures in nuclear medicine

    International Nuclear Information System (INIS)

    Spencer, R.P.

    1989-01-01

    The authors review the recent emergence of functional studies in nuclear medicine in this critical and informative text. The new procedures are presented in terms of their underlying physiology, indications, contraindications, methodology, results, interpretation and relationship to other evaluations. The volume includes discussions on the central nervous system, interventional studies, cardiac studies, bone densitometry, plus radiolabeled antibodies, radiolabeling of blood elements and flow and distribution

  1. Surface Environmental Surveillance Procedures Manual

    Energy Technology Data Exchange (ETDEWEB)

    RW Hanf; TM Poston

    2000-09-20

    Environmental surveillance data are used in assessing the impact of current and past site operations on human health and the environment, demonstrating compliance with applicable local, state, and federal environmental regulations, and verifying the adequacy of containment and effluent controls. SESP sampling schedules are reviewed, revised, and published each calendar year in the Hanford Site Environmental Surveillance Master Sampling Schedule. Environmental samples are collected by SESP staff in accordance with the approved sample collection procedures documented in this manual.

  2. Operating procedures and safety culture

    International Nuclear Information System (INIS)

    Carnino, A.

    1993-01-01

    The development of new technologies in recent years has led to a tremendous increase in the information to be mastered by operators in industrial processes. The information at operators disposal both in routine situations and accidental ones needs to be well prepared and organized to ensure reliability and safety. The man-machine interface should give operators all the necessary and clear indications on the process status and evolution so that the operators can operate the installation through adequate procedures. Procedures represent the real interface and mode of action of the operators on the machine, and they are of prime importance. Although they are by essence quite different, the routine, accident, and emergency procedures have in common one attribute: They all require a good safety culture both in their development and their implementation. From the definition given by the members of the International Nuclear Safety Advisory Group (INSAG), open-quotes Safety culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance,close quotes one can see that two aspects are embedded, a collective attitude that in fact is reflected in the managerial framework and an individual one that is linked to personnel behavior and work practices

  3. Computer managed emergency operating procedures

    International Nuclear Information System (INIS)

    Salamun, I.; Mavko, B.; Stritar, A.

    1994-01-01

    New computer technology is a very effective tool for developing a new design of nuclear power plant control room. It allows designer possibility to create a tool for managing with large database of power plant parameters and displaying them in different graphic forms and possibility of automated execution of well known task. The structure of Emergency Operating Procedures (EOP) is very suitable for programming and for creating expert system. The Computerized Emergency Operating Procedures (CEOP) described in this paper can be considered as an upgrading of standard EOP approach. EmDiSY (Emergency Display System - computer code name for CEOP) main purpose is to supply the operator with necessary information, to document all operator actions and to execute well known tasks. It is a function oriented CEOP that gives operator guidance on how to verify the critical safety functions and how to restore and maintain these functions where they are degraded. All knowledge is coded and stored in database files. The knowledge base consists from stepping order for verifying plant parameters, desired values of parameters, conditions for comparison and links between procedures and actions. Graphical shell allows users to read database, to follow instruction and to find out correct task. The desired information is concentrated in one screen and allows users to focus on a task. User is supported in two ways: desired parameter values are displayed on the process picture and automated monitoring critical safety function status trees are all time in progress and available to the user. (author). 4 refs, 4 figs

  4. INADMISSIBLE EVIDENCE IN CIVIL PROCEDURE

    Directory of Open Access Journals (Sweden)

    Mihajlo Dika

    2016-01-01

    Full Text Available This paper examines the exclusion of specific means of evidence as instruments for determining the object of evidence, as well as the taking of evidence in the framework of the Croatian civil procedure law. The introduction lays the grounds for classifying and qualifying exclusion of evidence (general, special; absolute, relative; removable, irremovable; direct, indirect, after which greater attention is paid to the so called absolute and relative type; exclusionary evidence of the direct relative type pertaining to the establishing of facts, and evidence dismissals. With regard to the indirect relative type, the paper examines exclusionary evidence concerning the object of evidence. The remainder of the paper focuses on illegally obtained evidence, while outlining the constitutional, statutory, judicature and doctrinaire premises of bearing for such evidence. Subsequently, the question of evidence obtained in violation of the Constitutional guarantee of respect and legal protection of private and family life, dignity, reputation and honour, as well as evidence obtained by breach of the Constitutional guarantee of freedom and secrecy of correspondence and all other forms of communication, and in violation of the right to safety and privacy of personal data, are discussed too. In addition, the paper analyses the institutions of preclusion of evidence and the so called informative evidence. Concluding, the author points to a lacking regulation of inadmissible evidence within the Croatian civil procedure law, underlining the need to determine de lege ferenda legal requirements with a view to operationalizing inadmissible evidence within the Croatian civil procedure law.

  5. 18 CFR 301.3 - Filing procedures.

    Science.gov (United States)

    2010-04-01

    ... FOR SALES FROM UTILITIES TO BONNEVILLE POWER ADMINISTRATION UNDER NORTHWEST POWER ACT § 301.3 Filing procedures. (a) Bonneville's ASC review procedures. The procedures established by Bonneville's Administrator... Bonneville's ASC review procedures. (b) Exchange Period. The Exchange Period will be equal to the term of...

  6. An improved ashing procedure for biologic sample

    Energy Technology Data Exchange (ETDEWEB)

    Zongmei, Wu [Zhejiang Province Enviromental Radiation Monitoring Centre (China)

    1992-07-01

    The classical ashing procedure in muffle was modified for biologic samples. In the modified procedure the door of muffle was open in the duration of ashing process, the ashing was accelerated and the ashing product quality was comparable to that the classical procedure. The modified procedure is suitable for ashing biologic samples in large batches.

  7. An improved ashing procedure for biologic sample

    International Nuclear Information System (INIS)

    Wu Zongmei

    1992-01-01

    The classical ashing procedure in muffle was modified for biologic samples. In the modified procedure the door of muffle was open in the duration of ashing process, the ashing was accelerated and the ashing product quality was comparable to that the classical procedure. The modified procedure is suitable for ashing biologic samples in large batches

  8. Series expansion of the modified Einstein Procedure

    Science.gov (United States)

    Seema Chandrakant Shah-Fairbank

    2009-01-01

    This study examines calculating total sediment discharge based on the Modified Einstein Procedure (MEP). A new procedure based on the Series Expansion of the Modified Einstein Procedure (SEMEP) has been developed. This procedure contains four main modifications to MEP. First, SEMEP solves the Einstein integrals quickly and accurately based on a series expansion. Next,...

  9. Research Activities on Development of Piping Design Methodology of High Temperature Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Huh, Nam-Su [Seoul National Univ. of Science and Technology, Seoul(Korea, Republic of); Won, Min-Gu [Sungkyukwan Univ., Suwon (Korea, Republic of); Oh, Young-Jin [KEPCO Engineering and Construction Co. Inc., Gimcheon (Korea, Republic of); Lee, Hyeog-Yeon; Kim, Yoo-Gon [Korea Atomic Energy Research Institute, Daejeon(Korea, Republic of)

    2016-10-15

    A SFR is operated at high temperature and low pressure compared with commercial pressurized water reactor (PWR), and such an operating condition leads to time-dependent damages such as creep rupture, excessive creep deformation, creep-fatigue interaction and creep crack growth. Thus, high temperature design and structural integrity assessment methodology should be developed considering such failure mechanisms. In terms of design of mechanical components of SFR, ASME B and PV Code, Sec. III, Div. 5 and RCC-MRx provide high temperature design and assessment procedures for nuclear structural components operated at high temperature, and a Leak-Before-Break (LBB) assessment procedure for high temperature piping is also provided in RCC-MRx, A16. Three web-based evaluation programs based on the current high temperature codes were developed for structural components of high temperature reactors. Moreover, for the detailed LBB analyses of high temperature piping, new engineering methods for predicting creep C*-integral and creep COD rate based either on GE/EPRI or on reference stress concepts were proposed. Finally, the numerical methods based on Garofalo's model and RCC-MRx have been developed, and they have been implemented into ABAQUS. The predictions based on both models were compared with the experimental results, and it has been revealed that the predictions from Garafalo's model gave somewhat successful results to describe the deformation behavior of Gr. 91 at elevated temperatures.

  10. Seismic design assessment by experimental methods. Notes from the workshop. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The workshop intended to provide training on the application of experimental techniques (mainly laboratory testing) as support to the seismic design of structures, equipment and components for nuclear power plants. The focus was on the activities planned by Nuclear Power Institute of China (NPIC) in the near future, and most of the lectures provided by the attendees, dealing with these national activities, were the basis for the discussion with the IAEA experts. Special modules were identified for the workshop, dealing with: Numerical models: detailing and comparison techniques; On site testing of structures and equipment; Special problems: Leak before Break (LBB), thermal effects, combination of seismic with other loads; General seismic behavior and design criteria for fuel assembly and core structures; Seismic qualification methodologies for reactor core, mechanical components, I and C and piping; Balancing analysis and test in seismic qualification; Design of mock-up: selection of seismic input, detailing, scaling and similitudes, selection of sensors and their location; Test planning and conduct, basic documents and specifications; Quality assurance and technical procedures in laboratory testing; Data processing techniques and interface with the numerical models. The material used for presentations by the lecturers and by the national attendees is collected in this volume together with some background literature provided by the experts with up to date references and procedures. A special chapter is added to these proceedings with the content of the discussion, for future reference and as a complement to the lectures content, more oriented to the specific, immediate needs of the attendees.

  11. Seismic design assessment by experimental methods. Notes from the workshop. Working material

    International Nuclear Information System (INIS)

    2001-01-01

    The workshop intended to provide training on the application of experimental techniques (mainly laboratory testing) as support to the seismic design of structures, equipment and components for nuclear power plants. The focus was on the activities planned by Nuclear Power Institute of China (NPIC) in the near future, and most of the lectures provided by the attendees, dealing with these national activities, were the basis for the discussion with the IAEA experts. Special modules were identified for the workshop, dealing with: Numerical models: detailing and comparison techniques; On site testing of structures and equipment; Special problems: Leak before Break (LBB), thermal effects, combination of seismic with other loads; General seismic behavior and design criteria for fuel assembly and core structures; Seismic qualification methodologies for reactor core, mechanical components, I and C and piping; Balancing analysis and test in seismic qualification; Design of mock-up: selection of seismic input, detailing, scaling and similitudes, selection of sensors and their location; Test planning and conduct, basic documents and specifications; Quality assurance and technical procedures in laboratory testing; Data processing techniques and interface with the numerical models. The material used for presentations by the lecturers and by the national attendees is collected in this volume together with some background literature provided by the experts with up to date references and procedures. A special chapter is added to these proceedings with the content of the discussion, for future reference and as a complement to the lectures content, more oriented to the specific, immediate needs of the attendees

  12. Failure assessment and evaluation of critical crack length for a fresh Zr-2 pressure tube of an Indian PHWR

    International Nuclear Information System (INIS)

    Krishnan, Suresh; Bhasin, Vivek; Kushwaha, H.S.; Mahajan, S.C.; Kakodkar, A.

    1996-01-01

    Fracture analysis of Zr-2 pressure tubes having through wall axial crack was done using finite element method. The analysis was done for tubes in as received condition. During reactor operation the mechanical properties of Zr-2 undergo changes. The analysis is valid for pressure tubes of newly commissioned reactors. The main aim of the study was to determine critical crack length of pressure tubes in normal operating conditions. Elastic plastic fracture analysis was done for different crack lengths to determine applied J-integral values. Tearing modulus instability concept was used to evaluate critical crack length. One of the important parameter studied was, the effect of crack face pressure, which leaking fluid exert on the crack faces/lips of through wall axial crack. Its effect was found to be significant for pressure tubes. It increases the applied J-integral values. Approximate analytical solutions which takes into account the plasticity ahead of crack tip, are available and widely used. These formulae do not take into account the crack face pressure. Since, for the present situation the effect of crack face pressure is significant hence, detailed finite analysis was necessary. Detailed 3D finite element analysis gives an insight into the variation of J-integral values over the thickness of pressure tube. It was found that J values are maximum at the middle layer of the tube. A peak factor on J values was defined and evaluated as ratio of maximum J to average J across the thickness, crack opening area for each length was also evaluated. The knowledge of crack opening area is useful for leak before break studies. The failure assessment was also done using Central Electricity Generating Board (CEGB) R-6 method considering the ductile tearing. The reserve factors (or safety margins) for different crack lengths was evaluated using R-6 method. (author). 30 refs., 21 figs., 34 tabs

  13. Revised Unfilling Procedure for Solid Lithium Lenses

    International Nuclear Information System (INIS)

    Leveling, A.

    2003-01-01

    A procedure for unfilling used lithium lenses to has been described in Pbar Note 664. To date, the procedure has been used to disassemble lenses 20, 21, 17, 18, and 16. As a result of this work, some parts of the original procedure were found to be time consuming and ineffective. Modifications to the original procedure have been made to streamline the process and are discussed in this note. The revised procedure is included in this note.

  14. Efficiency of performing pulmonary procedures in a shared endoscopy unit: procedure time, turnaround time, delays, and procedure waiting time.

    Science.gov (United States)

    Verma, Akash; Lee, Mui Yok; Wang, Chunhong; Hussein, Nurmalah B M; Selvi, Kalai; Tee, Augustine

    2014-04-01

    The purpose of this study was to assess the efficiency of performing pulmonary procedures in the endoscopy unit in a large teaching hospital. A prospective study from May 20 to July 19, 2013, was designed. The main outcome measures were procedure delays and their reasons, duration of procedural steps starting from patient's arrival to endoscopy unit, turnaround time, total case durations, and procedure wait time. A total of 65 procedures were observed. The most common procedure was BAL (61%) followed by TBLB (31%). Overall procedures for 35 (53.8%) of 65 patients were delayed by ≥ 30 minutes, 21/35 (60%) because of "spillover" of the gastrointestinal and surgical cases into the time block of pulmonary procedure. Time elapsed between end of pulmonary procedure and start of the next procedure was ≥ 30 minutes in 8/51 (16%) of cases. In 18/51 (35%) patients there was no next case in the room after completion of the pulmonary procedure. The average idle time of the room after the end of pulmonary procedure and start of next case or end of shift at 5:00 PM if no next case was 58 ± 53 minutes. In 17/51 (33%) patients the room's idle time was >60 minutes. A total of 52.3% of patients had the wait time >2 days and 11% had it ≥ 6 days, reason in 15/21 (71%) being unavailability of the slot. Most pulmonary procedures were delayed due to spillover of the gastrointestinal and surgical cases into the block time allocated to pulmonary procedures. The most common reason for difficulty encountered in scheduling the pulmonary procedure was slot unavailability. This caused increased procedure waiting time. The strategies to reduce procedure delays and turnaround times, along with improved scheduling methods, may have a favorable impact on the volume of procedures performed in the unit thereby optimizing the existing resources.

  15. PRINCIPLES AND PROCEDURES ON FISCAL

    Directory of Open Access Journals (Sweden)

    Morar Ioan Dan

    2011-07-01

    Full Text Available Fiscal science advertise in most analytical situations, while the principles reiterated by specialists in the field in various specialized works The two components of taxation, the tax system relating to the theoretical and the practical procedures relating to tax are marked by frequent references and invocations of the underlying principles to tax. This paper attempts a return on equity fiscal general vision as a principle often invoked and used to justify tax policies, but so often violated the laws fiscality . Also want to emphasize the importance of devising procedures to ensure fiscal equitable treatment of taxpayers. Specific approach of this paper is based on the notion that tax equity is based on equality before tax and social policies of the executive that would be more effective than using the other tax instruments. I want to emphasize that if the scientific approach to justify the unequal treatment of the tax law is based on the various social problems of the taxpayers, then deviates from the issue of tax fairness justification explaining the need to promote social policies usually more attractive to taxpayers. Modern tax techniques are believed to be promoted especially in order to ensure an increasing level of high efficiency at the expense of the taxpayers obligations to ensure equality before the law tax. On the other hand, tax inequities reaction generates multiple recipients from the first budget plan, but finalities unfair measures can not quantify and no timeline for the reaction, usually not known. But while statistics show fluctuations in budgetary revenues and often find in literature reviews and analysis relevant to a connection between changes in government policies, budget execution and outcome. The effects of inequality on tax on tax procedures and budgetary revenues are difficult to quantify and is among others to this work. Providing tax equity without combining it with the principles of discrimination and neutrality

  16. Instrument Calibration and Certification Procedure

    Energy Technology Data Exchange (ETDEWEB)

    Davis, R. Wesley [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-05-31

    The Amptec 640SL-2 is a 4-wire Kelvin failsafe resistance meter, designed to reliably use very low-test currents for its resistance measurements. The 640SL-1 is a 2-wire version, designed to support customers using the Reynolds Industries type 311 connector. For both versions, a passive (analog) dual function DC Milliameter/Voltmeter allows the user to verify the actual 640SL output current level and the open circuit voltage on the test leads. This procedure includes tests of essential performance parameters. Any malfunction noticed during calibration, whether specifically tested for or not, shall be corrected before calibration continues or is completed.

  17. Inspection system performance test procedure

    International Nuclear Information System (INIS)

    Jensen, C.E.

    1995-01-01

    This procedure establishes requirements to administer a performance demonstration test. The test is to demonstrate that the double-shell tank inspection system (DSTIS) supplied by the contractor performs in accordance with the WHC-S-4108, Double-Shell Tank Ultrasonic Inspection Performance Specification, Rev. 2-A, January, 1995. The inspection system is intended to provide ultrasonic (UT) and visual data to determine integrity of the Westinghouse Hanford Company (WHC) site underground waste tanks. The robotic inspection system consists of the following major sub-systems (modules) and components: Mobile control center; Deployment module; Cable management assembly; Robot mechanism; Ultrasonic testing system; Visual testing system; Pneumatic system; Electrical system; and Control system

  18. Procedure for taking physical inventories

    International Nuclear Information System (INIS)

    Boston, R.A.

    1984-01-01

    Physical inventories are taken periodically to meet Company, State and IAEA requirements. Those physical inventories may be verified by IAEA and/or State inspectors. This presentation describes in an introductory but detailed manner the approaches and procedures used in planning, preparing, conducting, reconciling and reporting physical inventories for the Model Plant. Physical inventories are taken for plant accounting purposes to provide an accurate basis for starting and closing the plant material balance. Physical inventories are also taken for safeguards purposes to provide positive assurance that the nuclear materials of concern are indeed present and accounted for

  19. Capital Investment Procedures for FEMYSO

    OpenAIRE

    Oluduro, Francis Oladele; Duru, Longinus; Al Jaafar, Mofid

    2008-01-01

    Date: 2008-06-05 Level: Bachelor Thesis in Business Administration EF0703, 15 ECTS Credits. Authors: Longinus Duru (Stockholm), Francis O.Oluduro (Västerås) and Mofid Al Jaafar (Västerås) Title: Capital Investment Procedures for FEMYSO Problem Area: Undertaking an investment by FEMYSO involves weighing up the risk against the returns but still capital investment decision are still one of the most undertaken decisions by organization managers because it involves commitment of huge amount of mo...

  20. Forthcoming indefinite contract review procedure

    CERN Multimedia

    Human Resources Department

    2011-01-01

    The vacancy notices for posts opened with a view to the award of an indefinite contract will be published in early April 2011. In the meantime, the list of posts to be opened this spring is available at the following address: Indefinite contract posts - spring 2011 A second exercise will take place in autumn 2011 and, as of 2012, the indefinite contract award procedure will only be held once a year, in autumn. For more information please consult: https://hr-recruit.web.cern.ch/hr-recruit/staff/IndefiniteContracts.asp  

  1. Waste segregation procedures and benefits

    International Nuclear Information System (INIS)

    Fish, J.D.; Massey, C.D.; Ward, S.J.

    1990-01-01

    Segregation is a critical first step in handling hazardous and radioactive materials to minimize the generation of regulated wastes. In addition, segregation can significantly reduce the complexity and the total cost of managing waste. Procedures at Sandia National Laboratories, Albuquerque require that wastes be segregated, first, by waste type (acids, solvents, low level radioactive, mixed, classified, etc.). Higher level segregation requirements, currently under development, are aimed at enhancing the possibilities for recovery, recycle and reapplication; reducing waste volumes; reducing waste disposal costs, and facilitating packaging storage, shipping and disposal. 2 tabs

  2. Vasoplegic syndrome during Whipple procedure.

    Science.gov (United States)

    Anandaswamy, Tejesh C; Rajappa, Geetha C; Krishnamachar, Harish

    2017-02-01

    Vasoplegic syndrome is an unusual cause of refractory hypotension under general anesthesia. It is commonly described in the setting of cardiac surgery, but rarely seen in noncardiac setting. We describe successful management of vasoplegic syndrome during Whipple procedure with vasopressin infusion. A high index of suspicion and prompt treatment with vasopressin can be lifesaving in patients with risk factors for vasoplegic syndrome who present with severe refractory hypotension and who respond poorly to fluid administration and routine vasopressor infusion. Copyright © 2016 Elsevier Inc. All rights reserved.

  3. Entangled entanglement: A construction procedure

    Energy Technology Data Exchange (ETDEWEB)

    Uchida, Gabriele, E-mail: Gabriele.Uchida@univie.ac.at [University of Vienna, Faculty of Computer Science, Währinger Strasse 29, 1090 Vienna (Austria); Bertlmann, Reinhold A., E-mail: Reinhold.Bertlmann@univie.ac.at [University of Vienna, Faculty of Physics, Boltzmanngasse 5, 1090 Vienna (Austria); Hiesmayr, Beatrix C., E-mail: Beatrix.Hiesmayr@univie.ac.at [University of Vienna, Faculty of Physics, Boltzmanngasse 5, 1090 Vienna (Austria)

    2015-10-30

    The familiar Greenberger–Horne–Zeilinger (GHZ) states can be rewritten by entangling the Bell states for two qubits with a third qubit state, which is dubbed entangled entanglement. We show that in a constructive way we obtain all eight independent GHZ states that form the simplex of entangled entanglement, the magic simplex. The construction procedure allows a generalization to higher dimensions both, in the degrees of freedom (considering qudits) as well as in the number of particles (considering n-partite states). Such bases of GHZ-type states exhibit a cyclic geometry, a Merry Go Round, that is relevant for experimental and quantum information theoretic applications.

  4. Radiation risk of diagnostical procedures

    International Nuclear Information System (INIS)

    Pohlit, W.

    1986-01-01

    The environmental radiation burden of man in Germany is about 1 mGy (Milligray) per year. This is, of course, also valid for children. Due to diagnostical procedures this burden is increased to about 1.3 mGy. The question arises wether this can be neglected, or important consequences have to be drawn. To give a clear answer, the action of ionizing radiation in living cells and in organisms is explained in detail. Many of the radiation actions at the DNA can soon be repaired by the cell, if the radiation dose was small. Some damage, however will remain irreparable for the cell and consequently leads to cell death, to mutations or to cell transformation. The number of these lesion increases or decreases linearily with radiation dose. Therefore, it must be expected that the risk of tumour induction is increased to above the normal background even by the smallest doses. This small but not negligible risk has to be compared with other risks of civilization or with other medical risks. But also the benefit and the efficacy of diagnostic procedures have to be considered. (orig./HSCH) [de

  5. Procedure to describe clavicular motion.

    Science.gov (United States)

    Gutierrez Delgado, Guivey; De Beule, Matthieu; Ortega Cardentey, Dolgis R; Segers, Patrick; Iznaga Benítez, Arsenio M; Rodríguez Moliner, Tania; Verhegghe, Benedict; Palmans, Tanneke; Van Hoof, Tom; Van Tongel, Alexander

    2017-03-01

    For many years, researchers have attempted to describe shoulder motions by using different mathematical methods. The aim of this study was to describe a procedure to quantify clavicular motion. The procedure proposed for the kinematic analysis consists of 4 main processes: 3 transcortical pins in the clavicle, motion capture, obtaining 3-dimensional bone models, and data processing. Clavicular motion by abduction (30° to 150°) and flexion (55° to 165°) were characterized by an increment of retraction of 27° to 33°, elevation of 25° to 28°, and posterior rotation of 14° to 15°, respectively. In circumduction, clavicular movement described an ellipse, which was reflected by retraction and elevation. Kinematic analysis shows that the articular surfaces move by simultaneously rolling and sliding on the convex surface of the sternum for the 3 movements of abduction, flexion, and circumduction. The use of 3 body landmarks in the clavicle and the direct measurement of bone allowed description of the osteokinematic and arthrokinematic movement of the clavicle. Copyright © 2017 Journal of Shoulder and Elbow Surgery Board of Trustees. Published by Elsevier Inc. All rights reserved.

  6. Geologic mapping procedure: Final draft

    International Nuclear Information System (INIS)

    1987-09-01

    Geologic mapping will provide a baseline record of the subsurface geology in the shafts and drifts of the Exploratory Shaft Facility (ESF). This information will be essential in confirming the specific repository horizon, selecting representative locations for the in situ tests, providing information for construction and decommissioning seal designs, documenting the excavation effects, and in providing information for performance assessment, which relates to the ultimate suitability of the site as a nuclear waste repository. Geologic mapping will be undertaken on the walls and roof, and locally on the floor within the completed At-Depth Facility (ADF) and on the walls of the two access shafts. Periodic mapping of the exposed face may be conducted during construction of the ADF. The mapping will be oriented toward the collection and presentation of geologic information in an engineering format and the portrayal of detailed stratigraphic information which may be useful in confirmation of drillhole data collected as part of the surface-based testing program. Geologic mapping can be considered as a predictive tool as well as a means of checking design assumptions. This document provides a description of the required procedures for geologic mapping for the ESF. Included in this procedure is information that qualified technical personnel can use to collect the required types of geologic descriptions, at the appropriate level of detail. 5 refs., 3 figs., 1 tab

  7. Surface Environmental Surveillance Procedures Manual

    International Nuclear Information System (INIS)

    Hanf, Robert W.; Poston, Ted M.

    2000-01-01

    Shows and explains certain procedures needed for surface environmental surveillance. Hanford Site environmental surveillance is conducted by the Pacific Northwest National Laboratory (PNNL) for the U.S. Department of Energy (DOE) under the Surface Environmental Surveillance Project (SESP). The basic requirements for site surveillance are set fourth in DOE Order 5400.1, General Environmental Protection Program Requirements. Guidance for the SESP is provided in DOE Order 5484.1, Environmental Protection, Safety, and Health Protection Information Reporting Requirements and DOE Order 5400.5, Radiation Protection of the Public and Environment. Guidelines for environmental surveillance activities are provided in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance. An environmental monitoring plan for the Hanford Site is outlined in DOE/RL 91-50 Rev. 2, Environmental Monitoring Plan, United States Department of Energy, Richland Operations Office. Environmental surveillance data are used in assessing the impact of current and past site operations on human health and the environment, demonstrating compliance with applicable local, state, and federal environmental regulations, and verifying the adequacy of containment and effluent controls. SESP sampling schedules are reviewed, revised, and published each calendar year in the Hanford Site Environmental Surveillance Master Sampling Schedule. Environmental samples are collected by SESP staff in accordance with the approved sample collection procedures documented in this manual. Personnel training requirements are documented in SESP-TP-01 Rev.2, Surface Environmental Surveillance Project Training Program.

  8. CMOS gate array characterization procedures

    Science.gov (United States)

    Spratt, James P.

    1993-09-01

    Present procedures are inadequate for characterizing the radiation hardness of gate array product lines prior to personalization because the selection of circuits to be used, from among all those available in the manufacturer's circuit library, is usually uncontrolled. (Some circuits are fundamentally more radiation resistant than others.) In such cases, differences in hardness can result between different designs of the same logic function. Hardness also varies because many gate arrays feature large custom-designed megacells (e.g., microprocessors and random access memories-MicroP's and RAM's). As a result, different product lines cannot be compared equally. A characterization strategy is needed, along with standardized test vehicle(s), methodology, and conditions, so that users can make informed judgments on which gate arrays are best suited for their needs. The program described developed preferred procedures for the radiation characterization of gate arrays, including a gate array evaluation test vehicle, featuring a canary circuit, designed to define the speed versus hardness envelope of the gate array. A multiplier was chosen for this role, and a baseline multiplier architecture is suggested that could be incorporated into an existing standard evaluation circuit chip.

  9. [Procedural learning disorder: neuropsychological characteristics].

    Science.gov (United States)

    Crespo-Eguílaz, N; Narbona, J

    This research aims at neurocognitive delineation of the core features of procedural learning disorder (PLD), otherwise labeled as motor coordination disorder or non-verbal learning disorder. A sample of 209 correlative outpatients (73% males), aged 6-12 years, all of them having QI ranging from 81 to 120, was clustered into the following neurobehavioural groups: PLD (n = 16), PLD plus attention deficit hyperactivity disorder (ADHD) (n = 37), ADHD combined type (n = 47), ADHD predominantly inattentive type (n = 23), specific language impairment (n = 68), and semantic-pragmatic language impairment (n = 18). Two additional groups of patients were included for some comparisons: children with periventricular leukomalacia (PVL) without learning disability (n = 8) or associating PLD (n = 17). A set of behavioural scales and neurocognitive tests was used to evaluate verbal and non-verbal IQ, attention, impulsivity control, visuo-motor coordination, declarative memory, procedural memory and learning, formal and functional dimensions of language, peer relationships and academic achievement. Parametric analysis were used to test the differences and similarities of neurobehavioural variables between groups. Our results allow us to conclude that PLD implies a difficult acquisition of automatized motor, cognitive and communicative abilities required in school work and peer social relationships. PLD is different from autistic spectrum disorders. It is frequently associated to inattentive ADHD. Operational criteria for diagnosis of PLD are proposed, according to our results. A bilateral posterior parietal dysfunction is a plausible explanation of its physiopathology. Preserved general intelligence and formal linguistic abilities are the clues for intervention designs.

  10. Antibiotic prophylaxis in obstetric procedures.

    Science.gov (United States)

    van Schalkwyk, Julie; Van Eyk, Nancy

    2010-09-01

    To review the evidence and provide recommendations on antibiotic prophylaxis for obstetrical procedures. Outcomes evaluated include need and effectiveness of antibiotics to prevent infections in obstetrical procedures. Published literature was retrieved through searches of Medline and The Cochrane Library on the topic of antibiotic prophylaxis in obstetrical procedures. Results were restricted to systematic reviews, randomized controlled trials/controlled clinical trials, and observational studies. Searches were updated on a regular basis and articles published from January 1978 to June 2009 were incorporated in the guideline. Current guidelines published by the American College of Obstetrics and Gynecology were also incorporated. Grey (unpublished) literature was identified through searching the websites of health technology assessment and health technology assessment-related agencies, clinical practice guideline collections, clinical trial registries, and national and international medical specialty societies. The evidence obtained was reviewed and evaluated by the Infectious Diseases Committee of the Society of Obstetricians and Gynaecologists of Canada under the leadership of the principal authors, and recommendations were made according to guidelines developed by the Canadian Task Force on Preventive Health Care (Table 1). Implementation of this guideline should reduce the cost and harm resulting from the administration of antibiotics when they are not required and the harm resulting from failure to administer antibiotics when they would be beneficial. SUMMARY STATEMENTS: 1. Available evidence does not support the use of prophylactic antibiotics to reduce infectious morbidity following operative vaginal delivery. (II-1) 2. There is insufficient evidence to argue for or against the use of prophylactic antibiotics to reduce infectious morbidity for manual removal of the placenta. (III) 3. There is insufficient evidence to argue for or against the use of

  11. Physiotherapy following elective orthopaedic procedures.

    Science.gov (United States)

    De Kleijn, P; Blamey, G; Zourikian, N; Dalzell, R; Lobet, S

    2006-07-01

    As haemophilic arthropathy and chronic synovitis are still the most important clinical features in people with haemophilia, different kinds of invasive and orthopaedic procedures have become more common during the last decades. The availability of clotting factor has made arthroplasty of one, or even multiple joints possible. This article highlights the role of physiotherapy before and after such procedures. Synovectomies are sometimes advocated in people with haemophilia to stop repetitive cycles of intra-articular bleeds and/or chronic synovitis. The synovectomy itself, however, does not solve the muscle atrophy, loss of range of motion (ROM), instability and poor propriocepsis, often developed during many years. The key is in taking advantage of the subsequent, relatively safe, bleed-free period to address these important issues. Although the preoperative ROM is the most important variable influencing the postoperative ROM after total knee arthroplasty, there are a few key points that should be considered to improve the outcome. Early mobilization, either manual or by means of a continuous passive mobilization machine, can be an optimal solution during the very first postoperative days. Muscle isometric contractions and light open kinetic chain exercises should also be started in order to restore the quadriceps control. Partial weight bearing can be started shortly after, because of quadriceps inhibition and to avoid excessive swelling. The use of continuous clotting factor replacement permits earlier and intensive rehabilitation during the postoperative period. During the rehabilitation of shoulder arthroplasty restoring the function of the rotator cuff is of utmost importance. Often the rotator cuff muscles are inhibited in the presence of pain and loss of ROM. Physiotherapy also assists in improving pain and maintaining ROM and strength. Functional weight-bearing tasks, such as using the upper limbs to sit and stand, are often discouraged during the first 6

  12. Assessment of fracture toughness of structural steels

    Energy Technology Data Exchange (ETDEWEB)

    Gomes Junyor, José Onésimo; Faria, Stéfanno Bruno; Rocha, Nirlando Antônio; Reis, Emil; Vilela, Jefferson José, E-mail: ze_onezo@hotmail.com, E-mail: sbrunofaria@gmail.com, E-mail: nar@cdtn.br, E-mail: emilr@cdtn.br, E-mail: jjv@cdtn.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil); Centro Universitário de Belo Horizonte (UNIBH), MG (Brazil); Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-11-01

    The fracture toughness parameters are applied to estimate the lifetime of mechanical components and define the criteria of safe failure and tolerable damages. This information allows equipment to be used longer with a high degree of safety. These techniques are applied in the Leak-Before-Break (LBB) concept that is accepted for designing the piping system of the primary circuit of the pressurized water reactor (PWR). In this work, fracture toughness tests such as J{sub IC} and CTOD were performed on some structural steels. The fracture toughness parameters were determined using SE(B) and C(T) test specimens. The fracture toughness values for the same material varied according to the type specimen. The parameter δ{sub 1c} showed different values when it was calculated using the ASTM E1820 standard and using the BS 7448: Part 1 standard. These results indicate that procedures of these standards need to be improved. Two systems with different sensitivity in the force measurement were used that showed similar results for toughness fracture but the dispersion was different. (author)

  13. RCS Leak Rate Calculation with High Order Least Squares Method

    International Nuclear Information System (INIS)

    Lee, Jeong Hun; Kang, Young Kyu; Kim, Yang Ki

    2010-01-01

    As a part of action items for Application of Leak before Break(LBB), RCS Leak Rate Calculation Program is upgraded in Kori unit 3 and 4. For real time monitoring of operators, periodic calculation is needed and corresponding noise reduction scheme is used. This kind of study was issued in Korea, so there have upgraded and used real time RCS Leak Rate Calculation Program in UCN unit 3 and 4 and YGN unit 1 and 2. For reduction of the noise in signals, Linear Regression Method was used in those programs. Linear Regression Method is powerful method for noise reduction. But the system is not static with some alternative flow paths and this makes mixed trend patterns of input signal values. In this condition, the trend of signal and average of Linear Regression are not entirely same pattern. In this study, high order Least squares Method is used to follow the trend of signal and the order of calculation is rearranged. The result of calculation makes reasonable trend and the procedure is physically consistence

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

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  15. International Piping Integrity Research Group (IPIRG) Program. Final report

    International Nuclear Information System (INIS)

    Wilkowski, G.; Schmidt, R.; Scott, P.

    1997-06-01

    This is the final report of the International Piping Integrity Research Group (IPIRG) Program. The IPIRG Program was an international group program managed by the U.S. Nuclear Regulatory Commission and funded by a consortium of organizations from nine nations: Canada, France, Italy, Japan, Sweden, Switzerland, Taiwan, the United Kingdom, and the United States. The program objective was to develop data needed to verify engineering methods for assessing the integrity of circumferentially-cracked nuclear power plant piping. The primary focus was an experimental task that investigated the behavior of circumferentially flawed piping systems subjected to high-rate loadings typical of seismic events. To accomplish these objectives a pipe system fabricated as an expansion loop with over 30 meters of 16-inch diameter pipe and five long radius elbows was constructed. Five dynamic, cyclic, flawed piping experiments were conducted using this facility. This report: (1) provides background information on leak-before-break and flaw evaluation procedures for piping, (2) summarizes technical results of the program, (3) gives a relatively detailed assessment of the results from the pipe fracture experiments and complementary analyses, and (4) summarizes advances in the state-of-the-art of pipe fracture technology resulting from the IPIRG program

  16. Numerical evaluation of cracked pipes under dynamic loading

    International Nuclear Information System (INIS)

    Petit, M.; Jamet, P.

    1989-01-01

    In order to apply the leak-before-break concept to piping systems, the behavior of cracked pipes under dynamic, and especially seismic, loadings must be studied. A simple finite element model of a cracked pipe has been developed and implemented in the general purpose computer code CASTEM 2000. The model is a generalization of the approach proposed by Paris and Tada (1). Considered loads are bending moment and axial force (representing thermal expansion and internal pressure.) The elastic characteristics of the model are determined using the Zahoor formulae for the geometry-dependent factors. Owing to the material behabior plasticity must be taken into account. To represent the crack growth, the material is defined by two characteristic values: J 1c which is the level of energy corresponding to crack initiation and the tearing modulus, T, which governs the length of propagation of the crack. For dynamic loads, unilateral conditions are imposed to represent crack closure. The model has been used for the design of dynamic tests to be conducted on shaking tables. Test principle is briefly described and numerical results are presented. Finally evaluation of margin, due to plasticity, in comparison with the standard design procedure is made

  17. International piping integrity research group (IPIRG) program final report

    International Nuclear Information System (INIS)

    Schmidt, R.; Wilkowski, G.; Scott, P.; Olsen, R.; Marschall, C.; Vieth, P.; Paul, D.

    1992-04-01

    This is the final report of the International Piping Integrity Research Group (IPIRG) Programme. The IPIRG Programme was an international group programme managed by the U.S. Nuclear Regulatory Commission and funded by a consortium of organizations from nine nations: Canada, France, Italy, Japan, Sweden, Switzerland, Taiwan, the United Kingdom, and the United states. The objective of the programme was to develop data needed to verify engineering methods for assessing the integrity of nuclear power plant piping that contains circumferential defects. The primary focus was an experimental task that investigated the behaviour of circumferentially flawed piping and piping systems to high-rate loading typical of seismic events. To accomplish these objectives a unique pipe loop test facility was designed and constructed. The pipe system was an expansion loop with over 30 m of 406-mm diameter pipe and five long radius elbows. Five experiments on flawed piping were conducted to failure in this facility with dynamic excitation. The report: provides background information on leak-before-break and flaw evaluation procedures in piping; summarizes the technical results of the programme; gives a relatively detailed assessment of the results from the various pipe fracture experiments and complementary analyses; and, summarizes the advances in the state-of-the-art of pipe fracture technology resulting from the IPIRG Program

  18. International Piping Integrity Research Group (IPIRG) Program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Wilkowski, G.; Schmidt, R.; Scott, P. [and others

    1997-06-01

    This is the final report of the International Piping Integrity Research Group (IPIRG) Program. The IPIRG Program was an international group program managed by the U.S. Nuclear Regulatory Commission and funded by a consortium of organizations from nine nations: Canada, France, Italy, Japan, Sweden, Switzerland, Taiwan, the United Kingdom, and the United States. The program objective was to develop data needed to verify engineering methods for assessing the integrity of circumferentially-cracked nuclear power plant piping. The primary focus was an experimental task that investigated the behavior of circumferentially flawed piping systems subjected to high-rate loadings typical of seismic events. To accomplish these objectives a pipe system fabricated as an expansion loop with over 30 meters of 16-inch diameter pipe and five long radius elbows was constructed. Five dynamic, cyclic, flawed piping experiments were conducted using this facility. This report: (1) provides background information on leak-before-break and flaw evaluation procedures for piping, (2) summarizes technical results of the program, (3) gives a relatively detailed assessment of the results from the pipe fracture experiments and complementary analyses, and (4) summarizes advances in the state-of-the-art of pipe fracture technology resulting from the IPIRG program.

  19. Review of current status of LWR safety research in Japan

    International Nuclear Information System (INIS)

    Yamada, Tasaburo; Mishima, Yoshitsugu; Ando, Yoshio; Miyazono, Shohachiro; Takashima, Yoichi.

    1977-01-01

    The Japan Atomic Energy Commission has exerted efforts on the research of the safety of nuclear plants in Japan, and ''Nuclear plant safety research committees'' was established in August 1974, which is composed of the government and the people. The philosophy of safety research, research and development plan, the forwarding procedure of the plan, international cooperation, for example LOFT program, and the effective feed back of the experimental results concerning nuclear safety are reviewed in this paper at first. As for the safety of nuclear reactors the basic philosophy that radio active fission products are contained in fuel or reactors with multiple barriers, (defence in depth) and almost no fission product is released outside reactor plants even at the time of hypothetical accident, is kept, and the research and development history and the future plan are described in this paper with the related technical problems. The structural safety is also explained, for example, on the philosophy ''leak before break'', pipe rupture, pipe restraint and stress analysis. The release of radioactive gas and liquid is decreased as the philosophy ''ALAP''. And probability safety evaluation method, LOCA, reactivity, accident and aseismatic design in nuclear plants in Japan are described. (Nakai, Y.)

  20. Procedure for preparation of dispersions

    International Nuclear Information System (INIS)

    1978-01-01

    Procedure for the preparation of a water based dispersion of cerium oxide, characterised in that a suspension of cerium (IV) hydroxide is formed with an acid, where the acid is in the state of a disaggregation of aggregated crystalline cerium hydroxide, the suspension being preheated for a specified time and to a specified temperature, so that the pH value becomes constant, and whereby the quantity of acid in the suspension is such that the constant pH value is lower than 5.4, so that a conditioned suspension may be obtained, and water may be mixed with the conditioned suspension for making a water based dispersion of cerium oxide. (G.C.)

  1. Geometric procedures for civil engineers

    CERN Document Server

    Tonias, Elias C

    2016-01-01

    This book provides a multitude of geometric constructions usually encountered in civil engineering and surveying practice.  A detailed geometric solution is provided to each construction as well as a step-by-step set of programming instructions for incorporation into a computing system. The volume is comprised of 12 chapters and appendices that may be grouped in three major parts: the first is intended for those who love geometry for its own sake and its evolution through the ages, in general, and, more specifically, with the introduction of the computer. The second section addresses geometric features used in the book and provides support procedures used by the constructions presented. The remaining chapters and the appendices contain the various constructions. The volume is ideal for engineering practitioners in civil and construction engineering and allied areas.

  2. Radiological Work Planning and Procedures

    CERN Document Server

    Kurtz, J E

    2000-01-01

    Each facility is tasked with maintaining personnel radiation exposure as low as reasonably achievable (ALARA). A continued effort is required to meet this goal by developing and implementing improvements to technical work documents (TWDs) and work performance. A review of selected TWDs from most facilities shows there is a need to incorporate more radiological control requirements into the TWD. The Radioactive Work Permit (RWP) provides a mechanism to place some of the requirements but does not provide all the information needed by the worker as he/she is accomplishing the steps of the TWD. Requiring the engineers, planners and procedure writers to put the radiological control requirements in the work steps would be very easy if all personnel had a strong background in radiological work planning and radiological controls. Unfortunately, many of these personnel do not have the background necessary to include these requirements without assistance by the Radiological Control organization at each facility. In add...

  3. Procedures for maintenance and repairs

    International Nuclear Information System (INIS)

    Pickel, E.

    1981-01-01

    After a general review of the operation experience in the history of more than 12 operating years, the organization in the plant will be shown with special aspect to quality assurance, capacity of the workshops and connected groups as radiation protection, chemical laboratories etc. The number, time intervals and manpower effort for the repeating tests will be discussed. Reasons and examples for back-fitting activities in the plant are given. Besides special repair and maintenance procedures as repair of the steam generators, in-service inspection of the reactor pressure vessel, repair of a feed-water pipe and repair of the core structure in the pressure vessel, the general system to handle maintenance and repair-work in the KWO-plant will be shown. This includes also the detailed planning of the annual refueling and revision of the plant. (orig./RW)

  4. Headache following intracranial neuroendovascular procedures.

    Science.gov (United States)

    Baron, Eric P; Moskowitz, Shaye I; Tepper, Stewart J; Gupta, Rishi; Novak, Eric; Hussain, Muhammad Shazam; Stillman, Mark J

    2012-05-01

    Predicting who will develop post-procedure headache (PPH) following intracranial endovascular procedures (IEPs) would be clinically useful and potentially could assist in reducing the excessive diagnostic testing so often obtained in these patients. Although limited safety data exist, the use of triptans or dihydroergotamine (DHE) often raise concern when used with pre/post-coiled aneurysms. We sought to determine risk factors for PPH following IEP, to evaluate the utility of diagnostic testing in patients with post-coil acute headache (HA), and to record whether triptans and DHE have been used safely in this clinical setting. We conducted a retrospective chart review of adult patients undergoing IEPs. Bivariate analyses were conducted to compare patients who did and did not develop PPH. We reviewed records pertaining to 372 patients, of whom 263 underwent intracranial coil embolizations, 21 acrylic glue embolizations, and 88 stent placements. PPH occurred in 72% of coil patients, 33% of glue patients, and 14% of stent patients. Significant risk factors for post-coil HA were female gender, any pre-coil HA history, smoking, and anxiety/depression. A pre-stent history of HA exceeding 1 year's duration, and smoking were risk factors for post-stent HA. A pre-glue history of HA exceeding 1 year was the only risk factor for post-glue HA. In the small subgroup available for study, treatment with triptans or DHE was not associated with adverse events in pre/post-coiled aneurysms. Diagnostic testing was low yield. Occurrence of PPH was common after IEPs and especially so with coiling and in women, smokers, and those with anxiety/depression, and was often of longer duration than allowed by current International Classification of Headache Disorders-II criteria. The yield of diagnostic testing was low, and in a small subgroup treatment with triptans or DHE did not cause adverse events in pre/post-coiled aneurysms. Prospective studies are needed to confirm these findings.

  5. Long terms results of Draf 3 procedure

    NARCIS (Netherlands)

    Georgalas, C.; Hansen, F.; Videler, W. J. M.; Fokkens, W. J.

    2011-01-01

    To assess the effectiveness and factors associated with restenosis after Draf type III (Endoscopic Modified Lothrop) frontal sinus drainage procedure. Retrospective analysis of prospectively collected data. A hundred and twenty two consecutive patients undergoing Draf III procedure for recalcitrant

  6. Procedure Integrated Development Environment (PRIDE), Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — NASA captures and distributes operational knowledge in the form of procedures. These procedures are created and accessed by a range of people performing many...

  7. Procedures For Microbial-Ecology Laboratory

    Science.gov (United States)

    Huff, Timothy L.

    1993-01-01

    Microbial Ecology Laboratory Procedures Manual provides concise and well-defined instructions on routine technical procedures to be followed in microbiological laboratory to ensure safety, analytical control, and validity of results.

  8. Typical NRC inspection procedures for model plant

    International Nuclear Information System (INIS)

    Blaylock, J.

    1984-01-01

    A summary of NRC inspection procedures for a model LEU fuel fabrication plant is presented. Procedures and methods for combining inventory data, seals, measurement techniques, and statistical analysis are emphasized

  9. TMACS Test Procedure TP011: Panalarm Interface

    International Nuclear Information System (INIS)

    Seghers, R.; Washburn, S.J.

    1994-01-01

    The TMACS Software Test Procedures translate the project's acceptance criteria into test steps. The TMACS Test Plan (WHC-SD-WM-TP-148) is fulfilled when all Test Cases are approved. This Test Procedure tests the TMACS Panalarm Interface functions

  10. XML Syntax for Clinical Laboratory Procedure Manuals

    OpenAIRE

    Saadawi, Gilan; Harrison, James H.

    2003-01-01

    We have developed a document type description (DTD) in Extensable Markup Language (XML)1 for clinical laboratory procedures. Our XML syntax can adequately structure a variety of procedure types across different laboratories and is compatible with current procedure standards. The combination of this format with an XML content management system and appropriate style sheets will allow efficient procedure maintenance, distributed access, customized display and effective searching across a large b...

  11. Procedural Attack! Procedural Generation for Populated Virtual Cities: A Survey

    Directory of Open Access Journals (Sweden)

    Werner Gaisbauer

    2017-06-01

    Full Text Available On the one hand, creating rich virtual worlds "by hand" like in the game Grand Theft Auto V is hugely expensive and limited to large studios. On the other hand, procedural content generation (PCG allows tiny teams to create huge worlds like Hello Games did with only four people (in the beginning for the recently released game No Man's Sky. Following in the footsteps of Hello Games, this paper tries to equip the reader with an overview about the state-of-the-art of how to build such a virtual world, i.e., a populated virtual city with buildings, streets, parks, vegetation, humans, and vehicles, using just PCG assets. Each PCG asset that is envisioned to bring the city to life is grouped and discussed in detail and the latest research trends in PCG are presented together with open questions. Using the above-mentioned PCG assets, instead of months, a city can be built in a mere couple of minutes by a user without much experience in designing 3D assets. The city can then be used for many applications like games, virtual reality (VR, or film.

  12. 40 CFR 791.30 - Hearing procedures.

    Science.gov (United States)

    2010-07-01

    ... officer may deem necessary to an understanding and determination of the dispute. The hearing officer shall... 40 Protection of Environment 31 2010-07-01 2010-07-01 true Hearing procedures. 791.30 Section 791... (CONTINUED) DATA REIMBURSEMENT Hearing Procedures § 791.30 Hearing procedures. (a) Representation by counsel...

  13. 49 CFR 195.214 - Welding procedures.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Welding procedures. 195.214 Section 195.214... PIPELINE Construction § 195.214 Welding procedures. (a) Welding must be performed by a qualified welder in accordance with welding procedures qualified under Section 5 of API 1104 or Section IX of the ASME Boiler and...

  14. 46 CFR 154.665 - Welding procedures.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 5 2010-10-01 2010-10-01 false Welding procedures. 154.665 Section 154.665 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) CERTAIN BULK DANGEROUS CARGOES SAFETY STANDARDS... Construction § 154.665 Welding procedures. Welding procedure tests for cargo tanks for a design temperature...

  15. 49 CFR 192.225 - Welding procedures.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Welding procedures. 192.225 Section 192.225... BY PIPELINE: MINIMUM FEDERAL SAFETY STANDARDS Welding of Steel in Pipelines § 192.225 Welding procedures. (a) Welding must be performed by a qualified welder in accordance with welding procedures...

  16. 40 CFR 1065.10 - Other procedures.

    Science.gov (United States)

    2010-07-01

    ... importance of pursuing changes to the procedures: (i) Whether supplemental emission standards or other... procedures, such as those of the California Air Resources Board or the International Organization for... 40 Protection of Environment 32 2010-07-01 2010-07-01 false Other procedures. 1065.10 Section 1065...

  17. TMACS Test Procedure TP009: Acromag Driver

    International Nuclear Information System (INIS)

    Washburn, S.J.

    1994-01-01

    The TMACS Software Project Test Procedures translate the project's acceptance criteria into test steps. Software releases are certified when the affected Test Procedures are successfully performed and the customers authorize installation of these changes. This Test Procedure tests the TMACS Acromag Software Driver (Bridge Code)

  18. Environmental Measurements Laboratory (EML) procedures manual

    International Nuclear Information System (INIS)

    Chieco, N.A.; Bogen, D.C.; Knutson, E.O.

    1990-11-01

    Volume 1 of this manual documents the procedures and existing technology that are currently used by the Environmental Measurements Laboratory. A section devoted to quality assurance has been included. These procedures have been updated and revised and new procedures have been added. They include: sampling; radiation measurements; analytical chemistry; radionuclide data; special facilities; and specifications. 228 refs., 62 figs., 37 tabs. (FL)

  19. 39 CFR 5.2 - Committee procedure.

    Science.gov (United States)

    2010-07-01

    ... 39 Postal Service 1 2010-07-01 2010-07-01 false Committee procedure. 5.2 Section 5.2 Postal Service UNITED STATES POSTAL SERVICE THE BOARD OF GOVERNORS OF THE U.S. POSTAL SERVICE COMMITTEES (ARTICLE V) § 5.2 Committee procedure. Each committee establishes its own rules of procedure, consistent with...

  20. WSSDA's Guide to Parliamentary Procedures. Revised

    Science.gov (United States)

    Randolph, Mary

    2004-01-01

    This guide to parliamentary procedures is presented by the Washington State School Directors' Association (WSSDA) for use by local school boards within the State of Washington. Parliamentary law and parliamentary procedure is the key to order and to provide justice and fairness to all. Through both formal and informal parliamentary procedures,…

  1. Intake Procedures in College Counseling Centers.

    Science.gov (United States)

    Pappas, James P.; And Others

    Intake procedures is the common subject of four papers presented in this booklet. James P. Pappas discusses trends, a decision theory model, information and issues in his article "Intake Procedures in Counseling Centers--Trends and Theory." In the second article "The Utilization of Standardized Tests in Intake Procedures or 'Where's the Post…

  2. Objective Truth Institution in Criminal Procedure

    Directory of Open Access Journals (Sweden)

    Voltornist O. A.

    2012-11-01

    Full Text Available The article deals with the category of objective truth in criminal procedure, its importance for correct determination of criminal court procedure aims. The author analyzes also the bill draft offered by the RF Committee of Inquiry “On amending in the RF Criminal Procedure Code due to the implementation ofobjective truth institution in criminal procedure”

  3. TMACS Test Procedure TP007: System administration

    International Nuclear Information System (INIS)

    Scanlan, P.; Washburn, S.; Seghers, R.

    1994-01-01

    The TMACS Software Project Test Procedures translate the project's acceptance criteria into test steps. Software releases are certified when the affected Test Procedures are successfully performed and the customers authorize installation of these changes. This Test Procedure tests the TMACS System Administration functions

  4. MITS Feed and Withdrawal Subsystem: operating procedures

    International Nuclear Information System (INIS)

    Brown, W.S.

    1980-01-01

    This document details procedures for the operation of the MITS (Machine Interface Test System) Feed and Withdrawal Subsystem (F and W). Included are fill with UF 6 , establishment of recycle and thruput flows, shutdown, UF 6 makeup, dump to supply container, Cascade dump to F and W, and lights cold trap dump, all normal procedures, plus an alternate procedure for trapping light gases

  5. 32 CFR 635.35 - Procedures.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 4 2010-07-01 2010-07-01 true Procedures. 635.35 Section 635.35 National Defense Department of Defense (Continued) DEPARTMENT OF THE ARMY (CONTINUED) LAW ENFORCEMENT AND CRIMINAL INVESTIGATIONS LAW ENFORCEMENT REPORTING Victim and Witness Assistance Procedures § 635.35 Procedures. (a) As required by Federal law, Army personnel...

  6. 21 CFR 211.150 - Distribution procedures.

    Science.gov (United States)

    2010-04-01

    ...: GENERAL CURRENT GOOD MANUFACTURING PRACTICE FOR FINISHED PHARMACEUTICALS Holding and Distribution § 211.150 Distribution procedures. Written procedures shall be established, and followed, describing the... 21 Food and Drugs 4 2010-04-01 2010-04-01 false Distribution procedures. 211.150 Section 211.150...

  7. 40 CFR 205.54 - Test procedures.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Test procedures. 205.54 Section 205.54 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) NOISE ABATEMENT PROGRAMS TRANSPORTATION EQUIPMENT NOISE EMISSION CONTROLS Medium and Heavy Trucks § 205.54 Test procedures. The procedures described...

  8. TMACS Test Procedure TP002: Trending

    International Nuclear Information System (INIS)

    Scanlan, P.K.

    1994-01-01

    The TMACS Software Project Test Procedures translate the project's acceptance criteria into test steps. Software releases are certified when the affected Test Procedures are successfully performed and the customers authorize installation of these changes. This Test Procedure tests the TMACS Trending functions

  9. 28 CFR 79.73 - Appeals procedures.

    Science.gov (United States)

    2010-07-01

    ... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Appeals procedures. 79.73 Section 79.73 Judicial Administration DEPARTMENT OF JUSTICE (CONTINUED) CLAIMS UNDER THE RADIATION EXPOSURE COMPENSATION ACT Procedures § 79.73 Appeals procedures. (a) An appeal must be in writing and must be received by...

  10. Modified Arthroscopic Brostrom Procedure With Bone Tunnels.

    Science.gov (United States)

    Lui, Tun Hing

    2016-08-01

    The open anatomic repair of the anterior talofibular and calcaneofibular ligaments (modified Brostrom procedure) is widely accepted as the standard surgical stabilization procedure for lateral ankle instability that does not respond to conservative measures. Arthroscopic Brostrom procedures with a suture anchor have been reported to achieve both anatomic repair of the lateral ankle ligaments and management of the associated intra-articular lesions. However, the complication rates are higher than open Brostom procedures. Many of these complications are associated with the use of a suture anchor. We report a modified arthroscopic Brostrom procedure in which the anterolateral ankle capsule is anchored to the lateral malleolus through small bone tunnels instead of suture anchors.

  11. Photogrammetry procedures applied to anthropometry.

    Science.gov (United States)

    Okimoto, Maria Lúcialeite Ribeiro; Klein, Alison Alfred

    2012-01-01

    This study aims to evaluate the reliability and establish procedures for the use of digital photogrammetry in anthropometric measurements of the human hand. The methodology included the construction of a platform to allow the placement of the hand always equivalent to a distance of the camera lens and to annul the effects of parallax. We developed a software to perform the measurements from the images and built up a subject of proof in a cast from a negative mold, this object was subjected to measurements with digital photogrammetry using the data collection platform in caliper and the Coordinate Measuring Machine (MMC). The results of the application of photogrammetry in the data collection segment hand, allow us to conclude that photogrammetry is an effective presenting precision coefficient below 0.940. Within normal and acceptable values, given the magnitude of the data used in anthropometry. It was concluded photogrammetry then be reliable, accurate and efficient for carrying out anthropometric surveys of population, and presents less difficulty to collect in-place.

  12. Training review criteria and procedures

    International Nuclear Information System (INIS)

    1986-07-01

    The industry, through commitment to the INPO-managed Training Accreditation Program, is implementing what is referred to as performance-based training, or the Systems Approach to Training (SAT). The NRC considers the following five elements as essential to these training programs: Systematic analysis of the jobs to be performed; learning objectives that are derived from the analysis and that describe desired performance after training; Training design and implementation based on the learning objectives; Evaluation of trainee mastery of the objectives during training; and evaluation and revision of the training based on the performance of trained personnel in the job setting. As indicated in the ''Commission Policy Statement on Training and Qualifications of Nuclear Power Plant Personnel'' of March 20, 1985,''the NRC will continue to closely monitor the process [INPO Accreditation] and its results, and ''It remains the continuing responsibility of the NRC to independently evaluate applicants' and licensees' implementation of improvement programs....'' These procedures provide a systematic means for implementing two of the NRC monitoring functions identified in the Commission Policy Statement: ''Continuing evaluation of industry training and qualification program effectiveness,''; and ''Monitoring plant and industry trends and events involving personnel errors.''

  13. Radiological Work Planning and Procedures

    International Nuclear Information System (INIS)

    KURTZ, J.E.

    2000-01-01

    Each facility is tasked with maintaining personnel radiation exposure as low as reasonably achievable (ALARA). A continued effort is required to meet this goal by developing and implementing improvements to technical work documents (TWDs) and work performance. A review of selected TWDs from most facilities shows there is a need to incorporate more radiological control requirements into the TWD. The Radioactive Work Permit (RWP) provides a mechanism to place some of the requirements but does not provide all the information needed by the worker as he/she is accomplishing the steps of the TWD. Requiring the engineers, planners and procedure writers to put the radiological control requirements in the work steps would be very easy if all personnel had a strong background in radiological work planning and radiological controls. Unfortunately, many of these personnel do not have the background necessary to include these requirements without assistance by the Radiological Control organization at each facility. In addition, there seems to be confusion as to what should be and what should not be included in the TWD

  14. Imaging of cartilage repair procedures

    International Nuclear Information System (INIS)

    Sanghvi, Darshana; Munshi, Mihir; Pardiwala, Dinshaw

    2014-01-01

    The rationale for cartilage repair is to prevent precocious osteoarthritis in untreated focal cartilage injuries in the young and middle-aged population. The gamut of surgical techniques, normal postoperative radiological appearances, and possible complications have been described. An objective method of recording the quality of repair tissue is with the magnetic resonance observation of cartilage repair tissue (MOCART) score. This scoring system evaluates nine parameters that include the extent of defect filling, border zone integration, signal intensity, quality of structure and surface, subchondral bone, subchondral lamina, and records presence or absence of synovitis and adhesions. The five common techniques of cartilage repair currently offered include bone marrow stimulation (microfracture or drilling), mosaicplasty, synthetic resorbable scaffold grafts, osteochondral allograft transplants, and autologous chondrocyte implantation (ACI). Complications of cartilage repair procedures that may be demonstrated on magnetic resonance imaging (MRI) include plug loosening, graft protuberance, graft depression, and collapse in mosaicplasty, graft hypertrophy in ACI, and immune response leading to graft rejection, which is more common with synthetic grafts and cadaveric allografts

  15. Remote handling procedures in JET

    International Nuclear Information System (INIS)

    Raimondi, T.; Huguet, M.

    1976-01-01

    Remote maintenance will be needed in the second phase of operation due to the structural activation produced by deuterium-tritium discharges. Priority will be given to tasks which require frequent intervention, but efforts will be made also to tackle larger operations such as replacement of an octant. Owing to the variety and unpredictability of the operations which may be required, general purpose telemanipulator and TV systems will be used, mounted on versatile articulated supports capable of reaching the various parts of the machine. An experimental programme is planned to test the envisaged equipment and develop procedures for carrying out the various tasks as they are more clearly identified. Design of peripheral equipment for easy accessibility, choice of simple connection methods, development of auxiliary tools, as well as careful programming of the operations, will be essential for successful remote maintenance. The effort put into these areas will, however, also result in considerable time saving during the assembly and maintenance in non-active conditions. Preliminary feasibility tests of some difficult operations have already been done with a force-reflecting servo-manipulator and two TV sets for front and side viewing. Leak identification and precision welding for vacuum tightness were demonstrated

  16. Probabilistic safety analysis procedures guide

    International Nuclear Information System (INIS)

    Papazoglou, I.A.; Bari, R.A.; Buslik, A.J.

    1984-01-01

    A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of tissues affecting reactor safety. This guide addresses the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant and from loss of offsite electric power. The scope includes analyses of problem-solving (cognitive) human errors, a determination of importance of the various core damage accident sequences, and an explicit treatment and display of uncertainties for the key accident sequences. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance) and the risk associated with external accident initiators, as consensus is developed regarding suitable methodologies in these areas. This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are essential for regulatory decision making. Methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study

  17. Crisis management and warning procedures

    Directory of Open Access Journals (Sweden)

    Valérie November

    2009-03-01

    territoriale du risque s’avère nécessaire.Based on two flood events that recently affected new housing areas in very different political, organisational and hydrological contexts, this article examines the practices of actors involved in emergency and crisis situations in Switzerland. In both cases, the actors are identified – through their role and their position in the various procedures related to crisis management – and an inventory is made of the documents used. The study examines how the flood events were managed, identifies the organisational changes that followed the crises, and determines how the risk was conceived and to what extent it was formalised by the different actors both before and after the floods. Finally new forecasting and warning procedures that were set up following the events are described. The study shows that floods have a decisive impact on the production of knowledge, but that this phenomenon varies according to the actors. Events such as floods also sometimes reveal the existence of "latent" knowledge, or knowledge that is available but has not yet been integrated into institutional procedures. In terms of both forecasting and crisis management, these events also provide the opportunity to test information channels and to identify and correct any problems relating to organisation, cooperation or the reliability of means of communication. Among other things, the risks and crises related to flooding modify the dynamics and policies of the local area as a result of readjustments in the networks of actors. The introduction of emergency and crisis management measures appears more effective, however, than the reorganisation of planning and development procedures, a process which generally takes a lot longer. Nevertheless, since the recollection of events tends to fade with time, it is important that risks find a more concrete form of spatial expression on the landscape.

  18. DACS upgrade acceptance test procedure

    International Nuclear Information System (INIS)

    Zuehlke, A.C.

    1994-01-01

    The readiness of the Data Acquisition and Control System (DACS) to provide monitoring and control of the mixer pump, directional drive system, and the instrumentation associated with the SY-101 tank and support systems, and the proper functioning of the DACS with new Model 984-785 Programmable Logic Controllers (PLCs), new MODBUS PLUS version 2.01 software for the PLCs, and version 3.72 of the GENESIS software will be systematically evaluated by performance of this procedure. The DACS, which is housed in a trailer located just outside of the north fence at the SY tank farm, receives input signals from a variety of sensors located in and around the SY-101 tanks. These sensors provide information such as: tank vapor space and ventilation system H 2 concentration; tank waste temperature; tank pressure; waste density; operating pump parameters such as speed, flow, rotational position, discharge pressure, and internal temperature; strain (for major equipment); and waste level. The output of these sensors is conditioned and transmitted to the DACS computers where these signals are displayed, recorded, and monitored for out-of-specification conditions. If abnormal conditions are detected, then, in certain situations, the DACS automatically generates alarms and causes the system to abort pump operations

  19. Developing, adopting and adapting operating procedures

    International Nuclear Information System (INIS)

    Rabouhams, J.

    1986-01-01

    This lecture specifies all the dispositions which have been taken by EDF Nuclear and Fossil Generation Department - according to the fact that availability and safety largely depend on the quality of the procedures and their easy handling - in order to develop, adopt and adapt the operating procedures. The following points are treated: General organization of procedures for plant operation during normal and abnormal conditions; Personnel and extend of responsibility involved into the development of procedures (research center, training center, specialized services, nuclear station, etc.); Validation of the procedures by means of full-scope simulators; Modifications of the procedures taking into account operation experience in material and human fields; Development of simulation softs in order to perform the procedures in abnormal situations; Evolution of operating technics and future skills. (orig.)

  20. Surgeon-patient communication during awake procedures.

    Science.gov (United States)

    Smith, Claire S; Guyton, Kristina; Pariser, Joseph J; Siegler, Mark; Schindler, Nancy; Langerman, Alexander

    2017-06-01

    Surgeons are increasingly performing procedures on awake patients. Communication during such procedures is complex and underexplored in the literature. Surgeons were recruited from the faculty of 2 hospitals to participate in an interview regarding their approaches to communication during awake procedures. Three researchers used the constant comparative method to transcribe, code, and review interviews until saturation was reached. Twenty-three surgeons described the advantages and disadvantages of awake procedures, their communication with the awake patient, their interactions with staff and with trainees, the environment of awake procedures, and how communication in this context is taught and learned. Surgeons recognized communication during awake procedures as important and reported varied strategies for ensuring patient comfort in this context. However, they also acknowledged challenges with multiparty communication during awake procedures, especially in balancing commitments to teaching with their duty to comfort the patient. Copyright © 2016 Elsevier Inc. All rights reserved.

  1. Human Reliability Analysis For Computerized Procedures

    International Nuclear Information System (INIS)

    Boring, Ronald L.; Gertman, David I.; Le Blanc, Katya

    2011-01-01

    This paper provides a characterization of human reliability analysis (HRA) issues for computerized procedures in nuclear power plant control rooms. It is beyond the scope of this paper to propose a new HRA approach or to recommend specific methods or refinements to those methods. Rather, this paper provides a review of HRA as applied to traditional paper-based procedures, followed by a discussion of what specific factors should additionally be considered in HRAs for computerized procedures. Performance shaping factors and failure modes unique to computerized procedures are highlighted. Since there is no definitive guide to HRA for paper-based procedures, this paper also serves to clarify the existing guidance on paper-based procedures before delving into the unique aspects of computerized procedures.

  2. Multiple position borehole extensometer procedure: Final draft

    International Nuclear Information System (INIS)

    1986-08-01

    The purpose of the Multiple Position Borehole Extensometer Procedure is to provide detailed information for MPBXs installed at the salt Deaf Smith County ESF. This procedure includes design of equipment, installation, instructions, instrument locations, measurement requirements, support requirements, quality assurance procedures, and data acquisition requirements. Data reduction procedures are also discussed; however, the relevance of the data is discussed elsewhere in the appropriate test plans. Sufficient detail is provided in this procedure to allow for integrating the requirements of this procedure into both the facility construction and overall underground testing programs; identifying necessary equipment for procurement; determining data acquisition requirements as input to Automatic Data Acquisition System (ADAS) design; providing step-by-step procedures for training personnel as well as for directing field operations; establishing quality assurance (QA) checkpoints and implementation methods; and defining data reduction methods and providing the anticipated accuracy of the system. 11 refs., 14 figs

  3. Writer`s guide for technical procedures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

    A primary objective of operations conducted in the US Department of Energy (DOE) complex is safety. Procedures are a critical element of maintaining a safety envelope to ensure safe facility operation. This DOE Writer`s Guide for Technical Procedures addresses the content, format, and style of technical procedures that prescribe production, operation of equipment and facilities, and maintenance activities. The DOE Writer`s Guide for Management Control Procedures and DOE Writer`s Guide for Emergency and Alarm Response Procedures are being developed to assist writers in developing nontechnical procedures. DOE is providing this guide to assist writers across the DOE complex in producing accurate, complete, and usable procedures that promote safe and efficient operations that comply with DOE orders, including DOE Order 5480.19, Conduct of Operations for DOE Facilities, and 5480.6, Safety of Department of Energy-Owned Nuclear Reactors.

  4. INITIATION AND CONDUCT OF ADMINISTRATIVE PROCEDURE

    Directory of Open Access Journals (Sweden)

    Milan Stipic

    2013-12-01

    Full Text Available General administrative procedure act contains legal norms that are valid for all identical cases. In addition to the general, there are special administrative procedures, customized to the specific administrative areas. Procedure initiation is regulated. Administrative procedure can be initiated at the request of the proponent and ex officio. When the official determines that the conditions for the conduct of administrative procedure are met, before making a decision, all the facts and circumstances relevant to the resolution of administrative matter have to be identified. When there are no legal requirements for the initiation of procedures, the official shall make a decision to reject the application of the party. The procedure is initiated ex officio when stipulated by law or when protection of public interest requires it. When initiating procedure ex officio, the public authority shall take into consideration the petition or other information that indicate the need to protect the public interest. In such cases the applicant is not a party, and the official is obliged to notify the applicant, if initiation of procedures is not accepted ex officio. Based on the notification, the applicant has a right to complain, including the situation when there is no response within the prescribed period of 30 days. Public authority may, therefore it is not obliged to, initiate administrative procedure by public announcement only in a situation where the parties are unknown, while it is obliged to initiate procedure by public announcement when this method of initiating the procedure is prescribed by law. Initiation of procedure with public announcement occurs in rare cases. Due to the application of efficiency and cost-effectiveness principle, two or more administrative procedures can be merged into one procedure by a conclusion. The condition for this is that the rights or obligations of the parties are based on the same legal basis and on the same or

  5. A procedure for safety assessment of components with cracks - Handbook. 3rd revised edition

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, P.; Bergman, M.; Brickstad, B.; Dahlberg, L.; Nilsson, F.; Sattari-Far, I. [SAQ Kontroll AB, Stockholm (Sweden)

    1999-12-01

    In this handbook a procedure is described which can be used both for assessment of detected cracks or crack-like defects and for defect tolerance analysis. The procedure can be used to calculate possible crack growth due to fatigue or stress corrosion and to calculate the reserve margin for failure due to fracture and plastic collapse. For ductile materials, the procedure gives the reserve margin for initiation of stable crack growth. Thus, an extra reserve margin, unknown to size, exists for failure in components made of ductile materials. The procedure was developed for operative use with the following objectives in mind: a) The procedure should be able to handle both linear and non-linear problems without any a priori division. b) The procedure shall ensure uniqueness of the safety assessment. c) The procedure should be well defined and easy to use. d) The conservatism of the procedure should be well validated. e) The handbook, that documents the procedure, should be so complete that for most assessments, access to any other fracture mechanics literature should not be necessary. The method utilized in the procedure is based on the R6-method developed at Nuclear Electric plc. The basic assumption is that fracture initiated by a crack can be described by the variables K{sub r} and L{sub r}. K{sub r} is the ratio between the stress intensity factor and the fracture toughness of the material. L{sub r} is the ratio between applied load and the plastic limit load of the structure. The pair of calculated values of these variables is plotted in a diagram. If the point is situated within the noncritical region, fracture is assumed not to occur. If the point is situated outside the region, crack growth and fracture may occur. The method can in principal be used for all metallic materials. It is, however, more extensively verified for steel alloys only. The method is not intended for use in temperature regions where creep deformation is of importance. To fulfil the above

  6. A procedure for safety assessment of components with cracks - Handbook. 3rd revised edition

    International Nuclear Information System (INIS)

    Andersson, P.; Bergman, M.; Brickstad, B.; Dahlberg, L.; Nilsson, F.; Sattari-Far, I.

    1999-12-01

    In this handbook a procedure is described which can be used both for assessment of detected cracks or crack-like defects and for defect tolerance analysis. The procedure can be used to calculate possible crack growth due to fatigue or stress corrosion and to calculate the reserve margin for failure due to fracture and plastic collapse. For ductile materials, the procedure gives the reserve margin for initiation of stable crack growth. Thus, an extra reserve margin, unknown to size, exists for failure in components made of ductile materials. The procedure was developed for operative use with the following objectives in mind: a) The procedure should be able to handle both linear and non-linear problems without any a priori division. b) The procedure shall ensure uniqueness of the safety assessment. c) The procedure should be well defined and easy to use. d) The conservatism of the procedure should be well validated. e) The handbook, that documents the procedure, should be so complete that for most assessments, access to any other fracture mechanics literature should not be necessary. The method utilized in the procedure is based on the R6-method developed at Nuclear Electric plc. The basic assumption is that fracture initiated by a crack can be described by the variables K r and L r . K r is the ratio between the stress intensity factor and the fracture toughness of the material. L r is the ratio between applied load and the plastic limit load of the structure. The pair of calculated values of these variables is plotted in a diagram. If the point is situated within the noncritical region, fracture is assumed not to occur. If the point is situated outside the region, crack growth and fracture may occur. The method can in principal be used for all metallic materials. It is, however, more extensively verified for steel alloys only. The method is not intended for use in temperature regions where creep deformation is of importance. To fulfil the above given objectives

  7. The mediation procedure in Romania

    Directory of Open Access Journals (Sweden)

    Alexandrina Zaharia

    2009-06-01

    Full Text Available The mediation activity as an alternative way of solving conflicts occupies an important place in modernsociety. Currently, the mediation reached its maturity worldwide being adopted without reservations.The future of solving conflicts is undoubtedly closely related to mediation. XXth century is the century of solvingconflicts amiably outside the court room. In Romania and the mediation profession were regulated by the Law no.192/2006, on the basis of the idea that mediation is one of the major themes of the reform strategy of the judicialsystem 2005-2007. By adopting the mentioned law it was followed the idea of reducing the volume of activitycourts, and therefore, relieve them of as many cases, with the direct effect on the quality of justice. Mediation is avoluntary process in which the parties with a neutral and impartial third party, without power of decision - themediator - who is qualified to assist the parties to negotiate, facilitating the communication between them andhelping them to reach a unanimous effective and sustainable agreement. The parties may resort to mediation beforeor after triggering a trial. Mediation can be applied, in principle, on any type of conflict. However, theRomanian legislator has established special stipulations on conflict mediation in criminal, civil and familylaw. Although not expressly provided, the stipulations regarding the civil conflicts and also apply to commercialconflicts. Therefore, the mediation is applicable to most types of lawsuits, except those relating to personalrights. As a "win- win" principle, the mediation does not convert any of the parties defeated or victorious; allthose involved have gained by applying this procedure.

  8. Vaginal hysterectomy, an outpatient procedure.

    Science.gov (United States)

    Engh, Marie Ellström; Hauso, Wenche

    2012-11-01

    To report our experience of treating women undergoing vaginal hysterectomy in an outpatient setting and to identify risk factors for hospital admission and women dissatisfied with care. Prospective observational report. department of obstetrics and gynecology, university hospital in Norway. 150 women who underwent vaginal hysterectomy at the outpatient clinic from February 2009 to April 2010. Perioperative data were collected prospectively and case notes were searched for complications. On the first postoperative day all women were contacted by telephone by a nurse. A visual analogue scale (VAS) was used to monitor pain and nausea during the stay at the outpatient clinic and the day after surgery. VAS was also used to specify the women's degree of satisfaction with care the day after surgery. The number of women who could be discharged from the outpatient unit and had a satisfaction score of ≥7 the day after surgery. Of the 150 women, 84% could be discharged after a mean observation period of 276 min (SD ± 80 min). The mean satisfaction score was 9.0, SD ± 1.4, and 92.6% of the women reported ≥7 points in the satisfaction score. No women with serious complications were sent home. Using a multivariable logistic regression model only pain at discharge was found as significant (p= 0.009) for admittance to hospital. Vaginal hysterectomy is a feasible outpatient procedure and the majority of women were satisfied with the care they received. © 2012 The Authors Acta Obstetricia et Gynecologica Scandinavica© 2012 Nordic Federation of Societies of Obstetrics and Gynecology.

  9. PC based temporary shielding administrative procedure (TSAP)

    International Nuclear Information System (INIS)

    Olsen, D.E.; Pederson, G.E.; Hamby, P.N.

    1995-01-01

    A completely new Administrative Procedure for temporary shielding was developed for use at Commonwealth Edison's six nuclear stations. This procedure promotes the use of shielding, and addresses industry requirements for the use and control of temporary shielding. The importance of an effective procedure has increased since more temporary shielding is being used as ALARA goals become more ambitious. To help implement the administrative procedure, a personal computer software program was written to incorporate the procedural requirements. This software incorporates the useability of a Windows graphical user interface with extensive help and database features. This combination of a comprehensive administrative procedure and user friendly software promotes the effective use and management of temporary shielding while ensuring that industry requirements are met

  10. PC based temporary shielding administrative procedure (TSAP)

    Energy Technology Data Exchange (ETDEWEB)

    Olsen, D.E.; Pederson, G.E. [Sargent & Lundy, Chicago, IL (United States); Hamby, P.N. [Commonwealth Edison Co., Downers Grove, IL (United States)

    1995-03-01

    A completely new Administrative Procedure for temporary shielding was developed for use at Commonwealth Edison`s six nuclear stations. This procedure promotes the use of shielding, and addresses industry requirements for the use and control of temporary shielding. The importance of an effective procedure has increased since more temporary shielding is being used as ALARA goals become more ambitious. To help implement the administrative procedure, a personal computer software program was written to incorporate the procedural requirements. This software incorporates the useability of a Windows graphical user interface with extensive help and database features. This combination of a comprehensive administrative procedure and user friendly software promotes the effective use and management of temporary shielding while ensuring that industry requirements are met.

  11. Civil rights reference of administrative procedures

    International Nuclear Information System (INIS)

    Held, J.

    1984-01-01

    The book deals with the constitutional obligations which substantive civil rights demand from administrative procedures. The Federal Constitutional Court distinguishes between protection of civil rights in, and by, administrative and judicial procedures. The author analyses the example of the decision of the Federal Constitutional Court concerning the atomic power plant of Muelheim-Kaerlich. In the licensing procedure pursuant to the Atomic Energy Act, the civil rights of persons concerned are guaranteed by the governmental obligation to its protection. (CW) [de

  12. Procedures minimally invasive image-guided

    International Nuclear Information System (INIS)

    Mora Guevara, Alejandro

    2011-01-01

    A literature review focused on minimally invasive procedures, has been performed at the Department of Radiology at the Hospital Calderon Guardia. A multidisciplinary team has been raised for decision making. The materials, possible complications and the available imaging technique such as ultrasound, computed tomography, magnetic resonance imaging, have been determined according to the procedure to be performed. The revision has supported medical interventions didactically enjoying the best materials, resources and conditions for a successful implementation of procedures and results [es

  13. Can proceduralization support coping with the unexpected?

    Energy Technology Data Exchange (ETDEWEB)

    Norros, Leena; Savioja, Paula; Liinasuo, Marja; Wahlstrom, Mikael [VTT Technical Research Centre of Finland, Vuorimiehentie (Finland)

    2014-08-15

    Operations of safety critical industries unquestionably require a diversity of technical and organizational control measures to increase stability and predictability of the complex sociotechnical systems. Nevertheless, experiences from recent severe accidents and results of safety research have questioned the effectiveness of the prevailing safety management strategy that mainly relies on standardization and designed-in defenses. This paper discusses the identified need to balance between stability and flexibility in a concrete safety issue, i.e., proceduralization. The main research problem of our study is whether procedure guided practice can offer sufficient support for flexibility of operating activity. We shall frame our study with the help of a model that explains different aspects of procedures. We then elaborate how these different aspects were considered empirically in our 3-phase study. In the first study we interviewed 62 main control room operators and asked how they consider procedures to support balancing. In the second study we observed in detail 12 NPP operator crews' activity in a simulated loss-of-coolant accident. In a third study we inquired 5 procedure designers about their conceptions concerning procedure guidance in operator work. Drawing on either interview or behavioral data we analyzed the personnel's stance to the flexibility and stability balancing, and how the conceptions portray in the practices of procedure usage. Our results demonstrate that the operators are aware of the need for balancing flexibility and stability and consider successful balancing to represent 'good' professional action. In actual action many operators, however, tend towards more straightforward following of procedures. Designers also see the capability for balancing stability and flexibility as a key operator competence but describe actual acting simply as procedure-following. According to the documents of the nuclear community, procedure

  14. Unexpected effects of computer presented procedures

    International Nuclear Information System (INIS)

    Blackman, H.S.; Nelson, W.R.

    1988-01-01

    Results from experiments conducted at the Idaho National Engineering Laboratory have been presented regarding the computer presentation of procedural information. The results come from the experimental evaluation of an expert system which presented procedural instructions to be performed by a nuclear power plant operator. Lessons learned and implications from the study are discussed as well as design issues that should be considered to avoid some of the pitfalls in computer presented or selected procedures

  15. Can proceduralization support coping with the unexpected?

    International Nuclear Information System (INIS)

    Norros, Leena; Savioja, Paula; Liinasuo, Marja; Wahlstrom, Mikael

    2014-01-01

    Operations of safety critical industries unquestionably require a diversity of technical and organizational control measures to increase stability and predictability of the complex sociotechnical systems. Nevertheless, experiences from recent severe accidents and results of safety research have questioned the effectiveness of the prevailing safety management strategy that mainly relies on standardization and designed-in defenses. This paper discusses the identified need to balance between stability and flexibility in a concrete safety issue, i.e., proceduralization. The main research problem of our study is whether procedure guided practice can offer sufficient support for flexibility of operating activity. We shall frame our study with the help of a model that explains different aspects of procedures. We then elaborate how these different aspects were considered empirically in our 3-phase study. In the first study we interviewed 62 main control room operators and asked how they consider procedures to support balancing. In the second study we observed in detail 12 NPP operator crews' activity in a simulated loss-of-coolant accident. In a third study we inquired 5 procedure designers about their conceptions concerning procedure guidance in operator work. Drawing on either interview or behavioral data we analyzed the personnel's stance to the flexibility and stability balancing, and how the conceptions portray in the practices of procedure usage. Our results demonstrate that the operators are aware of the need for balancing flexibility and stability and consider successful balancing to represent 'good' professional action. In actual action many operators, however, tend towards more straightforward following of procedures. Designers also see the capability for balancing stability and flexibility as a key operator competence but describe actual acting simply as procedure-following. According to the documents of the nuclear community, procedure

  16. Payment Procedures for Electronic Government Services

    OpenAIRE

    Pousttchi, Key; Wiedemann, Dietmar Georg

    2005-01-01

    In this paper, we analyse payment procedures for their suitability for electronic government. We provide an overview of the payment procedures currently available on the market, compare the situation in electronic government with the situation in electronic commerce and analyze what we can transfer. Based on functional requirements we propose a scheme that allows public agencies to examine the appropriateness of any given payment procedure for electronic government.

  17. Nuclear Waste Fund cash management procedures

    International Nuclear Information System (INIS)

    1988-04-01

    The Nuclear Waste Policy Act if 1982 (NWPA) provided for the Office of Radioactive Waste Management (OCRWM) to adopt financial and accounting methods comparable to those used by private industry, including borrowing and investing authority. This document describes the procedures OCRWM follows to meet its borrowing and investing authority under the NWPA. These procedures are a supplement to, and are, therefore, not intended to supersede, existing Departmental policies and procedures

  18. Unexpected effects of computer presented procedures

    International Nuclear Information System (INIS)

    Blackman, H.S.; Nelson, W.R.

    1988-01-01

    Results from experiments conducted at the Idaho National Engineering Laboratory will be presented regarding the computer presentation of procedural information. The results come from the experimental evaluation of an expert system which presented procedural instructions to be performed by a nuclear power plant operator. Lessons learned and implications from the study will be discussed as well as design issues that should be considered to avoid some of the pitfalls in computer presented or selected procedures. 1 ref., 1 fig

  19. Robotic vascular resections during Whipple procedure.

    Science.gov (United States)

    Allan, Bassan J; Novak, Stephanie M; Hogg, Melissa E; Zeh, Herbert J

    2018-01-01

    Indications for resection of pancreatic cancers have evolved to include selected patients with involvement of peri-pancreatic vascular structures. Open Whipple procedures have been the standard approach for patients requiring reconstruction of the portal vein (PV) or superior mesenteric vein (SMV). Recently, high-volume centers are performing minimally invasive Whipple procedures with portovenous resections. Our institution has performed seventy robotic Whipple procedures with concomitant vascular resections. This report outlines our technique.

  20. Robotic vascular resections during Whipple procedure

    OpenAIRE

    Allan, Bassan J.; Novak, Stephanie M.; Hogg, Melissa E.; Zeh, Herbert J.

    2018-01-01

    Indications for resection of pancreatic cancers have evolved to include selected patients with involvement of peri-pancreatic vascular structures. Open Whipple procedures have been the standard approach for patients requiring reconstruction of the portal vein (PV) or superior mesenteric vein (SMV). Recently, high-volume centers are performing minimally invasive Whipple procedures with portovenous resections. Our institution has performed seventy robotic Whipple procedures with concomitant vas...

  1. Conception, definition, measuring procedure of grain size

    International Nuclear Information System (INIS)

    Yanagisawa, Kazuaki

    1976-12-01

    The conception, definition, measuring procedure of ''Grain Size'' were surveyed. A concept ''grain diameter'' was introduced after deriving a calculation formula for the grain diameter for using the Comparison (simple) and Intercept(detailed) procedure. As an example and putting into practice, the grain diameter determination was carried out by means of the Comparison procedure for a UO 2 pellet used in a densification experiment. (auth.)

  2. Implementation of procedures to NPP Krsko INTRANEK

    International Nuclear Information System (INIS)

    Gradisar, D.; Krajnc, M.; Kocnar, R.; Spiler, J.

    1999-01-01

    Part of NEK documentation has already been presented on NEK Intranet such as USAR, Technical Specifications, QA Plan as well as some frequently used series of drawings. At the time being the process of presentation of all procedures (thereinafter INTRANEK procedures) is in progress. The purpose of this project is the presentation of 1600 procedures with average size of 30 pages what is more than 48000 pages altogether. ADOBE PDF (Portable Document Format) has been chosen as the most suitable format for the presentation of procedures on INTRANEK. PDF format meets the following criteria: the outlook of a document page is always the same as an original one and cannot be changed without control. In addition to this, full text search is available as well as easy jump from procedure to procedure. Some changes of working process on internal procedures have to be made before the project start, which determine the responsibility of individual users in the process. The work flow, which enables easy daily maintenance, has been prepared, the rules of both procedure numbering as well as folder contents/name have been set and the server selected. The project was managed and implemented with the extensive use of compute-aided management, document distribution and control, databases, electronics mail and Intranet tools. The results of practical implementation of NEK procedures and our experience with INTRANEK are presented in this paper.(author)

  3. Radiation Exposure from Medical Exams and Procedures

    Science.gov (United States)

    Fact Sheet Adopted: January 2010 Health Physics Society Specialists in Radiation Safety Radiation Exposure from Medical Exams and Procedures Ionizing radiation is used daily in hospitals and clinics ...

  4. Procedural Pain Management for Children Receiving Physiotherapy

    OpenAIRE

    von Baeyer, Carl L.; Tupper, Susan M.

    2010-01-01

    Purpose: This article provides an overview of literature relevant to the prevention and relief of pain and distress during physiotherapy procedures, with guidance for physiotherapists treating children.

  5. Information Security - Data Loss Prevention Procedure

    Science.gov (United States)

    The purpose of this procedure is to extend and provide specificity to the Environmental Protection Agency (EPA) Information Security Policy regarding data loss prevention and digital rights management.

  6. Management of the Bohunice RPVs annealing procedures

    International Nuclear Information System (INIS)

    Repka, M.

    1994-01-01

    The program of annealing regeneration procedure of RPVs units 1 and 2 of NPP V-1 (EBO) realization in the year 1993, is the topic of this paper. In the paper the following steps are described in detail: the preparation works, the annealing procedure realization schedule and safety management: starting with zero conditions, assembling of annealing apparatus, annealing procedure, cooling down and disassembling procedure of annealing apparatus. At the end the programs of annealing of both RPVs including the dosimetry measurements are discussed and evaluated. (author). 3 figs

  7. Robot-assisted procedures in pediatric neurosurgery.

    Science.gov (United States)

    De Benedictis, Alessandro; Trezza, Andrea; Carai, Andrea; Genovese, Elisabetta; Procaccini, Emidio; Messina, Raffaella; Randi, Franco; Cossu, Silvia; Esposito, Giacomo; Palma, Paolo; Amante, Paolina; Rizzi, Michele; Marras, Carlo Efisio

    2017-05-01

    OBJECTIVE During the last 3 decades, robotic technology has rapidly spread across several surgical fields due to the continuous evolution of its versatility, stability, dexterity, and haptic properties. Neurosurgery pioneered the development of robotics, with the aim of improving the quality of several procedures requiring a high degree of accuracy and safety. Moreover, robot-guided approaches are of special interest in pediatric patients, who often have altered anatomy and challenging relationships between the diseased and eloquent structures. Nevertheless, the use of robots has been rarely reported in children. In this work, the authors describe their experience using the ROSA device (Robotized Stereotactic Assistant) in the neurosurgical management of a pediatric population. METHODS Between 2011 and 2016, 116 children underwent ROSA-assisted procedures for a variety of diseases (epilepsy, brain tumors, intra- or extraventricular and tumor cysts, obstructive hydrocephalus, and movement and behavioral disorders). Each patient received accurate preoperative planning of optimal trajectories, intraoperative frameless registration, surgical treatment using specific instruments held by the robotic arm, and postoperative CT or MR imaging. RESULTS The authors performed 128 consecutive surgeries, including implantation of 386 electrodes for stereo-electroencephalography (36 procedures), neuroendoscopy (42 procedures), stereotactic biopsy (26 procedures), pallidotomy (12 procedures), shunt placement (6 procedures), deep brain stimulation procedures (3 procedures), and stereotactic cyst aspiration (3 procedures). For each procedure, the authors analyzed and discussed accuracy, timing, and complications. CONCLUSIONS To the best their knowledge, the authors present the largest reported series of pediatric neurosurgical cases assisted by robotic support. The ROSA system provided improved safety and feasibility of minimally invasive approaches, thus optimizing the surgical

  8. Procedural pain in neonatal units in Kenya.

    Science.gov (United States)

    Kyololo, O'Brien Munyao; Stevens, Bonnie; Gastaldo, Denise; Gisore, Peter

    2014-11-01

    To determine the nature and frequency of painful procedures and procedural pain management practices in neonatal units in Kenya. Cross-sectional survey. Level I and level II neonatal units in Kenya. Ninety-five term and preterm neonates from seven neonatal units. Medical records of neonates admitted for at least 24 h were reviewed to determine the nature and frequency of painful procedures performed in the 24 h period preceding data collection (6:00 to 6:00) as well as the pain management interventions (eg, morphine, breastfeeding, skin-to-skin contact, containment, non-nutritive sucking) that accompanied each procedure. Neonates experienced a total of 404 painful procedures over a 24 h period (mean=4.3, SD 2.0; range 1-12); 270 tissue-damaging (mean=2.85, SD 1.1; range 1-6) and 134 non-tissue-damaging procedures (mean=1.41, SD 1.2; range 0-6). Peripheral cannula insertion (27%) and intramuscular injections (22%) were the most common painful procedures. Ventilated neonates and neonates admitted in level II neonatal units had a higher number of painful procedures than those admitted in level I units (mean 4.76 vs 2.96). Only one procedure had a pain intensity score documented; and none had been performed with any form of analgesia. Neonates in Kenya were exposed to numerous tissue-damaging and non-tissue-damaging procedures without any form of analgesia. Our findings suggest that education is needed on how to assess and manage procedural pain in neonatal units in Kenya. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

  9. Parliamentary Pastries: Learning Parliamentary Procedure through Cookies

    Science.gov (United States)

    Toupence, Rachelle H.

    2008-01-01

    Parliamentary procedure is an integral part of the business of many recreation organizations, but students often perceive it to be difficult and irrelevant to their professional preparation. The activity uses the creation of a cookie recipe to practice the basic meeting business functions in parliamentary procedure. The cookie meeting is an active…

  10. 29 CFR 1614.305 - Consideration procedures.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 4 2010-07-01 2010-07-01 false Consideration procedures. 1614.305 Section 1614.305 Labor Regulations Relating to Labor (Continued) EQUAL EMPLOYMENT OPPORTUNITY COMMISSION FEDERAL SECTOR EQUAL EMPLOYMENT OPPORTUNITY Related Processes § 1614.305 Consideration procedures. (a) Once a petition is filed...

  11. 32 CFR 623.4 - Accounting procedures.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 3 2010-07-01 2010-07-01 true Accounting procedures. 623.4 Section 623.4... ARMY MATERIEL § 623.4 Accounting procedures. (a) Loan document format. (1) When the lending accountable... property accounting purposes. (3) Loans will be processed by accountable property officers according to...

  12. W-087 Acceptance test procedure. Revision 1

    International Nuclear Information System (INIS)

    Joshi, A.W.

    1997-01-01

    This Acceptance Test Procedure/Operational Test Procedure (ATP/OTP) has been prepared to demonstrate that the Electrical/Instrumentation and Mechanical systems function as required by project criteria and to verify proper operation of the integrated system including the interlocks

  13. Acceptance test procedure for Project W-280

    International Nuclear Information System (INIS)

    Stites, C.G.

    1994-01-01

    This Document is the Acceptance Test Procedure for 200 Area C and SY Tank Farm Lighting Upgrade. This Acceptance Test Procedure has been prepared to demonstrate that the Tank Farm Lighting Systems function correctly as required by project criteria and as intended by design

  14. 25 CFR 225.21 - Negotiation procedures.

    Science.gov (United States)

    2010-04-01

    ... setting forth the duration of the minerals agreement; (3) A statement providing indemnification to the... accounting and mineral valuation procedures; (8) Provisions establishing operating and management procedures... refusal by the Indian mineral owner in the event of a proposed assignment; (10) Bond requirements; (11...

  15. 9 CFR 381.311 - Recall procedure.

    Science.gov (United States)

    2010-01-01

    ... CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS Canning and Canned Products § 381.311 Recall procedure... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Recall procedure. 381.311 Section 381.311 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY...

  16. Towards a procedure for metaphor identification

    NARCIS (Netherlands)

    Steen, G.J.

    2002-01-01

    This article aims to demonstrate the possibility of a stepwise procedure for metaphor identification. It is situated against the background of a more encompassing and complete five-step procedure for deriving conceptual metaphorical mappings from linguistic metaphors. The mainly cognitive linguistic

  17. 21 CFR 60.44 - Hearing procedures.

    Science.gov (United States)

    2010-04-01

    ... RESTORATION Due Diligence Hearings § 60.44 Hearing procedures. The due diligence hearing shall be conducted in accordance with this part, supplemented by the nonconflicting procedures in part 16. During the due diligence... requesting a hearing under part 16. The standard of due diligence set forth in § 60.36 will apply in the due...

  18. 48 CFR 410.002 - Procedures.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Procedures. 410.002 Section 410.002 Federal Acquisition Regulations System DEPARTMENT OF AGRICULTURE COMPETITION AND ACQUISITION PLANNING MARKET RESEARCH 410.002 Procedures. Market research must include obtaining information on...

  19. Procedural lawmaking at the International Criminal Tribunals

    NARCIS (Netherlands)

    Sluiter, G.; Darcy, S.; Powderly, J.

    2011-01-01

    This chapter examines the role played by the judges in creating the procedural rules which govern the functioning of the ad hoc Tribunals. Noting that the bench had been tasked with devising its own rules of procedure and evidence, it queries whether judicial lawmaking in this context at the

  20. MITS Feed and Withdrawal Subsystem: operating procedures

    International Nuclear Information System (INIS)

    Brown, W.S.

    1980-01-01

    This procedure details the steps involved in establishing closed loop flows, providing UF 6 vapor to the FEED header of the Sampling Subsystem and returning it through the PRODUCT and TAILS headers via the F and W recycle valves. It is essentially a Startup Procedure

  1. W-087 Acceptance test procedure. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Joshi, A.W.

    1997-06-10

    This Acceptance Test Procedure/Operational Test Procedure (ATP/OTP) has been prepared to demonstrate that the Electrical/Instrumentation and Mechanical systems function as required by project criteria and to verify proper operation of the integrated system including the interlocks.

  2. Procedure to Generate the MPACT Multigroup Library

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kang Seog [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-12-17

    The CASL neutronics simulator MPACT is under development for the neutronics and T-H coupled simulation for the light water reactor. The objective of this document is focused on reviewing the current procedure to generate the MPACT multigroup library. Detailed methodologies and procedures are included in this document for further discussion to improve the MPACT multigroup library.

  3. 48 CFR 17.504 - Ordering procedures.

    Science.gov (United States)

    2010-10-01

    ... METHODS AND CONTRACT TYPES SPECIAL CONTRACTING METHODS Interagency Acquisitions Under the Economy Act 17.504 Ordering procedures. (a) Before placing an Economy Act order for supplies or services with another...; see also 6.302 for procedures to follow where using other than full and open competition.) The...

  4. 77 FR 51943 - Procedures for Safety Investigations

    Science.gov (United States)

    2012-08-28

    ... rule, Procedures for Safety Investigations, which published July 27, 2012 in the Federal Register, 77... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1708 Procedures for Safety Investigations AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Proposed rule; extension of comment period...

  5. 22 CFR 226.71 - Closeout procedures.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Closeout procedures. 226.71 Section 226.71 Foreign Relations AGENCY FOR INTERNATIONAL DEVELOPMENT ADMINISTRATION OF ASSISTANCE AWARDS TO U.S. NON-GOVERNMENTAL ORGANIZATIONS After-the-Award Requirements § 226.71 Closeout procedures. (a) Recipients shall...

  6. CT4 - Cost-Optimum Procedures

    DEFF Research Database (Denmark)

    Thomsen, Kirsten Engelund; Wittchen, Kim Bjarne

    This report collects the status in European member states regarding implementation of the cos optimum procedure for setting energy performance requirements to new and existing buildings.......This report collects the status in European member states regarding implementation of the cos optimum procedure for setting energy performance requirements to new and existing buildings....

  7. Procedures for mastitis diagnosis and control.

    Science.gov (United States)

    Sears, P M; González, R N; Wilson, D J; Han, H R

    1993-11-01

    Procedures for mastitis diagnosis and control include culturing individual cow and bulk tank milk samples, antibiotic susceptibility testing, and evaluation of somatic cell count reports and clinical mastitis treatment records. Integrated use of such procedures is necessary for effective mastitis diagnosis and control.

  8. Multimodality imaging to guide cardiac interventional procedures

    NARCIS (Netherlands)

    Tops, Laurens Franciscus

    2010-01-01

    In recent years, a number of new cardiac interventional procedures have been introduced. Catheter ablation procedures for atrial fibrillation (AF) have been refined and are now considered a good treatment option in patients with drug-refractory AF. In cardiac pacing, cardiac resynchronization

  9. Matching procedure for the sixth Painleve equation

    International Nuclear Information System (INIS)

    Guzzetti, Davide

    2006-01-01

    In the framework of the isomonodromy deformation method, we present a constructive procedure to obtain the critical behaviour of Painleve VI transcendents and solve the connection problem. This procedure yields two- and one-parameter families of solutions, including trigonometric and logarithmic behaviours, and three classes of solutions with Taylor expansion at a critical point

  10. 5 CFR 339.303 - Examination procedures.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Examination procedures. 339.303 Section... QUALIFICATION DETERMINATIONS Medical Examinations § 339.303 Examination procedures. (a) When an agency orders or offers a medical examination under this subpart, it must inform the applicant or employee in writing of...

  11. 22 CFR 92.60 - Examination procedures.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Examination procedures. 92.60 Section 92.60... and Letters Rogatory § 92.60 Examination procedures. (a) Explaining interrogatory to witness. If the... examination of a witness propound such inquiries as may be necessary to satisfy himself whether the witness is...

  12. 47 CFR 13.209 - Examination procedures.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 1 2010-10-01 2010-10-01 false Examination procedures. 13.209 Section 13.209 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL COMMERCIAL RADIO OPERATORS Examination System § 13.209 Examination procedures. (a) Each examination for a commercial radio operator license must be administered at a...

  13. 37 CFR 1.809 - Examination procedures.

    Science.gov (United States)

    2010-07-01

    ... 37 Patents, Trademarks, and Copyrights 1 2010-07-01 2010-07-01 false Examination procedures. 1.809... Biological Material § 1.809 Examination procedures. (a) The examiner shall determine pursuant to § 1.104 in... deposited biological material sufficient to specifically identify it and to permit examination; and (4) The...

  14. 22 CFR 92.37 - Authentication procedure.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Authentication procedure. 92.37 Section 92.37... Notarial Acts § 92.37 Authentication procedure. (a) The consular officer must compare the foreign official...) Where the State law requires the consular officer's certificate of authentication to show that the...

  15. 46 CFR 296.40 - Billing procedures.

    Science.gov (United States)

    2010-10-01

    ... OPERATORS MARITIME SECURITY PROGRAM (MSP) Billing and Payment Procedures § 296.40 Billing procedures. Submission of voucher. For contractors operating under more than one MSP Operating Agreement, the contractor may submit a single monthly voucher applicable to all its MSP Operating Agreements. Each voucher...

  16. Procedures for ground-water investigations

    International Nuclear Information System (INIS)

    1992-12-01

    This manual was developed by the Pacific Northwest Laboratory (PNL) to document the procedures used to carry out and control the technical aspects of ground-water investigations at the PNL. Ground-water monitoring procedures are developed and used in accordance with the PNL Quality Assurance Program

  17. 8 CFR 270.2 - Enforcement procedures.

    Science.gov (United States)

    2010-01-01

    ... Aliens and Nationality DEPARTMENT OF HOMELAND SECURITY IMMIGRATION REGULATIONS PENALTIES FOR DOCUMENT FRAUD § 270.2 Enforcement procedures. (a) Procedures for the filing of complaints. Any person or entity... charges for document fraud committed by refugees at the time of entry. The Service shall not issue a...

  18. 40 CFR 7.90 - Grievance procedures.

    Science.gov (United States)

    2010-07-01

    ...) Exception. Recipients with fewer than fifteen (15) full-time employees need not comply with this section... Recipients § 7.90 Grievance procedures. (a) Requirements. Each recipient shall adopt grievance procedures... significantly impair the recipient's ability to provide benefits or services. ...

  19. 10 CFR 474.4 - Test procedures.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 3 2010-01-01 2010-01-01 false Test procedures. 474.4 Section 474.4 Energy DEPARTMENT OF ENERGY ENERGY CONSERVATION ELECTRIC AND HYBRID VEHICLE RESEARCH, DEVELOPMENT, AND DEMONSTRATION PROGRAM; PETROLEUM-EQUIVALENT FUEL ECONOMY CALCULATION § 474.4 Test procedures. (a) The electric vehicle energy...

  20. 40 CFR 68.52 - Operating procedures.

    Science.gov (United States)

    2010-07-01

    ...) CHEMICAL ACCIDENT PREVENTION PROVISIONS Program 2 Prevention Program § 68.52 Operating procedures. (a) The... for safely conducting activities associated with each covered process consistent with the safety information for that process. Operating procedures or instructions provided by equipment manufacturers or...

  1. Grid - a fast threshold tracking procedure

    DEFF Research Database (Denmark)

    Fereczkowski, Michal; Dau, Torsten; MacDonald, Ewen

    2016-01-01

    A new procedure, called “grid”, is evaluated that allows rapid acquisition of threshold curves for psychophysics and, in particular, psychoacoustic, experiments. In this method, the parameterresponse space is sampled in two dimensions within a single run. This allows the procedure to focus more e...

  2. 12 CFR 411.405 - Penalty procedures.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Penalty procedures. 411.405 Section 411.405 Banks and Banking EXPORT-IMPORT BANK OF THE UNITED STATES NEW RESTRICTIONS ON LOBBYING Penalties and Enforcement § 411.405 Penalty procedures. Agencies shall impose and collect civil penalties pursuant to the...

  3. 44 CFR 208.52 - Reimbursement procedures.

    Science.gov (United States)

    2010-10-01

    ... 44 Emergency Management and Assistance 1 2010-10-01 2010-10-01 false Reimbursement procedures. 208... Reimbursement Claims and Appeals § 208.52 Reimbursement procedures. (a) General. A Sponsoring Agency must present a claim for reimbursement to DHS in such manner as the Assistant Administrator specifies . (b...

  4. 28 CFR 527.31 - Procedures.

    Science.gov (United States)

    2010-07-01

    ... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Procedures. 527.31 Section 527.31 Judicial Administration BUREAU OF PRISONS, DEPARTMENT OF JUSTICE INMATE ADMISSION, CLASSIFICATION, AND TRANSFER TRANSFERS Transfer of Inmates to State Agents for Production on State Writs § 527.31 Procedures...

  5. 27 CFR 44.227 - Customs procedure.

    Science.gov (United States)

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 2 2010-04-01 2010-04-01 false Customs procedure. 44.227..., WITHOUT PAYMENT OF TAX, OR WITH DRAWBACK OF TAX Drawback of Tax § 44.227 Customs procedure. The customs... having inspected the articles and supervised the lading thereof on the export carrier, the customs...

  6. Comparison of transition-matrix sampling procedures

    DEFF Research Database (Denmark)

    Yevick, D.; Reimer, M.; Tromborg, Bjarne

    2009-01-01

    We compare the accuracy of the multicanonical procedure with that of transition-matrix models of static and dynamic communication system properties incorporating different acceptance rules. We find that for appropriate ranges of the underlying numerical parameters, algorithmically simple yet high...... accurate procedures can be employed in place of the standard multicanonical sampling algorithm....

  7. Procedural Due Process Rights in Student Discipline.

    Science.gov (United States)

    Pressman, Robert; Weinstein, Susan

    To assist administrators in understanding procedural due process rights in student discipline, this manual draws together hundreds of citations and case summaries of federal and state court decisions and provides detailed commentary as well. Chapter 1 outlines the general principles of procedural due process rights in student discipline, such as…

  8. 45 CFR 708.7 - Hearing procedures.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 3 2010-10-01 2010-10-01 false Hearing procedures. 708.7 Section 708.7 Public Welfare Regulations Relating to Public Welfare (Continued) COMMISSION ON CIVIL RIGHTS COLLECTION BY SALARY OFFSET FROM INDEBTED CURRENT AND FORMER EMPLOYEES § 708.7 Hearing procedures. (a) If an employee timely...

  9. 50 CFR 85.21 - Application procedures.

    Science.gov (United States)

    2010-10-01

    ... 50 Wildlife and Fisheries 6 2010-10-01 2010-10-01 false Application procedures. 85.21 Section 85... Application for Grants § 85.21 Application procedures. (a) Eligible applicants will submit their proposals to..., Missouri, Ohio, and Wisconsin Division of Federal Aid, U.S. Fish and Wildlife Service, Bishop Henry Whipple...

  10. 32 CFR 162.6 - Procedures.

    Science.gov (United States)

    2010-07-01

    ... Department of Defense OFFICE OF THE SECRETARY OF DEFENSE DEFENSE CONTRACTING PRODUCTIVITY ENHANCING CAPITAL INVESTMENT (PECI) § 162.6 Procedures. The following procedures shall be followed by the DoD Components in the... documentation, pre-investment analysis, financing, and post-investment accountability of PECI projects, when DoD...

  11. 5 CFR 179.304 - Notification procedures.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Notification procedures. 179.304 Section 179.304 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT CIVIL SERVICE REGULATIONS CLAIMS COLLECTION STANDARDS Administrative Offset § 179.304 Notification procedures. Before collecting any debt...

  12. 5 CFR 179.308 - Accelerated procedures.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Accelerated procedures. 179.308 Section 179.308 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT CIVIL SERVICE REGULATIONS CLAIMS COLLECTION STANDARDS Administrative Offset § 179.308 Accelerated procedures. OPM may make an administrative...

  13. 40 CFR 73.12 - Rounding Procedures.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Rounding Procedures. 73.12 Section 73.12 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) SULFUR DIOXIDE ALLOWANCE SYSTEM Allowance Allocations § 73.12 Rounding Procedures. (a) Calculation...

  14. 32 CFR 145.6 - Procedures.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 1 2010-07-01 2010-07-01 false Procedures. 145.6 Section 145.6 National Defense... THE OFFICE OF SPECIAL COUNSEL OF THE MERIT SYSTEMS PROTECTION BOARD § 145.6 Procedures. (a... corrective or disciplinary action considered appropriate because of facts disclosed by such an investigation...

  15. 28 CFR 550.31 - Procedures.

    Science.gov (United States)

    2010-07-01

    ... the allotted time period. An inmate may rebut this presumption during the disciplinary process. (b... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Procedures. 550.31 Section 550.31... Urine Surveillance § 550.31 Procedures. (a) Staff of the same sex as the inmate tested shall directly...

  16. Assessment procedures results of training in biology

    Directory of Open Access Journals (Sweden)

    Elena A. Galkina

    2018-04-01

    Full Text Available The article describes the procedures for evaluating the results of training in biology. The mechanisms for monitoring the learning outcomes of a biology teacher are presented. Examples of algorithms for procedures for evaluating learning outcomes in biology are demonstrated.

  17. The benefits of using customized procedure packs.

    Science.gov (United States)

    Baines, R; Colquhoun, G; Jones, N; Bateman, R

    2001-01-01

    Discrete item purchasing is the traditional approach for hospitals to obtain consumable supplies for theatre procedures. Although most items are relatively low cost, the management and co-ordination of the supply chain, raising orders, controlling stock, picking and delivering to each operating theatre can be complex and costly. Customized procedure packs provide a solution.

  18. Occupational exposures from selected interventional radiological procedures

    International Nuclear Information System (INIS)

    Janeczek, J.; Beal, A.; James, D.

    2001-01-01

    The number of radiology and cardiology interventional procedures has significantly increased in recent years due to better diagnostic equipment resulting in an increase in radiation dose to the staff and patients. The assessment of staff doses was performed for cardiac catheterization and for three other non-cardiac procedures. The scattered radiation distribution resulting from the cardiac catheterization procedure was measured prior to the staff dose measurements. Staff dose measurements included those of the left shoulder, eye, thyroid and hand doses of the cardiologist. In non-cardiac procedures doses to the hands of the radiologist were measured for nephrostomy, fistulogram and percutaneous transluminal angioplasty procedures. Doses to the radiologist or cardiologist were found to be relatively high if correct protection was not observed. (author)

  19. Deterministic effects of interventional radiology procedures

    International Nuclear Information System (INIS)

    Shope, Thomas B.

    1997-01-01

    The purpose of this paper is to describe deterministic radiation injuries reported to the Food and Drug Administration (FDA) that resulted from therapeutic, interventional procedures performed under fluoroscopic guidance, and to investigate the procedure or equipment-related factors that may have contributed to the injury. Reports submitted to the FDA under both mandatory and voluntary reporting requirements which described radiation-induced skin injuries from fluoroscopy were investigated. Serious skin injuries, including moist desquamation and tissues necrosis, have occurred since 1992. These injuries have resulted from a variety of interventional procedures which have required extended periods of fluoroscopy compared to typical diagnostic procedures. Facilities conducting therapeutic interventional procedures need to be aware of the potential for patient radiation injury and take appropriate steps to limit the potential for injury. (author)

  20. Sentinel node biopsy (SNB) in malignant melanoma as same day procedure vs delayed procedure

    DEFF Research Database (Denmark)

    Rødgaard, Jes Christian; Kramer, Stine; Stolle, Lars B

    2013-01-01

    The aim of this study was to compare a delayed sentinel node biopsy (dSNB) procedure with a same-day procedure (sSNB) in malignant melanoma. In March 2012, Aarhus University Hospital went from the dSNB to the sSNB procedure defined by lymphoscintigraphy (LS) and sentinel node biopsy (SNB) perform......, essential to keep the morbidity and economic costs low, while keeping the quality of the procedure high....

  1. An XML Representation for Crew Procedures

    Science.gov (United States)

    Simpson, Richard C.

    2005-01-01

    NASA ensures safe operation of complex systems through the use of formally-documented procedures, which encode the operational knowledge of the system as derived from system experts. Crew members use procedure documentation on the ground for training purposes and on-board space shuttle and space station to guide their activities. Investigators at JSC are developing a new representation for procedures that is content-based (as opposed to display-based). Instead of specifying how a procedure should look on the printed page, the content-based representation will identify the components of a procedure and (more importantly) how the components are related (e.g., how the activities within a procedure are sequenced; what resources need to be available for each activity). This approach will allow different sets of rules to be created for displaying procedures on a computer screen, on a hand-held personal digital assistant (PDA), verbally, or on a printed page, and will also allow intelligent reasoning processes to automatically interpret and use procedure definitions. During his NASA fellowship, Dr. Simpson examined how various industries represent procedures (also called business processes or workflows), in areas such as manufacturing, accounting, shipping, or customer service. A useful method for designing and evaluating workflow representation languages is by determining their ability to encode various workflow patterns, which depict abstract relationships between the components of a procedure removed from the context of a specific procedure or industry. Investigators have used this type of analysis to evaluate how well-suited existing workflow representation languages are for various industries based on the workflow patterns that commonly arise across industry-specific procedures. Based on this type of analysis, it is already clear that existing workflow representations capture discrete flow of control (i.e., when one activity should start and stop based on when other

  2. Judicial civil procedure dragging out in Kosovo

    Directory of Open Access Journals (Sweden)

    Rrustem Qehaja

    2016-03-01

    Full Text Available This article tends to deal with one of the most worrying issues in the judicial system of Kosovo the problem of judicial civil procedure dragging out. The article analyses the reasons of these dragging outs of the judicial civil procedure focusing on the context of one of the basic procedural principles in civil procedure-the principle of economy or efficiency in the courts. Dragging out of civil procedure in Kosovo has put in question not only the basic principles of civil procedure, but it also challenges the general principles related to human rights and freedoms sanctioned not only by the highest legal act of the country, but also with international treaties. The article tends to give a reflection to the most important reasons that effect and influence in these dragging outs of civil procedure, as well as, at the same time aims to give the necessary alternatives to pass through them by identifying dilemmas within the judicial practice. As a result, the motives of this scientific paper are exactly focused at the same time on identifying the dilemmas, as well as presenting ideas, to overstep them, including the judicial practice of the European Court of Human Rights on Article 6 of the European Convention on Human Rights, by which it is given the possibility to offering people efficient and within a reasonable time legal protection of their rights before national courts. For these reasons, the paper elaborates this issue based on both, the legal theory and judicial practice.

  3. Interim Reliability Evaluation Program procedures guide

    International Nuclear Information System (INIS)

    Carlson, D.D.; Gallup, D.R.; Kolaczkowski, A.M.; Kolb, G.J.; Stack, D.W.; Lofgren, E.; Horton, W.H.; Lobner, P.R.

    1983-01-01

    This document presents procedures for conducting analyses of a scope similar to those performed in Phase II of the Interim Reliability Evaluation Program (IREP). It documents the current state of the art in performing the plant systems analysis portion of a probabilistic risk assessment. Insights gained into managing such an analysis are discussed. Step-by-step procedures and methodological guidance constitute the major portion of the document. While not to be viewed as a cookbook, the procedures set forth the principal steps in performing an IREP analysis. Guidance for resolving the problems encountered in previous analyses is offered. Numerous examples and representative products from previous analyses clarify the discussion

  4. Radiation safety in nuclear medicine procedures

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Sang Geon; Kim, Ja Hae; Song, Ho Chun [Dept. of Nuclear Medicine, Medical Radiation Safety Research Center, Chonnam National University Hospital, Gwangju (Korea, Republic of)

    2017-03-15

    Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed.

  5. Smoke as a pictorial procedure: Fumage

    Directory of Open Access Journals (Sweden)

    José Antonio Pérez Esteban

    2013-01-01

    Full Text Available I propose a new definition for fumage and address in a brief approach —from the chemical point of view— the nature of smoke. From this base, I study the possible supports, potential tools for application in artistic purposes, visual possibilities, attachment procedure and narrative connotations related to its use. Next, I analyze its connections with the related heat engraving art. To finish and justifying the new definition which claims the contemporaneity of the procedure, I bring a list of artists who have used and, mainly, who are using this procedure in their artistic proposals.

  6. Radiation safety in nuclear medicine procedures

    International Nuclear Information System (INIS)

    Cho, Sang Geon; Kim, Ja Hae; Song, Ho Chun

    2017-01-01

    Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed

  7. Health Code Number (HCN) Development Procedure

    Energy Technology Data Exchange (ETDEWEB)

    Petrocchi, Rocky; Craig, Douglas K.; Bond, Jayne-Anne; Trott, Donna M.; Yu, Xiao-Ying

    2013-09-01

    This report provides the detailed description of health code numbers (HCNs) and the procedure of how each HCN is assigned. It contains many guidelines and rationales of HCNs. HCNs are used in the chemical mixture methodology (CMM), a method recommended by the department of energy (DOE) for assessing health effects as a result of exposures to airborne aerosols in an emergency. The procedure is a useful tool for proficient HCN code developers. Intense training and quality assurance with qualified HCN developers are required before an individual comprehends the procedure to develop HCNs for DOE.

  8. Reliability of application of inspection procedures

    Energy Technology Data Exchange (ETDEWEB)

    Murgatroyd, R A

    1988-12-31

    This document deals with the reliability of application of inspection procedures. A method to ensure that the inspection of defects thanks to fracture mechanics is reliable is described. The Systematic Human Error Reduction and Prediction Analysis (SHERPA) methodology is applied to every task performed by the inspector to estimate the possibility of error. It appears that it is essential that inspection procedures should be sufficiently rigorous to avoid substantial errors, and that the selection procedures and the training period for inspectors should be optimised. (TEC). 3 refs.

  9. Reliability of application of inspection procedures

    International Nuclear Information System (INIS)

    Murgatroyd, R.A.

    1988-01-01

    This document deals with the reliability of application of inspection procedures. A method to ensure that the inspection of defects thanks to fracture mechanics is reliable is described. The Systematic Human Error Reduction and Prediction Analysis (SHERPA) methodology is applied to every task performed by the inspector to estimate the possibility of error. It appears that it is essential that inspection procedures should be sufficiently rigorous to avoid substantial errors, and that the selection procedures and the training period for inspectors should be optimised. (TEC)

  10. Overview of LBB implementation for the EPR

    International Nuclear Information System (INIS)

    Cauquelin, C.

    1997-01-01

    This paper presents an overview of the use of leak-before-break (LBB) analysis for EPR reactors. EPR is an evolutionary Nuclear Island of the 4 loop x 1500 Mwe class currently in the design phase. Application of LBB to the main coolant lines and resulting design impacts are summarized. Background information on LBB analysis in France and Germany is also presented

  11. The analysis of normative requirements to materials of PWR components, basing on LBB concepts

    Energy Technology Data Exchange (ETDEWEB)

    Anikovsky, V.V.; Karzov, G.P.; Timofeev, B.T. [CRISM Prometey, St. Petersburg (Russian Federation)

    1997-04-01

    The paper discusses the advisability of the correction of Norms to solve in terms of material science the Problem: how the normative requirements to materials must be changed in terms of the concept {open_quotes}leak before break{close_quotes} (LBB).

  12. The failure behavior of duplex 316 L steel-TA6V titanium alloy spherical pressure vessels

    International Nuclear Information System (INIS)

    Miannay, D.

    1980-05-01

    The purpose of this paper is to compare the experimental residual stresses of spherical vessels made of TA6V alloy which exhibits plasticity before failure in toughness testing and cracked with several configurations, with stresses estimated according to the afore mentioned theories. An internal austenitic 316 L steel is used to prevent 'leak before break' [fr

  13. Overview of LBB implementation for the EPR

    Energy Technology Data Exchange (ETDEWEB)

    Cauquelin, C.

    1997-04-01

    This paper presents an overview of the use of leak-before-break (LBB) analysis for EPR reactors. EPR is an evolutionary Nuclear Island of the 4 loop x 1500 Mwe class currently in the design phase. Application of LBB to the main coolant lines and resulting design impacts are summarized. Background information on LBB analysis in France and Germany is also presented.

  14. Crack-opening area calculations for circumferential through-wall pipe cracks

    Energy Technology Data Exchange (ETDEWEB)

    Kishida, K.; Zahoor, A.

    1988-08-01

    This report describes the estimation schemes for crack opening displacement (COD) of a circumferential through-wall crack, then compares the COD predictions with pipe experimental data. Accurate predictions for COD are required to reliably predict the leak rate through a crack in leak-before-break applications.

  15. Crack-opening area calculations for circumferential through-wall pipe cracks

    International Nuclear Information System (INIS)

    Kishida, K.; Zahoor, A.

    1988-08-01

    This report describes the estimation schemes for crack opening displacement (COD) of a circumferential through-wall crack, then compares the COD predictions with pipe experimental data. Accurate predictions for COD are required to reliably predict the leak rate through a crack in leak-before-break applications

  16. Ductile fracture behaviour of primary heat transport piping material ...

    Indian Academy of Sciences (India)

    R. Narasimhan (Krishtel eMaging) 1461 1996 Oct 15 13:05:22

    Abstract. Design of primary heat transport (PHT) piping of pressurised heavy water reactors (PHWR) has to ensure implementation of leak-before-break con- cepts. In order to be able to do so, the ductile fracture characteristics of PHT piping material have to be quantified. In this paper, the fracture resistance of SA333, Grade.

  17. Helicopter Flight Procedures for Community Noise Reduction

    Science.gov (United States)

    Greenwood, Eric

    2017-01-01

    A computationally efficient, semiempirical noise model suitable for maneuvering flight noise prediction is used to evaluate the community noise impact of practical variations on several helicopter flight procedures typical of normal operations. Turns, "quick-stops," approaches, climbs, and combinations of these maneuvers are assessed. Relatively small variations in flight procedures are shown to cause significant changes to Sound Exposure Levels over a wide area. Guidelines are developed for helicopter pilots intended to provide effective strategies for reducing the negative effects of helicopter noise on the community. Finally, direct optimization of flight trajectories is conducted to identify low noise optimal flight procedures and quantify the magnitude of community noise reductions that can be obtained through tailored helicopter flight procedures. Physically realizable optimal turns and approaches are identified that achieve global noise reductions of as much as 10 dBA Sound Exposure Level.

  18. 7 CFR 1210.325 - Procedure.

    Science.gov (United States)

    2010-01-01

    ... Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (MARKETING AGREEMENTS AND ORDERS; MISCELLANEOUS COMMODITIES), DEPARTMENT OF AGRICULTURE WATERMELON RESEARCH AND PROMOTION PLAN Watermelon Research and Promotion Plan National Watermelon Promotion Board § 1210.325 Procedure...

  19. 21 CFR 314.530 - Withdrawal procedures.

    Science.gov (United States)

    2010-04-01

    ... Serious or Life-Threatening Illnesses § 314.530 Withdrawal procedures. (a) For new drugs approved under... benefit; (2) The applicant fails to perform the required postmarketing study with due diligence; (3) Use...

  20. 46 CFR 221.85 - Hearing procedures.

    Science.gov (United States)

    2010-10-01

    ... § 221.85 Hearing procedures. (a) The Hearing Officer shall conduct a fair and impartial proceeding in... the authentication of any written exhibit or statement. (c) At the close of the Party's presentation...