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Sample records for containment performance assessment

  1. Performance assessment of containment filtered venting system with Venturi scrubber

    International Nuclear Information System (INIS)

    Adinarayna, K.N.V.; Ali, Seik Mansoor; Balasubramaniyan, V.

    2015-01-01

    Venting through appropriate filtration systems is now being considered as a severe accident management strategy for maintaining the containment integrity and also as a means to reduce the radiological consequences to the public and environment. The option of filtered containment venting appears to have assumed significance in the post- Fukushima accident backdrop. Back-fitting of a suitable Venturi scrubber based CFVS for the Indian BWRs (TAPS- 1 and 2) at Tarapur is now being contemplated. Several key issues need to be carefully addressed for ensuring the desired functional capability of such a system. At the outset, this paper highlights a few thermal hydraulic issues that are of interest from regulatory perspective. This is followed by a detailed description of the mathematical models developed for assessing the depressurization characteristics of CFVS, energy absorption capacity of the Scrubber Tank (ST) water inventory, iodine removal and aerosol retention capability etc. Finally, application of these models to investigate the response of CFVS under twin unit SBO conditions in TAPS-1 and 2 is presented. The studies presented here give insight into the key variables affecting the CFVS performance and would be useful to both the system designer as well as the regulator. (author)

  2. Containment performance improvement program

    International Nuclear Information System (INIS)

    Beckner, W.; Mitchell, J.; Soffer, L.; Chow, E.; Lane, J.; Ridgely, J.

    1990-01-01

    The Containment Performance Improvement (CPI) program has been one of the main elements in the US Nuclear Regulatory Commission's (NRC's) integrated approach to closure of severe accident issues for US nuclear power plants. During the course of the program, results from various probabilistic risk assessment (PRA) studies and from severe accident research programs for the five US containment types have been examined to identify significant containment challenges and to evaluate potential improvements. The five containment types considered are: the boiling water reactor (BMR) Mark I containment, the BWR Mark II containment, the BWR Mark III containment, the pressurized water reactor (PWR) ice condenser containment, and the PWR dry containments (including both subatmospheric and large subtypes). The focus of the CPI program has been containment performance and accident mitigation, however, insights are also being obtained in the areas of accident prevention and accident management

  3. Assessment of Loads and Performance of a Containment in a Hypothetical Accident (ALPHA). Facility design report

    International Nuclear Information System (INIS)

    Yamano, Norihiro; Maruyama, Yu; Kudo, Tamotsu; Moriyama, Kiyofumi; Ito, Hideo; Komori, Keiichi; Sonobe, Hisao; Sugimoto, Jun

    1998-06-01

    In the ALPHA (Assessment of Loads and Performance of Containment in Hypothetical Accident) program, several tests have been performed to quantitatively evaluate loads to and performance of a containment vessel during a severe accident of a light water reactor. The ALPHA program focuses on investigating leak behavior through the containment vessel, fuel-coolant interaction, molten core-concrete interaction and FP aerosol behavior, which are generally recognized as significant phenomena considered to occur in the containment. In designing the experimental facility, it was considered to simulate appropriately the phenomena mentioned above, and to cover experimental conditions not covered by previous works involving high pressure and temperature. Experiments from the viewpoint of accident management were also included in the scope. The present report describes design specifications, dimensions, instrumentation of the ALPHA facility based on the specific test objectives and procedures. (author)

  4. Assessment of the effect of nitrogen gas on passive containment cooling system performance

    International Nuclear Information System (INIS)

    Ha, Huiun; Suh, Jungsoo

    2016-01-01

    As a part of the passive containment cooling system (PCCS) of Innovative PWR development project, we have been investigating the effect of the nitrogen gas released from safety injection tank (SIT) on PCCS performance. With the design characteristics of APR1400 and conceptual design of PCCS, we developed a GOTHIC model of the APR1400 containment with PCCS. The calculation model is described herein, and representative results from the calculation are presented as well. The results of the present work will be used for the design of PCCS. APR1400 GOTHIC model was developed for assessment on the effect of SIT nitrogen gas on passive containment cooling system performance. Calculation results confirmed that influence of nitrogen gas release is negligible; however, further studies should be performed to confirm effect of non-condensable gas on the final performance of PCCS. These insights are important for developing the PCCS of Innovative PWR

  5. Assessment of the effect of nitrogen gas on passive containment cooling system performance

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Huiun; Suh, Jungsoo [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    As a part of the passive containment cooling system (PCCS) of Innovative PWR development project, we have been investigating the effect of the nitrogen gas released from safety injection tank (SIT) on PCCS performance. With the design characteristics of APR1400 and conceptual design of PCCS, we developed a GOTHIC model of the APR1400 containment with PCCS. The calculation model is described herein, and representative results from the calculation are presented as well. The results of the present work will be used for the design of PCCS. APR1400 GOTHIC model was developed for assessment on the effect of SIT nitrogen gas on passive containment cooling system performance. Calculation results confirmed that influence of nitrogen gas release is negligible; however, further studies should be performed to confirm effect of non-condensable gas on the final performance of PCCS. These insights are important for developing the PCCS of Innovative PWR.

  6. Initial performance assessment of the Westinghouse AP600 containment design and related safety issues

    International Nuclear Information System (INIS)

    Nicolette, V.F.; Washington, K.E.; Tills, J.L.

    1991-01-01

    This work summarizes the Westinghouse AP600 advanced reactor design assessment calculations performed to date with the CONTAIN code. Correlations for modeling the important heat transfer phenomena are discussed as well. A CONTAIN model of the AP600 was constructed for design basis accident (DBA) calculations. Insights gained from modeling of the smaller-scale Westinghouse Integral Test Facility were incorporated in the development of the AP600 model. The results of the DBA calculations are compared to the results of other researchers to serve as a point of reference for future severe accident calculations. The CONTAIN calculations are reviewed to examine several parameters/phenomena of interest. The results of the calculations are also used to identify limitations of the CONTAIN code regarding application to advanced reactor containment designs. The most recent heat transfer correlations available in the literature are assessed for use in the flow regimes and geometries applicable to the AP600. Use of one of these correlations in CONTAIN may allow for a more accurate assessment of the AP600

  7. Contaminant fluxes through site containment barriers: Performance assessment and illustrative results

    International Nuclear Information System (INIS)

    Vita, C.L.

    1994-01-01

    Contaminant mass flux by advective and diffusive transport is predicted for five containment barriers that use one or more clay liners, flexible membrane liners (FMLs), or liquid collection and removal systems (LCRS)s. Barriers are engineered systems intended to contain and isolate site contaminants from the environment. Barriers include liners, caps, and cutoff walls. Barriers may be used in contaminated-site cleanups (including CERCLA and RCRA), RCRA landfills, or other RCRA TSDFs. Concepts are provided for barrier performance assessment, including analysis and optimization, for meeting performance requirements and controlling risk at minimum cost. Concepts and results can help in planning, designing, or evaluating and communicating, the use or effectiveness of proposed or existing barriers for site cleanups or waste containment. 15 refs., 6 figs., 5 tabs

  8. Assessment of the performance of containment and surveillance equipment part 1: methodology

    International Nuclear Information System (INIS)

    Rezniczek, A.; Richter, B.

    2009-01-01

    Equipment performance aims at the creation of relevant data. As Containment and Surveillance (C/S) is playing an ever increasing role in safeguards systems, the issue of how to assess the performance of C/S equipment is being addressed by the ESARDA Working Group on C/S. The issue is important not only for the development of appropriate safeguards approaches but also for the review of existing approaches with regard to the implementation of the Additional Protocol (A P) and Integrated Safeguards. It is expected that the selection process of appropriate equipment, especially for unattended operation, is facilitated by the availability of methods to determine the performance of such equipment. Apart from EURATOM, the users of assessment methodologies would be the International Atomic Energy Agency (IAEA), plant operators, and instrument developers. The paper describes a non-quantitative performance assessment methodology. A structured procedure is outlined that allows assessing the suitability of different C/S instrumentation to comply with the objectives of its application. The principle to determine the performance of C/S equipment is to define, based on safeguards requirements, a task profile and to check the performance profile against the task profile. The performance profile of C/S equipment can be derived from the functional specifications and design basis tolerances provided by the equipment manufacturers.

  9. Probabilistic safety assessment of LWR containment systems performance. Report of principal working group n.5 on risk assessment

    International Nuclear Information System (INIS)

    Holloway, N.J.; Harper, F.T.; Bellard, S.W.

    1992-01-01

    This report reviews current approaches to PSA of LWR containment systems performance. It is based on a variety of recent PSA reports which deal with Level-2 PSA. The report is a summary of recent state-of-the-art containment analysis and is intended to assist analysts in their selection of the most appropriate methods of extending Level-1 plant safety evaluations into Level-2 assessments of the containment performance. The document is primarily concerned with the performance of the containment as an engineered system rather than with the source terms consequent upon its failure. It is addressed mainly to the performance of large dry PWR containments, with a secondary emphasis on other containment types. After explaining the purposes of these analyses, a survey of LWR containment analysis options is presented: direct approaches using containment event tree construction, indirect approaches based on previous PSAs, alternative and novel approaches. The selection process is then described, followed by conclusions on their suitability for various cases: accident management, research prioritization, identifying design weaknesses, specific issue resolution, modelling physical reality, etc.

  10. Assessment of the performance of containment and surveillance equipment part 2: trial application

    International Nuclear Information System (INIS)

    Rezniczek, A.; Richter, B.; Jussofie, A.

    2009-01-01

    The adopted methodological approach for assessing the performance of Containment and Surveillance (C/S) equipment resulted from an account of work performed for and in cooperation with the ESARDA Working Group on C/S. It was applied on a trial basis to a dry storage facility for spent nuclear fuel and consisted of the following steps: (1) Acquisition and analysis of design information and operational characteristics of the facility under consideration, (2) assumptions on diversion and misuse scenarios, (3) assumptions on safeguards approach and definition of safeguards requirements, (4) compilation and characterisation of candidate C/S equipment, (5) performance assessment of C/S equipment. The candidate equipment taken into account was routinely used by the IAEA: DCM14-type camera, Type E capand- wire seal, COBRA fibre optic seal, and VACOSS electronic seal. Four applications were considered: camera mounted in the reception area, seal on secondary lid of transport and storage cask, seal on protective lid, and seal on group of casks. For these applications, requirements were defined and requirement levels were attributed. The assignment of performance levels was carried out by using the technical specifications and design basis tolerances provided by the equipment manufacturers. The results were entered into four performance assessment tables. Although the assessment methodology was not yet fully developed, its trial application yielded promising results with regard to the selection of appropriate C/S equipment.

  11. Assessment of CONTAIN and MELCOR for performing LOCA and LOVA analyses in ITER

    International Nuclear Information System (INIS)

    Merrill, B.J.; Hagrman, D.L.; Gaeta, M.J.; Petti, D.A.

    1994-09-01

    This report describes the results of an assessment of the CONTAIN and MELCOR computer codes for ITER LOCA and LOVA applications. As part of the assessment, the results of running a test problem that describes an ITER LOCA are presented. It is concluded that the MELCOR code should be the preferred code for ITER severe accident thermal hydraulic analyses. This code will require the least modification to be appropriate for calculating thermal hydraulic behavior in ITER relevant conditions that include vacuum, cryogenics, ITER temperatures, and the presence of a liquid metal test module. The assessment of the aerosol transport models in these codes concludes that several modifications would have to be made to CONTAIN and/or MELCOR to make them applicable to the aerosol transport part of severe accident analysis in ITER

  12. LASCO: a performance assessment and training laboratory for containment and surveillance techniques

    International Nuclear Information System (INIS)

    Cuypers, M.; Landat, D.

    1991-01-01

    The use of Containment and Surveillance (C/S) techniques for the implementation of nuclear safeguards has increased substantially in recent years. Sealing and identification systems are used on a large scale and video surveillance is replacing gradually film camera systems. Furthermore many C/S systems are operated in an unattended mode. In order to evaluate the performances and assurance which can be obtained from C/S systems, JRC has installed a laboratory, called LaSCo, for testing C/S components and systems, simulating, where possible, field conditions. This laboratory includes facilities for training inspectors, for instance for reviewing aid of video pictures, use of integrated multisensor systems, evaluation of ultrasonic sealing methods. Several years ago, JRC installed a performance laboratory for NDA, called PERLA, which is now extensively used. LaSCo is expected to play the same role as PERLA but in the field of Containment and Surveillance and by extension to non nuclear measurements (e.g. Weighing, volume determinations). The newly built facilities and the first experimental lay-out of LaSCo are described. It is expected that industry and inspectors will make extensive use of LaSCo

  13. Mechanical performance assessment of half warm recycled asphalt mixes containing up to 100 % RAP

    International Nuclear Information System (INIS)

    Lizárraga, J. M.; Jiménez del Barco-Carrión, A.; Ramírez, A.; Díaz, P.; Moreno-Navarro, F.; Rubio, M.C.

    2017-01-01

    The use of Half Warm Mixes with high Reclaimed Asphalt content (HWMRA) has the potential to generate significant environmental advantages such as the reduction in consumption of natural resources and the emission of gases into the atmosphere. This paper therefore focuses on demonstrating the viability of using these types of mixes in wearing courses. For this purpose, an HWMRA with 70 % and 100 % Reclaimed Asphalt Pavement (RAP) and emulsion were designed in the laboratory. The performance of the mixes was then assessed and compared with that of conventional Hot Mix Asphalt. In a second stage, the mixes were manufactured in-plant, and laid and compacted in an Accelerated Pavement Test track. The cores were then extracted and tested for stiffness modulus and resistance to fatigue. The results from the tests conducted with both the laboratory specimens and the cores showed that the performance of HWMRA is comparable to that of HMA. These findings encourage greater confidence in promoting the use of these types of sustainable asphalt mixes. [es

  14. Mechanical performance assessment of half warm recycled asphalt mixes containing up to 100 % RAP

    Directory of Open Access Journals (Sweden)

    J. M. Lizárraga

    2017-07-01

    Full Text Available The use of Half Warm Mixes with high Reclaimed Asphalt content (HWMRA has the potential to generate significant environmental advantages such as the reduction in consumption of natural resources and the emission of gases into the atmosphere. This paper therefore focuses on demonstrating the viability of using these types of mixes in wearing courses. For this purpose, an HWMRA with 70 % and 100 % Reclaimed Asphalt Pavement (RAP and emulsion were designed in the laboratory. The performance of the mixes was then assessed and compared with that of conventional Hot Mix Asphalt. In a second stage, the mixes were manufactured in-plant, and laid and compacted in an Accelerated Pavement Test track. The cores were then extracted and tested for stiffness modulus and resistance to fatigue. The results from the tests conducted with both the laboratory specimens and the cores showed that the performance of HWMRA is comparable to that of HMA. These findings encourage greater confidence in promoting the use of these types of sustainable asphalt mixes.

  15. Decontamination of digital image sensors and assessment of electron microscope performance in a BSL-3 containment

    Directory of Open Access Journals (Sweden)

    Michael B. Sherman

    2015-05-01

    Full Text Available A unique biological safety level (BSL-3 cryo-electron microscopy facility with a 200 keV high-end cryo-electron microscope has been commissioned at the University of Texas Medical Branch (UTMB to study the structure of viruses and bacteria classified as select agents. We developed a microscope decontamination protocol based on chlorine dioxide gas with a continuous flow system. In this paper we report on testing digital camera sensors (both CCD and CMOS direct detector in a BSL-3 environment, and microscope performance after chlorine dioxide (ClO2 decontamination cycles.

  16. Overpressurization performance of containment structures

    International Nuclear Information System (INIS)

    Barr, P.; Bleackley, M.; Harrop, L.P.; Hargreaves, J.; Jowett, J.; Phillips, D.W.

    1987-01-01

    The containment building of a PWR is the outermost engineered barrier between the reactor and the environment. The most important element of such a containment system is the pressure boundary structure and its associated seals and penetrations. This containment structure is designed deterministically to withstand a number of loads and load combinations of which the dominant one is generally the internal pressure due to the double-ended guillotine break in one of the primary circuit loops. Typically, the design basis large LOCA produces a peak pressure increase in the region of 0.3 MPa in some 10 seconds and with a duration of up to a few tens of seconds. The assessment of overpressure performance of the containment structure is a key component of the PWR safety case, and is usually carried out by estimating a static factor of safety to some failure limit state. These estimates can be made using simple force-balance calculations or complicated finite element calculations, and both approaches have merit. In this paper we examine these approaches and discuss their value in estimating failure pressures and failure modes for a variety of internal pressurization transients. This discussion covers both general design and risk considerations and is illustrated by numerical examples taken from previous and on-going analysis

  17. An assessment of BWR [boiling water reactor] Mark III containment challenges, failure modes, and potential improvements in performance

    International Nuclear Information System (INIS)

    Schroeder, J.A.; Pafford, D.J.; Kelly, D.L.; Jones, K.R.; Dallman, F.J.

    1991-01-01

    This report describes risk-significant challenges posed to Mark III containment systems by severe accidents as identified for Grand Gulf. Design similarities and differences between the Mark III plants that are important to containment performance are summarized. The accident sequences responsible for the challenges and the postulated containment failure modes associated with each challenge are identified and described. Improvements are discussed that have the potential either to prevent or delay containment failure, or to mitigate the offsite consequences of a fission product release. For each of these potential improvements, a qualitative analysis is provided. A limited quantitative risk analysis is provided for selected potential improvements. 21 refs., 5 figs., 46 tabs

  18. Performance assessment

    International Nuclear Information System (INIS)

    Doe, T.

    1985-01-01

    The purpose of performance assessment is to show that the repository is expected to serve its stated function - disposing of radioactive waste safely both during operation and for the postclosure period. Performance assessment is a straightforward concept, but its application may be very complicated. The concept of performance assessment has been clarified by the Nuclear Regulatory Commission (NRC) in their Draft Generic Technical Position on Licensing Assessment Methodology for High-Level Waste Geologic Repositories (NRC, 1984). This document has gone a long way toward defining the criteria that the NRC will use to determine whether or not information from site characterization is adequate to meet the regulations of the Nuclear Regulatory Commission and the Environmental Protection Agency (EPA). A favorable determination is required for issuance of a construction authorization, which is the first major regulatory requirement for developing a working repository. It is, therefore, essential that a research program be developed that not only resolves the outstanding technical issues, but also does it in such a way that the results are clearly applicable to the formal performance assessment and licensing procedures. The definitions of performance assessment are reviewed and the current NRC thinking is summarized

  19. A multimedia exposure assessment methodology for evaluating the performance of the design of structures containing chemical and radioactive wastes

    International Nuclear Information System (INIS)

    Stephanatos, B.N.; Molholt, B.; Walter, K.P.; MacGregor, A.

    1991-01-01

    The objectives of this work are to develop a multimedia exposure assessment methodology for the evaluation of existing and future design of structures containing chemical and radioactive wastes and to identify critical parameters for design optimization. The designs are evaluated in terms of their compliance with various federal and state regulatory requirements. Evaluation of the performance of a particular design is presented within the scope of a given exposure pathway. An exposure pathway has four key components: (1) a source and mechanism of chemical release, (2) a transport medium; (3) a point of exposure; and (4) a route of exposure. The first step in the analysis is the characterization of the waste source behavior. The rate and concentration of releases from the source are evaluated using appropriate mathematical models. The migration of radionuclides and chemicals is simulated through each environmental medium to the exposure point. The total exposure to the potential receptor is calculated, and an estimate of the health effects of the exposure is made. Simulation of the movement of radionuclides and chemical wastes from the source to the receptor point includes several processes. If the predicted human exposure to contaminants meets the performance criteria, the design has been validated. Otherwise the structure design is improved to meet the performance criteria. A phased modeling approach is recommended at a particular mixed waste site. A relatively simple model is initially used to pinpoint critical fate and transport processes and design parameters. The second phase of the modeling effort involves the use of more complex and resource intensive fate and transport models. This final step in the modeling process provides more accurate estimates of contaminant concentrations at the point of exposure. Thus the human dose is more accurately predicted, providing better design validation

  20. An assessment of BWR [boiling water reactor] Mark-II containment challenges, failure modes, and potential improvements in performance

    International Nuclear Information System (INIS)

    Kelly, D.L.; Jones, K.R.; Dallman, R.J.; Wagner, K.C.

    1990-07-01

    This report assesses challenges to BWR Mark II containment integrity that could potentially arise from severe accidents. Also assessed are some potential improvements that could prevent core damage or containment failure, or could mitigate the consequences of such failure by reducing the release of fission products to the environment. These challenges and improvements are analyzed via a limited quantitative risk/benefit analysis of a generic BWR/4 reactor with Mark II containment. Point estimate frequencies of the dominant core damage sequences are obtained and simple containment event trees are constructed to evaluate the response of the containment to these severe accident sequences. The resulting containment release modes are then binned into source term release categories, which provide inputs to the consequence analysis. The output of the consequences analysis is used to construct an overall base case risk profile. Potential improvements and sensitivities are evaluated by modifying the event tree spilt fractions, thus generating a revised risk profile. Several important sensitivity cases are examined to evaluate the impact of phenomenological uncertainties on the final results. 75 refs., 25 figs., 65 tabs

  1. Measurements and assessments on shielding performance of FCTC{sub 10}'6{sup 0}Co transport container

    Energy Technology Data Exchange (ETDEWEB)

    Zhuang, Dajie; Li, Guo Qiang; Wang, Renze [China Institute for Radiation Protection, Shanxi (China); Zhang, Guo Qing [Shanghai Institute of Applied Physics, Shanghai (China)

    2016-09-15

    FCTC10 container is designed to transport {sup 60}Co radioactive sources used in irradiation industry. It belongs to Type B(U) Category III (yellow) package when being loaded with a {sup 60}Co source of 1.8×10{sup 5} Ci. The container is constituted of shielding container, basket, protective cover and bracket. Shielding ability is provided mainly by stainless steel shells, tungsten alloy and lead among steel shells. Radiation level around the container has been calculated with both Monte Carlo simulations and measurements. It is proven that the shielding performance of the container fulfills the requirements in GB11806-2004 (Regulations for the safe transport of radioactive material, China Standard Press). Exposure doses to workers and to critical groups of public were calculated based on hypothetical exposure scene according to transport practice experience. The results show that doses to workers and public are less than the constraint dose considered in design, and the radiation level would be increased less than a factor of 2 under design basis accidents.

  2. NRC performance assessment program

    International Nuclear Information System (INIS)

    Coplan, S.M.

    1986-01-01

    The U.S. Nuclear Regulatory Commission's (NRC) performance assessment program includes the development of guidance to the U.S. Department of Energy (DOE) on preparation of a license application and on conducting the studies to support a license application. The nature of the licensing requirements of 10 CFR Part 60 create a need for performance assessments by the DOE. The NRC and DOE staffs each have specific roles in assuring the adequacy of those assessments. Performance allocation is an approach for determining what testing and analysis will be needed during site characterization to assure that an adequate data base is available to support the necessary performance assessments. From the standpoint of establishing is implementable methodology, the most challenging performance assessment needed for licensing is the one that will be used to determine compliance with the U.S. Environmental Protection Agency's (EPA) containment requirement

  3. Development of integraded mechanistically-based degradation-mode models for performance assessment of high-level waste containers

    Energy Technology Data Exchange (ETDEWEB)

    Farmer, J. C., LLNL

    1998-06-01

    A key component of the Engineered Barrier System (EBS) being designed for containment of spent-fuel and high-level waste at the proposed geological repository at Yucca Mountain, Nevada is a two-tayer canister. In this particular design, the inner barrier is made of a corrosion resistant material (CRM) such as Alloy 825, 625 or C-22, while the outer barrier is made of a corrosion-allowance material (CAM) such as A516 Gr 55 or Monel 400. At the present time, Alloy C- 22 and A516 Gr 55 are favored.

  4. Development of integrated mechanistically-based degradation-mode models for performance assessment of high-level waste containers

    International Nuclear Information System (INIS)

    Farmer, J. C.

    1998-01-01

    A key component of the Engineered Barrier System (EBS) being designed for containment of spent-fuel and high-level waste at the proposed geological repository at Yucca Mountain, Nevada is a two-tayer canister. In this particular design, the inner barrier is made of a corrosion resistant material (CRM) such as Alloy 825, 625 or C-22, while the outer barrier is made of a corrosion-allowance material (CAM) such as A516 Gr 55 or Monel 400. At the present time, Alloy C- 22 and A516 Gr 55 are favored

  5. Development of integrated mechanistically-based degradation-mode models for performance assessment of high-level waste containers

    International Nuclear Information System (INIS)

    Bedrossian, P; Estill, J; Farmer, J; Hopper, R; Horn, J; Huang, J S; McCright, D; Roy, A; Wang, F; Wilfinger, K

    1999-01-01

    A key component of the Engineered Barrier System (EBS) being designed for containment of spent-fuel and high-level waste at the proposed geological repository at Yucca Mountain, Nevada is a two-layer canister. In this particular design, the inner barrier is made of a corrosion resistant material (CRM) such as Alloy 825, 625 or C-22, while the outer barrier is made of a corrosion-allowance material (CAM) such as A516 Gr 55, a carbon steel, or Monel 400. At the present time, Alloy C-22 and A516 G4 55 are favored

  6. Performance Evaluation and Modelling of Container Terminals

    Science.gov (United States)

    Venkatasubbaiah, K.; Rao, K. Narayana; Rao, M. Malleswara; Challa, Suresh

    2018-02-01

    The present paper evaluates and analyzes the performance of 28 container terminals of south East Asia through data envelopment analysis (DEA), principal component analysis (PCA) and hybrid method of DEA-PCA. DEA technique is utilized to identify efficient decision making unit (DMU)s and to rank DMUs in a peer appraisal mode. PCA is a multivariate statistical method to evaluate the performance of container terminals. In hybrid method, DEA is integrated with PCA to arrive the ranking of container terminals. Based on the composite ranking, performance modelling and optimization of container terminals is carried out through response surface methodology (RSM).

  7. CONTAIN assessment of the NUPEC mixing experiments

    International Nuclear Information System (INIS)

    Stamps, D.W.

    1995-08-01

    The ability of the CONTAIN code to predict the thermal hydraulics of five experiments performed in the NUPEC 1/4-scale model containment was assessed. These experiments simulated severe accident conditions in a nuclear power plant in which helium (as a nonflammable substitute for hydrogen) and steam were coinjected at different locations in the facility with and without the concurrent injection of water sprays in the dome. Helium concentrations, gas temperatures and pressures, and wall temperatures were predicted and compared with the data. The use of different flow solvers, nodalization schemes, and analysis methods for the treatment of water sprays was emphasized. As a result, a general procedure was suggested for lumped-parameter code analyses of problems in which the thermal hydraulics are dominated by water sprays

  8. Performance of particulate containment at nanotechnology workplaces

    International Nuclear Information System (INIS)

    Lo, Li-Ming; Tsai, Candace S.-J.; Dunn, Kevin H.; Hammond, Duane; Marlow, David; Topmiller, Jennifer; Ellenbecker, Michael

    2015-01-01

    The evaluation of engineering controls for the production or use of carbon nanotubes (CNTs) was investigated at two facilities. These control assessments are necessary to evaluate the current status of control performance and to develop proper control strategies for these workplaces. The control systems evaluated in these studies included ventilated enclosures, exterior hoods, and exhaust filtration systems. Activity-based monitoring with direct-reading instruments and filter sampling for microscopy analysis were used to evaluate the effectiveness of control measures at study sites. Our study results showed that weighing CNTs inside the biological safety cabinet can have a 37 % reduction on the particle concentration in the worker’s breathing zone, and produce a 42 % lower area concentration outside the enclosure. The ventilated enclosures used to reduce fugitive emissions from the production furnaces exhibited good containment characteristics when closed, but they failed to contain emissions effectively when opened during product removal/harvesting. The exhaust filtration systems employed for exhausting these ventilated enclosures did not provide promised collection efficiencies for removing engineered nanomaterials from furnace exhaust. The exterior hoods were found to be a challenge for controlling emissions from machining nanocomposites: the downdraft hood effectively contained and removed particles released from the manual cutting process, but using the canopy hood for powered cutting of nanocomposites created 15–20 % higher ultrafine (<500 nm) particle concentrations at the source and at the worker’s breathing zone. The microscopy analysis showed that CNTs can only be found at production sources but not at the worker breathing zones during the tasks monitored

  9. Performance of particulate containment at nanotechnology workplaces

    Energy Technology Data Exchange (ETDEWEB)

    Lo, Li-Ming, E-mail: LLo@cdc.gov [National Institute for Occupational Safety and Health, Centers for Disease Control and Prevention (United States); Tsai, Candace S.-J. [Purdue University (United States); Dunn, Kevin H.; Hammond, Duane; Marlow, David; Topmiller, Jennifer [National Institute for Occupational Safety and Health, Centers for Disease Control and Prevention (United States); Ellenbecker, Michael [University of Massachusetts Lowell (United States)

    2015-11-15

    The evaluation of engineering controls for the production or use of carbon nanotubes (CNTs) was investigated at two facilities. These control assessments are necessary to evaluate the current status of control performance and to develop proper control strategies for these workplaces. The control systems evaluated in these studies included ventilated enclosures, exterior hoods, and exhaust filtration systems. Activity-based monitoring with direct-reading instruments and filter sampling for microscopy analysis were used to evaluate the effectiveness of control measures at study sites. Our study results showed that weighing CNTs inside the biological safety cabinet can have a 37 % reduction on the particle concentration in the worker’s breathing zone, and produce a 42 % lower area concentration outside the enclosure. The ventilated enclosures used to reduce fugitive emissions from the production furnaces exhibited good containment characteristics when closed, but they failed to contain emissions effectively when opened during product removal/harvesting. The exhaust filtration systems employed for exhausting these ventilated enclosures did not provide promised collection efficiencies for removing engineered nanomaterials from furnace exhaust. The exterior hoods were found to be a challenge for controlling emissions from machining nanocomposites: the downdraft hood effectively contained and removed particles released from the manual cutting process, but using the canopy hood for powered cutting of nanocomposites created 15–20 % higher ultrafine (<500 nm) particle concentrations at the source and at the worker’s breathing zone. The microscopy analysis showed that CNTs can only be found at production sources but not at the worker breathing zones during the tasks monitored.

  10. Performance of Sequoyah Containment Anchorage System

    International Nuclear Information System (INIS)

    Fanous, F.; Greimann, L.; Wassef, W.; Bluhm, D.

    1993-01-01

    Deformation of a steel containment anchorage system during a severe accident may result in a leakage path at the containment boundaries. Current design criteria are based on either ductile or brittle failure modes of headed bolts that do not account for factors such as cracking of the containment basemat or deformation of the anchor bolt that may affect the behavior of the containment anchorage system. The purpose of this study was to investigate the performance of a typical ice condenser containment's anchorage system. This was accomplished by analyzing the Sequoyah Containment Anchorage System. Based on a strength of materials approach and assuming that the anchor bolts are resisting the uplift caused by the internal pressure, one can estimate that the failure of the anchor bolts would occur at a containment pressure of 79 psig. To verify these results and to calibrate the strength of materials equation, the Sequoyah containment anchorage system was analyzed with the ABAQUS program using a three-dimensional, finite-element model. The model included portions of the steel containment building, shield building, anchor bolt assembly, reinforced concrete mat and soil foundation material

  11. Assessment of energy performance and air pollutant emissions in a diesel engine generator fueled with water-containing ethanol-biodiesel-diesel blend of fuels

    International Nuclear Information System (INIS)

    Lee, Wen-Jhy; Liu, Yi-Cheng; Mwangi, Francis Kimani; Chen, Wei-Hsin; Lin, Sheng-Lun; Fukushima, Yasuhiro; Liao, Chao-Ning; Wang, Lin-Chi

    2011-01-01

    Biomass based oxygenated fuels have been identified as possible replacement of fossil fuel due to pollutant emission reduction and decrease in over-reliance on fossil fuel energy. In this study, 4 v% water-containing ethanol was mixed with (65-90%) diesel using (5-30%) biodiesel (BD) and 1 v% butanol as stabilizer and co-solvent respectively. The fuels were tested against those of biodiesel-diesel fuel blends to investigate the effect of addition of water-containing ethanol for their energy efficiencies and pollutant emissions in a diesel-fueled engine generator. Experimental results indicated that the fuel blend mix containing 4 v% of water-containing ethanol, 1 v% butanol and 5-30 v% of biodiesel yielded stable blends after 30 days standing. BD1041 blend of fuel, which composed of 10 v% biodiesel, 4 v% of water-containing ethanol and 1 v% butanol demonstrated -0.45 to 1.6% increase in brake-specific fuel consumption (BSFC, mL kW -1 h -1 ) as compared to conventional diesel. The better engine performance of BD1041 was as a result of complete combustion, and lower reaction temperature based on the water cooling effect, which reduced emissions to 2.8-6.0% for NO x , 12.6-23.7% particulate matter (PM), 20.4-23.8% total polycyclic aromatic hydrocarbons (PAHs), and 30.8-42.9% total BaPeq between idle mode and 3.2 kW power output of the diesel engine generator. The study indicated that blending diesel with water-containing ethanol could achieve the goal of more green sustainability. -- Highlights: → Water-containing ethanol was mixed with diesel using biodiesel and butanol as stabilizer and co-solvent, respectively. → Fuel blends with 4 v% water-containing ethanol, 1 v% butanol, 5-30 v% biodiesel and conventional diesel yielded a stable blended fuel after more than 30 days. → Due to more complete combustion and water quench effect, target fuel BD1041 was gave good energy performance and significant reduction of PM, NO x , total PAH and total BaPeq emissions.

  12. Perspectives on containment performance improvement based on the IPEs

    Energy Technology Data Exchange (ETDEWEB)

    Lehner, J.R.; Lin, C.C.; Pratt, W.T. [Brookhaven National Lab., Upton, NY (United States)] [and others

    1995-04-01

    Generic Letter 88-20, {open_quotes}Individual Plant Examination (IPE) for Severe Accident Vulnerabilities - 10CFR 50.54(f),{close_quotes} was issued by the NRC on November 23, 1988. In addition to assessing the core damage frequency from severe accidents, licensees were requested to report the results of their analyses regarding containment performance. Supplements to the Generic Letter forwarded technical insights obtained by the NRC staff through its Containment Performance Improvement (CPI) program. At this time, most of the IPEs have been submitted by the licensees. In a follow-on effort to support regulatory activities, the NRC staff with assistance from Brookhaven National Laboratory, has initiated a program involving a global examination of the containment performance results documented in the IPEs. The objective is to identify insights of potential generic safety significance relative to plant design, operation and maintenance, as well as to assess response to the previously forwarded CPI insights. The containment performance results of the IPEs are being categorized for commonalities and differences for different reactor and containment types. Preliminary results show that not only differences in plant design but also the methods, data, boundary conditions, and assumptions used in the different IPEs have a major impact on the containment performance results obtained. This paper presents preliminary results regarding the differences in containment performance observed in the IPEs and discusses some of the underlying reasons for these differences.

  13. Containment concepts assessment for the SEAFP reactor

    International Nuclear Information System (INIS)

    Di Pace, L.; Natalizio, A.

    2000-01-01

    A simple methodology has been developed for making relative comparisons of potential containment designs for future fusion reactors. The assessment methodology requires only conceptual design information. The application of this methodology, at the early stages of a fusion reactor design, provides designers useful information regarding the suitability of various containment designs and design features. Because the radiation hazard from the operation of future fusion power reactors is expected to be low, the containment design, in addition to public safety, needs to take into account worker safety considerations, as well as factors important to the reliable and economical operation of the power plant. Several containment concepts have been assessed with a methodology that takes into account public safety, worker safety, operability and maintainability as well as cost. This paper describes this methodology and presents the results of the assessment. The paper concludes that, to obtain a containment design that is optimised with respect to safety, operational and cost factors, designers should focus on a containment that is conceptually simple-that is, one utilising a single, large containment building without relying on special features such as expansion volumes, pressure suppression pools or spray systems

  14. Process of performance assessment

    International Nuclear Information System (INIS)

    King, C.M.; Halford, D.K.

    1987-01-01

    Performance assessment is the process used to evaluate the environmental consequences of disposal of radioactive waste in the biosphere. An introductory review of the subject is presented. Emphasis is placed on the process of performance assessment from the standpoint of defining the process. Performance assessment, from evolving experience at DOE sites, has short-term and long-term subprograms, the components of which are discussed. The role of mathematical modeling in performance assessment is addressed including the pros and cons of current approaches. Finally, the system/site/technology issues as the focal point of this symposium are reviewed

  15. TURVA-2012: Performance assessment

    International Nuclear Information System (INIS)

    Hellae, Pirjo; Snellman, Margit; Marcos, Nuria; Pastina, Barbara; Smith, Paul; Koskinen, Kari

    2014-01-01

    TURVA-2012 is Posiva's safety case in support of the Preliminary Safety Analysis Report (PSAR) and application for a construction licence for a repository for disposal of spent nuclear fuel at the Olkiluoto site in south-western Finland. Posiva's safety concept is based on long-term isolation and containment, which is achieved through a robust engineered barrier system (EBS) design and favourable geological conditions at the repository site. The reference design considered in the TURVA-2012 safety case is the KBS-3V design, with the EBS consisting of a copper-iron canister, a buffer of swelling clay material, a backfill in the deposition tunnels of low-permeability material and closure of the central tunnels and other underground openings. The host rock acts as a natural barrier. Each barrier contributes to safety through one or more safety function. The conditions needed for the barriers to fulfil their respective safety functions are expressed in terms of performance targets for the EBS and the target properties for the host rock. The performance assessment (Posiva, 2013), which is a key component of TURVA-2012, analyses the ability of the repository system to provide containment and isolation of the spent nuclear fuel during the long-term evolution of the system and the site. The conditions needed for the barriers to fulfil their respective safety functions are expressed in terms of performance targets for the engineered barriers and target properties for the host rock, for example properties related to the corrosion resistance and mechanical strength of the canister as well as groundwater flow and composition. The analyses take into account the uncertainties in the initial state, the subsequent thermal, hydraulic, mechanical and chemical evolution of the repository system and uncertainties in the evolution. The conclusions of the performance assessment are based mostly on the output of key modelling activities. Whenever modelling is not possible the conclusions

  16. Performance-based containment leakage testing

    International Nuclear Information System (INIS)

    Cybulskis, P.

    1995-01-01

    The U.S. Nuclear Regulatory Commission (NRC) is reviewing regulatory requirements in an effort to revise those that are marginal to safety but impose significant burdens on licensees. Identification of requirements marginal to safety and development and evaluation of alternatives utilize the NRC safety goals and insights from probabilistic risk assessments (PRAs). Since earlier studies found design-basis containment leakage to be a minor contributor to reactor accident risk, containment leakage testing has been selected as a candidate for change in regulations. This paper summarizes the technical analyses supporting the NRC proposal to amend Appendix J of 10 CFR Part 50 as its first effort to decrease unnecessary regulatory burdens on licensees

  17. AP1000 Containment Design and Safety Assessment

    International Nuclear Information System (INIS)

    Wright, Richard F.; Ofstun, Richard P.; Bachere, Sebastien

    2002-01-01

    The AP1000 is an up-rated version of the AP600 passive plant design that recently received final design certification from the US NRC. Like AP600, the AP1000 is a two-loop, pressurized water reactor featuring passive core cooling and passive containment safety systems. One key safety feature of the AP1000 is the passive containment cooling system which maintains containment integrity in the event of a design basis accident. This system utilizes a high strength, steel containment vessel inside a concrete shield building. In the event of a pipe break inside containment, a high pressure signal actuates valves which allow water to drain from a storage tank atop the shield building. Water is applied to the top of the containment shell, and evaporates, thereby removing heat. An air flow path is formed between the shield building and the containment to aid in the evaporation and is exhausted through a chimney at the top of the shield building. Extensive testing and analysis of this system was performed as part of the AP600 design certification process. The AP1000 containment has been designed to provide increased safety margin despite the increased reactor power. The containment volume was increased to accommodate the larger steam generators, and to provide increased margin for containment pressure response to design basis events. The containment design pressure was increased from AP600 by increasing the shell thickness and by utilizing high strength steel. The passive containment cooling system water capacity has been increased and the water application rate has been scaled to the higher decay heat level. The net result is higher margins to the containment design pressure limit than were calculated for AP600 for all design basis events. (authors)

  18. Simplified dynamic buckling assessment of steel containments

    International Nuclear Information System (INIS)

    Farrar, C.R.; Duffey, T.A.; Renick, D.H.

    1993-01-01

    A simplified, three-degree-of-freedom analytical procedure for performing a response spectrum buckling analysis of a thin containment shell is developed. Two numerical examples with R/t values which bound many existing steel containments are used to illustrate the procedure. The role of damping on incipient buckling acceleration level is evaluated for a regulatory seismic spectrum using the two numerical examples. The zero-period acceleration level that causes incipient buckling in either of the two containments increases 31% when damping is increased from 1% to 4% of critical. Comparisons with finite element results on incipient buckling levels are favorable

  19. Hydrogen burn assessment with the CONTAIN code

    International Nuclear Information System (INIS)

    van Rij, H.M.

    1986-01-01

    The CONTAIN computer code was developed at Sandia National Laboratories, under contract to the US Nuclear Regulatory Commission (NRC). The code is intended for calculations of containment loads during severe accidents and for prediction of the radioactive source term in the event that the containment leaks or fails. A strong point of the CONTAIN code is the continuous interaction of the thermal-hydraulics phenomena, aerosol behavior and fission product behavior. The CONTAIN code can be used for Light Water Reactors as well as Liquid Metal Reactors. In order to evaluate the CONTAIN code on its merits, comparisons between the code and experiments must be made. In this paper, CONTAIN calculations for the hydrogen burn experiments, carried out at the Nevada Test Site (NTS), are presented and compared with the experimental data. In the Large-Scale Hydrogen Combustion Facility at the NTS, 21 tests have been carried out. These tests were sponsored by the NRC and the Electric Power Research Institute (EPRI). The tests, carried out by EG and G, were performed in a spherical vessel 16 m in diameter with a design pressure of 700 kPa, substantially higher than that of most commercial nuclear containment buildings

  20. Assessment of integrity of structures containing cracks

    International Nuclear Information System (INIS)

    Townley, C.H.A.

    1976-01-01

    The object of the investigations is to provide a method of assessing the safety and integrity of structures containing cracklike defects. Estimated load at which the cracked structure will fail is compared with the highest load likely to be applied in service

  1. Assessment of high performance concrete containing fly ash and calcium nitrite based corrosion inhibitor as a mean to prevent the corrosion of reinforcing steel

    International Nuclear Information System (INIS)

    Montes-García, P; Jiménez-Quero, V; López-Calvo, H

    2015-01-01

    This research analyses the effectiveness of the water-to-cement ratio (w/c), fly ash and a calcium nitrite based corrosion inhibitor to prevent the corrosion of reinforcing steel embedded in high performance concrete. The interactive effect between the inhibitor and fly ash was evaluated because the occurrence of a negative effect when both ingredients are added together in a concrete mixture has been reported. All the concrete mixtures studied in this investigation had 8.2% of silica fume. Twenty seven prismatic concrete specimens were fabricated with dimensions of 55 × 230 × 300 mm each containing two steel rods embedded for the purpose of corrosion monitoring. The specimens were exposed to a simulated marine environment with two daily cycles of wetting and drying for one year. To evaluate the deterioration of the specimens corrosion potentials and linear polarization resistance tests were carried out. The results indicate that the use of a low w/c, the addition of fly ash and the addition of the corrosion inhibitor contributed to the reduction of the corrosion of steel in the concrete specimens. The results further suggest that the combination of fly ash and corrosion inhibitor does not promote the deterioration of the concrete matrix

  2. Computer aided probabilistic assessment of containment integrity

    International Nuclear Information System (INIS)

    Tsai, J.C.; Touchton, R.A.

    1984-01-01

    In the probabilistic risk assessment (PRA) of a nuclear power plant, there are three probability-based techniques which are widely used for event sequence frequency quantification (including nodal probability estimation). These three techniques are the event tree analysis, the fault tree analysis and the Bayesian approach for database development. In the barrier analysis for assessing radionuclide release to the environment in a PRA study, these techniques are employed to a greater extent in estimating conditions which could lead to failure of the fuel cladding and the reactor coolant system (RCS) pressure boundary, but to a lesser degree in the containment pressure boundary failure analysis. The main reason is that containment issues are currently still in a state of flux. In this paper, the authors describe briefly the computer programs currently used by the nuclear industry to do event tree analyses, fault tree analyses and the Bayesian update. The authors discuss how these computer aided probabilistic techniques might be adopted for failure analysis of the containment pressure boundary

  3. Assessment of enzyme supplementation on growth performance and apparent nutrient digestibility in diets containing undecorticated sunflower seed meal in layer chicks.

    Science.gov (United States)

    Fafiolu, A O; Oduguwa, O O; Jegede, A V; Tukura, C C; Olarotimi, I D; Teniola, A A; Alabi, J O

    2015-08-01

    Six hundred and forty one-day-old layer chicks were used to investigate the effect of replacing soybean meal with undecorticated sunflower seed meal protein for protein at 0, 25, 50, and 75% levels. Diets were without enzyme supplementation or with enzyme supplementation with four replications of twenty birds. Growth performance and nutrient utilization were determined. Proximate composition of the undecorticated sunflower seed meal used revealed that undecorticated sunflower seed meal contained 925.9, 204.5, 336.2, 215.1, 52.0 and 192.2g/kg dry matter, crude protein, ether extract, crude fibre, ash and soluble carbohydrates, respectively. Results showed that the final weight of 484.4 g/bird was obtained for birds on 75% undecorticated sunflower seed meal diet, while the lowest value of 472.2g/bird was obtained for birds on 25% undecorticated sunflower seed meal diet. Weight gain per bird per day was not significantly (P > 0.05) affected as the level of undecorticated sunflower seed meal increased in the diets. Feed intake per bird per day increased (P meal inclusion in the diet. However, enzyme supplementation of the diets showed marked (P meal inclusion in the diet while crude protein digestibility progressively reduced (P meal increased in the diet. Ash digestibility values were, however, increased (P meal increased in the diets. Birds on enzyme-supplemented diets consistently showed superior (P meal in the diets of layer chicks showed a similar body weight gain/bird/day with the control. Undecorticated sunflower seed meal used in this study is a good source of crude protein, ether extract, and amino acids and had the potential to serve as feeding stuffs as replacement for soybeans. The nutritive value of undecorticated sunflower seed meal was improved for layer chicks with exogenous enzyme supplementation. © 2015 Poultry Science Association Inc.

  4. Performance of containment of Indian PHWR

    International Nuclear Information System (INIS)

    Mohan, Nalini; Ghadge, S.G.; Bajaj, S.S.

    2006-01-01

    This paper summarizes the various requirements and activities relevant to the testing of containment system of Indian Pressurized Heavy Water Reactor (PHWR). All Indian PHWR containments are constructed from concrete either reinforced or prestressed or a combination of both and lined with polymeric coating based on Epoxy or Vinyl in order to achieve the leak tightness necessary from the radiological considerations following an accident. The current concept includes a complete double containment (except the base raft) extended to all penetrations and some of the pipings (those open to the containment atmosphere). The primary containment fitted with a passive pressure suppression system is enveloped in the secondary containment (confinement) where slight vacuum is maintained during normal operation as well as post accident condition. The Integrated leakage Rate Test (ILRT) conducted so far on the containment indicate that the overall leakages from the containment are lower than those necessary to meet the radiological limits following a postulated accident and interception of leakages by secondary containment as per design. The details of the, tests, repairs carried out and observations are given in this paper. The experience of ILRT also indicate improvement in leak tightness in many areas. (author)

  5. Assessing Scientific Performance.

    Science.gov (United States)

    Weiner, John M.; And Others

    1984-01-01

    A method for assessing scientific performance based on relationships displayed numerically in published documents is proposed and illustrated using published documents in pediatric oncology for the period 1979-1982. Contributions of a major clinical investigations group, the Childrens Cancer Study Group, are analyzed. Twenty-nine references are…

  6. Performance assessment calculational exercises

    International Nuclear Information System (INIS)

    Barnard, R.W.; Dockery, H.A.

    1990-01-01

    The Performance Assessment Calculational Exercises (PACE) are an ongoing effort coordinated by Yucca Mountain Project Office. The objectives of fiscal year 1990 work, termed PACE-90, as outlined in the Department of Energy Performance Assessment (PA) Implementation Plan were to develop PA capabilities among Yucca Mountain Project (YMP) participants by calculating performance of a Yucca Mountain (YM) repository under ''expected'' and also ''disturbed'' conditions, to identify critical elements and processes necessary to assess the performance of YM, and to perform sensitivity studies on key parameters. It was expected that the PACE problems would aid in development of conceptual models and eventual evaluation of site data. The PACE-90 participants calculated transport of a selected set of radionuclides through a portion of Yucca Mountain for a period of 100,000 years. Results include analyses of fluid-flow profiles, development of a source term for radionuclide release, and simulations of contaminant transport in the fluid-flow field. Later work included development of a problem definition for perturbations to the originally modeled conditions and for some parametric sensitivity studies. 3 refs

  7. Context for performance assessment

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1997-01-01

    In developing its recommendations on performance assessment for disposal of low-level radioactive waste, Scientific committee 87-3 of the National Council on Radiation Protection and Measurements (NCRP) has considered a number of topics that provide a context for the development of suitable approaches to performance assessment. This paper summarizes the Committee' discussions on these topics, including (1) the definition of low-level waste and its sources and properties, as they affect the variety of wastes that must be considered, (2) fundamental objectives and principles of radioactive waste disposal and their application to low-level waste, (3) current performance objectives for low-level waste disposal in the US, with particular emphasis on such unresolved issues of importance to performance assessment as the time frame for compliance, requirements for protection of groundwater and surface water, inclusion of doses from radon, demonstrating compliance with fixed performance objectives using highly uncertain model projections, and application of the principle that releases to the environment should be maintained as low as reasonably achievable (ALARA), (4) the role of active and passive institutional controls over disposal sites, (5) the role of the inadvertent human intruder in low-level waste disposal, (6) model validation and confidence in model outcomes, and (7) the concept of reasonable assurance of compliance

  8. Texas' performance assessment work

    International Nuclear Information System (INIS)

    Charbeneau, R.J.; Hertel, N.E.; Pollard, C.G.

    1990-01-01

    The Texas Low-Level Radioactive Waste Disposal Authority is completing two years of detailed on-site suitability studies of a potential low-level radioactive waste disposal site in Hudspeth County, Texas. The data from these studies have been used to estimate site specific parameters needed to do a performance assessment of the site. The radiological impacts of the site have been analyzed as required for a license application. The approach adopted for the performance assessment was to use simplified and yet conservative assumptions with regard to releases, radionuclide transport, and dose calculations. The methodologies employed in the performance assessment are reviewed in the paper. Rather than rely on a single computer code, a modular approach to the performance assessment was selected. The HELP code was used to calculate the infiltration rate through the trench covers and the amount of leachate released from this arid site. Individual pathway analyses used spreadsheet calculations. These calculations were compared with those from other computer models including CRRIS, INGDOS, PATHRAE, and MICROSHIELD copyright, and found to yield conservative estimates of the effective whole body dose. The greatest difficulty in performing the radiological assessment of the site was the selection of reasonable source terms for release into the environment. A surface water pathway is unreasonable for the site. Though also unlikely, the groundwater pathway with exposure through a site boundary well was found to yield the largest calculated dose. The more likely pathway including transport of leachate from the facility through the unsaturated zone and returning to the ground surface yields small doses. All calculated doses associated with normal releases of radioactivity are below the regulatory limits

  9. Energy performance assessment methodology

    Energy Technology Data Exchange (ETDEWEB)

    Platzer, W.J. [Fraunhofer Inst. for Solar Energy Systems, Freiburg (Germany)

    2006-01-15

    The energy performance of buildings are intimately connected to the energy performance of building envelopes. The better we understand the relation between the quality of the envelope and the energy consumption of the building, the better we can improve both. We have to consider not only heating but all service energies related to the human comfort in the building, such as cooling, ventilation, lighting as well. The complexity coming from this embracing approach is not to be underestimated. It is less and less possible to realted simple characteristic performance indicators of building envelopes (such as the U-value) to the overall energy performance. On the one hand much more paramters (e.g. light transmittance) come into the picture we have to assess the product quality in a multidimensional world. Secondly buildings more and more have to work on a narrow optimum: For an old, badly insulated building all solar gains are useful for a high-performance building with very good insulation and heat recovery systems in the ventilation overheating becomes more likely. Thus we have to control the solar gains, and sometimes we need high gains, sometimes low ones. And thirdly we see that the technology within the building and the user patterns and interactions as well influence the performance of a building envelope. The aim of this project within IEA Task27 was to improve our knowledge on the complex situation and also to give a principal approach how to assess the performance of the building envelope. The participants have contributed to this aim not pretending that we have reached the end. (au)

  10. Performance evaluation of microservices architectures using containers

    OpenAIRE

    Amaral, Marcelo; Polo, Jordà; Carrera Pérez, David; Mohomed, Iqbal; Unuvar, Merve; Steinder, Malgorzata

    2015-01-01

    Microservices architecture has started a new trend for application development for a number of reasons: (1) to reduce complexity by using tiny services; (2) to scale, remove and deploy parts of the system easily; (3) to improve flexibility to use different frameworks and tools; (4) to increase the overall scalability; and (5) to improve the resilience of the system. Containers have empowered the usage of microservices architectures by being lightweight, providing fast start-up times, and havi...

  11. Combined Life Cycle Assessment and Life Cycle Costing in the Eco-Care-Matrix: A case study on the performance of a modernized manufacturing system for glass containers

    DEFF Research Database (Denmark)

    Auer, Johannes; Bey, Niki; Schäfer, Johannes-Marius

    2017-01-01

    Cycle Assessment, as well as Life Cycle Costing (LCC). The results were then to be displayed in an Eco-Care-Matrix (ECM) in order to quantitatively visualize the improvements when comparing the updated manufacturing system to the previous one and they were to be discussed in terms of (i) ecodesign...

  12. Waste package performance assessment

    International Nuclear Information System (INIS)

    Lester, D.H.

    1981-01-01

    This paper describes work undertaken to assess the life-expectancy and post-failure nuclide release behavior of high-level and waste packages in a geologic repository. The work involved integrating models of individual phenomena (such as heat transfer, corrosion, package deformation, and nuclide transport) and using existing data to make estimates of post-emplacement behavior of waste packages. A package performance assessment code was developed to predict time to package failure in a flooded repository and subsequent transport of nuclides out of the leaking package. The model has been used to evaluate preliminary package designs. The results indicate, that within the limitation of model assumptions and data base, packages lasting a few hundreds of years could be developed. Very long lived packages may be possible but more comprehensive data are needed to confirm this

  13. Croton megalocarpus oil-fired micro-trigeneration prototype for remote and self-contained applications: experimental assessment of its performance and gaseous and particulate emissions

    Science.gov (United States)

    Wu, Dawei; Roskilly, Anthony P.; Yu, Hongdong

    2013-01-01

    According to the International Energy Agency's World Energy Outlook 2011, 60 per cent of the population in Africa, some 587 million people, mostly in sub-Saharan Africa, lacked access to electricity in 2009. We developed a 6.5 kWe micro-trigeneration prototype, on the basis of internal combustion engine with pure Croton megalocarpus oil (CMO) fuelling, which configures a distributed energy system to generate power, heating and cooling from a single sustainable fuel source for remote users. Croton megalocarpus is an indigenous tree in East and South Africa which has recently attracted lots of interests as a biofuel source because of its high oil-yield rate. The direct and local use of CMO, instead of CMO biodiesel converted by the transesterification process, minimizes the carbon footprints left behind because of the simple fuel production of CMO. The experimental assessment proves that the prototype fuelled with CMO achieves similar efficiency as with diesel. Also, with the elevation of the oil injection temperature, the gaseous and particulate emissions of CMO could be ameliorated to some extent as improvement of the atomization in the spray and the combustion in the engine cylinder. PMID:24427514

  14. Fracture mechanics performance of UF6 containers

    International Nuclear Information System (INIS)

    Gonzalez, M.E.; Iorio, A.F.; Crespi, J.C.

    1993-01-01

    The main purpose of this work was to determine the fracture mechanics performance of UF 6 transport cylinders type ANSI N14.1.30B, which was made from ASTM A 516 Grade 70 steel. It was assumed an internal surface axial crack subjected to stresses due to service, proof and transport accident loads. The KUMAR-GERMAN-SHIH elastoplastic methodology gave adequate results for crack depth estimation. The results validate the leak-before-break criteria for service and proof conditions but not for accident ones. In the last case a non-destructive examination must be done in order to assure the absence of defects larger than one third of the cylinder wall thickness. (Author)

  15. Corrosion assessment of dry fuel storage containers

    Energy Technology Data Exchange (ETDEWEB)

    Graves, C.E.

    1994-09-01

    The structural stability as a function of expected corrosion degradation of 75 dry fuel storage containers located in the 200 Area Low-Level Waste Burial Grounds was evaluated. These containers include 22 concrete burial containers, 13 55-gal (208-l) drums, and 40 Experimental Breeder Reactor II (EBR-II) transport/storage casks. All containers are buried beneath at least 48 in. of soil and a heavy plastic tarp with the exception of 35 of the EBR-II casks which are exposed to atmosphere. A literature review revealed that little general corrosion is expected and pitting corrosion of the carbon steel used as the exterior shell for all containers (with the exception of the concrete containers) will occur at a maximum rate of 3.5 mil/yr. Penetration from pitting of the exterior shell of the 208-l drums and EBR-II casks is calculated to occur after 18 and 71 years of burial, respectively. The internal construction beneath the shell would be expected to preclude containment breach, however, for the drums and casks. The estimates for structural failure of the external shells, large-scale shell deterioration due to corrosion, are considerably longer, 39 and 150 years respectively for the drums and casks. The concrete burial containers are expected to withstand a service life of 50 years.

  16. Georgia's Teacher Performance Assessment

    Science.gov (United States)

    Fenton, Anne Marie; Wetherington, Pamela

    2016-01-01

    Like most states, Georgia until recently depended on an assessment of content knowledge to award teaching licenses, along with a licensure recommendation from candidates' educator preparation programs. While the content assessment reflected candidates' grasp of subject matter, licensure decisions did not hinge on direct, statewide assessment of…

  17. A development of containment performance analysis methodology using GOTHIC code

    Energy Technology Data Exchange (ETDEWEB)

    Lee, B. C.; Yoon, J. I. [Future and Challenge Company, Seoul (Korea, Republic of); Byun, C. S.; Lee, J. Y. [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Lee, J. Y. [Seoul National University, Seoul (Korea, Republic of)

    2003-10-01

    In a circumstance that well-established containment pressure/temperature analysis code, CONTEMPT-LT treats the reactor containment as a single volume, this study introduces, as an alternative, the GOTHIC code for an usage on multi-compartmental containment performance analysis. With a developed GOTHIC methodology, its applicability is verified for containment performance analysis for Korean Nuclear Unit 1. The GOTHIC model for this plant is simply composed of 3 compartments including the reactor containment and RWST. In addition, the containment spray system and containment recirculation system are simulated. As a result of GOTHIC calculation, under the same assumptions and conditions as those in CONTEMPT-LT, the GOTHIC prediction shows a very good result; pressure and temperature transients including their peaks are nearly the same. It can be concluded that the GOTHIC could provide reasonable containment pressure and temperature responses if considering the inherent conservatism in CONTEMPT-LT code.

  18. A development of containment performance analysis methodology using GOTHIC code

    International Nuclear Information System (INIS)

    Lee, B. C.; Yoon, J. I.; Byun, C. S.; Lee, J. Y.; Lee, J. Y.

    2003-01-01

    In a circumstance that well-established containment pressure/temperature analysis code, CONTEMPT-LT treats the reactor containment as a single volume, this study introduces, as an alternative, the GOTHIC code for an usage on multi-compartmental containment performance analysis. With a developed GOTHIC methodology, its applicability is verified for containment performance analysis for Korean Nuclear Unit 1. The GOTHIC model for this plant is simply composed of 3 compartments including the reactor containment and RWST. In addition, the containment spray system and containment recirculation system are simulated. As a result of GOTHIC calculation, under the same assumptions and conditions as those in CONTEMPT-LT, the GOTHIC prediction shows a very good result; pressure and temperature transients including their peaks are nearly the same. It can be concluded that the GOTHIC could provide reasonable containment pressure and temperature responses if considering the inherent conservatism in CONTEMPT-LT code

  19. Containment performance of S-prism under severe BDB conditions

    International Nuclear Information System (INIS)

    Boardman, C.E.; Dubberley, A.E.; Hui, M.; Iwashige, K.

    2001-01-01

    S-PRISM is an advanced Fast Reactor plant design that utilizes compact modular pool-type reactors sized to enable factory fabrication and an affordable prototype test of a single Nuclear Steam Supply System (NSSS) for design certification at minimum cost and risk. Based on the success of the previous DOE sponsored Advanced Liquid Metal Reactor (ALMR) program GE has continued to develop and assess the technical viability and economic potential of an up-rated modular Fast Reactor called Super PRISM (S-PRISM). S-PRISM retains all of the key ALMR design features including passive reactor shutdown, passive shutdown heat removal, and passive reactor cavity cooling that were developed under an earlier DOE program. An additional feature of S-PRISM involves the use an innovative containment system that reduces the required design basis containment pressure by a factor of two through the use of a controlled venting system. The performance of this innovative containment system is evaluated and described in this paper. (author)

  20. MELCOR 1.8.3 assessment: CSE containment spray experiments

    International Nuclear Information System (INIS)

    Kmetyk, L.N.

    1994-12-01

    MELCOR is a fully integrated, engineering-level computer code, being developed at Sandia National Laboratories for the USNRC, that models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRS. As part, of an ongoing assessment program, the MELCOR computer code has been used to analyze a series of containment spray tests performed in the Containment Systems Experiment (CSE) vessel to evaluate the performance of aqueous sprays as a means of decontaminating containment atmospheres. Basecase MELCOR results are compared with test data, and a number of sensitivity studies on input modelling parameters and options in both the spray package and the associated aerosol washout and atmosphere decontamination by sprays modelled in the radionuclide package have been done. Time-step and machine-dependency calculations were done to identify whether any numeric effects exist in these CSE assessment analyses. A significant time-step dependency due to an error in the spray package coding was identified and eliminated. A number of other code deficiencies and inconveniences also are noted

  1. Assessing biosafety of GM plants containing lectins

    DEFF Research Database (Denmark)

    Poulsen, Morten; Pedersen, Jan W.

    2010-01-01

    insects. However, since the cry genes are not active against all insects, e.g. sap-sucking insects, other genes coding for proteins such as lectins show promise of complementing the cry genes for insect resistance. As with other novel plants, lectin-expressing plants will need to be assessed...... for their potential risks to human and animal health and the environment. The expressed lectin protein should be assessed on its own for potential toxicity and allergenicity as for any other new protein. Although not many lectins have been thoroughly tested for their toxicity, our evaluation suggests that most...... of the lectins that are potentially useful for insect resistance will pose no health risk in genetically modified (GM) plants. Since some lectins are known for their toxicity to humans, the insertion of lectin genes in food crop plants will have to be assessed carefully. It is expected that in some cases...

  2. H1259 Container Foams: Performance Data on Aged Materials

    International Nuclear Information System (INIS)

    Linda Domeier

    2002-01-01

    Samples of the three cushioning foams used in the H1259 weapon storage container were obtained in 1997, 1998, 2000 and 2001 and tested for density, compression set and compressive strength using the same procedures specified for acceptance testing. Foams from six containers, all about 30 years old and located at Pantex, were evaluated. The bottom cushioning foam is a General Plastics polyurethane foam and the two side pads are rebonded polyurethane foams. All the tests were carried out at room temperature. When compared to the original acceptance requirements the foams were generally in-spec for density and compressive strength at 10% strain and were generally out-of-spec for compression set and compressive strength at 50% strain. Significant variability was noted in the performance of each foam sample and even more in the container-to-container foam performance. The container-to-container variability remains the major unknown in predicting the long-term suitability of these containers for continued use. The performance of the critical bottom cushion foams was generally more uniform and closer to the specified performance than that of the rebonded foams. It was judged that all the foams were adequate for continued use as storage container foams (not shipping) under controlled conditions to mitigate temperature extremes or high impact. This archived information is important in evaluations of the continued suitability for weapon storage use of the H1259 containers and other containers using the same foam cushions

  3. OLEM Performance Assessment Information

    Data.gov (United States)

    U.S. Environmental Protection Agency — This asset includes a variety of data sets that measure the performance of Office of Land and Emergency Management (OLEM) programs in support of the Office of the...

  4. Simply Performance Assessment

    Science.gov (United States)

    McLaughlin, Cheryl A.; McLaughlin, Felecia C.; Pringle, Rose M.

    2013-01-01

    This article presents the experiences of Miss Felecia McLaughlin, a fourth-grade teacher from the island of Jamaica who used the model proposed by Bass et al. (2009) to assess conceptual understanding of four of the six types of simple machines while encouraging collaboration through the creation of learning teams. Students had an opportunity to…

  5. Biologic assessment of copper-containing amalgams.

    Science.gov (United States)

    Mjor, I A; Eriksen, H M; Haugen, E; Skogedal, O

    1977-12-01

    In order to reduce creep and avoid marginal fractures in amalgam restorations, new alloys containing higher proportions of copper have been introduced. Fillings of these materials were placed in cavities prepared in the deciduous teeth of monkeys or placed in polyethylene tubes and implanted subcutaneously in rats. Conventional silver/tin alloys and zinc oxide eugenol cement were used as reference materials. Despite limitations due to the varying depths of cavities and the small number of animals involved it was concluded that the high copper alloys caused more severe pulp damage than the other materials studied. In the implantation studies many of the high copper specimens were exfoliated before the end of the experimental period. It is concluded that in deep cavities these materials require the use of a non-toxic base or lining material although as they are commonly used in young children's teeth the placement of linings and the isolation of the cavity pose problems.

  6. Studies of severe accidents in light water reactors. Containment performance

    International Nuclear Information System (INIS)

    Hayns, M.R.; Phillips, D.W.; Young, R.L.D.

    1987-01-01

    The containment system of a LWR is an obvious component of the plant which performs an important safety function in preventing the release of fission products to the environment in the event of design basis accidents. With over 260 LWRs in service worldwide, and others still under construction, there is a considerable diversity of containment types and combinations of containment safeguards systems. All of these satisfy local regulatory requirements which are principally aimed at the design basis accidents, and these requirements naturally have a considerable uniformity. However, their design diversity becomes more relevant to the performance of the containment in severe accident conditions, and this aspect of containment performance is reviewed in this paper. The ability of the containment to mitigate severe accident consequences introduces the potential for accident management and recovery and this in turn points towards a range of new containment systems and concepts. PSA helps in judging these possibilities and in forming policies and procedures for accident management. It is perhaps in accident management that severe accident containment performance will be most beneficial in the future, and where additional effort in containment analysis will be focused

  7. Total System Performance Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Yong Soo; Kang, Chul Hyung; Lee, Youn Myoung; Han, Ji Woong; Choi, Jong Won; Hahn, Pil Soo; Park, Jeong Hwa; Jeong, Mi Seon

    2007-06-15

    Based on the KAERI FEP list developed through the previous studies, the KAERI FEP Encyclopedia has been developed. Current version is 1.0 which includes all relevant FEPs to compose of two references and all alternative scenarios. Many interaction FEPs between scenario defining FEP(SDF) are created throughout the study. FEPs are classified into many Integrated FEP(IFEP) which eventually become the elements of the RES matrix. The FEAS program one of the component of the KAERI's CYPRUS information system is added to develop the FEP, RES, AC, AMF and finally scenarios. It assists to create transparent way to deal with assessment from the stage of the planning of the R and D to the final stage of the external audit and regulatory body review. Even though MASCOT-K and compartment analysis codes such as AMBER, GoldSim and Ecolego are excellent for TSPA they by in heritage possess a certain limitation especially to identify a proper migration cross sectional area when a relatively big component intersects with a tiny one such as a fracture. It is truly 3D phenomena in nature. MDPSA code is developed which is expected to overcome limitations in compartment models while successfully deals with natural disruptive events. The R and D target for the TSPA is to develop the sufficient scenarios and their variation cases to understand the safety of KRS in every possible aspect. For this, reference scenarios, alternative scenarios covering engineered barrier failure and natural events are developed and assessed respectively for around 100 cases. The stylized template to assess the Korean reference biosphere is developed using the AMBER. Three critical groups, agricultural, freshwater and marine water fishing groups are identified to assess the DCF following the guidelines of ICRP. Based on the QA principles of T2R3, the web based QA system is developed using the procedures in the USNRC 10CFR50 Appendix B. The QA system is combined with the PAID and FEAS to create the comprehensive

  8. Total System Performance Assessment

    International Nuclear Information System (INIS)

    Hwang, Yong Soo; Kang, Chul Hyung; Lee, Youn Myoung; Han, Ji Woong; Choi, Jong Won; Hahn, Pil Soo; Park, Jeong Hwa; Jeong, Mi Seon

    2007-06-01

    Based on the KAERI FEP list developed through the previous studies, the KAERI FEP Encyclopedia has been developed. Current version is 1.0 which includes all relevant FEPs to compose of two references and all alternative scenarios. Many interaction FEPs between scenario defining FEP(SDF) are created throughout the study. FEPs are classified into many Integrated FEP(IFEP) which eventually become the elements of the RES matrix. The FEAS program one of the component of the KAERI's CYPRUS information system is added to develop the FEP, RES, AC, AMF and finally scenarios. It assists to create transparent way to deal with assessment from the stage of the planning of the R and D to the final stage of the external audit and regulatory body review. Even though MASCOT-K and compartment analysis codes such as AMBER, GoldSim and Ecolego are excellent for TSPA they by in heritage possess a certain limitation especially to identify a proper migration cross sectional area when a relatively big component intersects with a tiny one such as a fracture. It is truly 3D phenomena in nature. MDPSA code is developed which is expected to overcome limitations in compartment models while successfully deals with natural disruptive events. The R and D target for the TSPA is to develop the sufficient scenarios and their variation cases to understand the safety of KRS in every possible aspect. For this, reference scenarios, alternative scenarios covering engineered barrier failure and natural events are developed and assessed respectively for around 100 cases. The stylized template to assess the Korean reference biosphere is developed using the AMBER. Three critical groups, agricultural, freshwater and marine water fishing groups are identified to assess the DCF following the guidelines of ICRP. Based on the QA principles of T2R3, the web based QA system is developed using the procedures in the USNRC 10CFR50 Appendix B. The QA system is combined with the PAID and FEAS to create the comprehensive

  9. Total System Performance Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Yong Soo; Kang, Chul Hyung; Lee, Youn Myoung; Han, Ji Woong; Choi, Jong Won; Hahn, Pil Soo; Park, Jeong Hwa; Jeong, Mi Seon

    2007-06-15

    Based on the KAERI FEP list developed through the previous studies, the KAERI FEP Encyclopedia has been developed. Current version is 1.0 which includes all relevant FEPs to compose of two references and all alternative scenarios. Many interaction FEPs between scenario defining FEP(SDF) are created throughout the study. FEPs are classified into many Integrated FEP(IFEP) which eventually become the elements of the RES matrix. The FEAS program one of the component of the KAERI's CYPRUS information system is added to develop the FEP, RES, AC, AMF and finally scenarios. It assists to create transparent way to deal with assessment from the stage of the planning of the R and D to the final stage of the external audit and regulatory body review. Even though MASCOT-K and compartment analysis codes such as AMBER, GoldSim and Ecolego are excellent for TSPA they by in heritage possess a certain limitation especially to identify a proper migration cross sectional area when a relatively big component intersects with a tiny one such as a fracture. It is truly 3D phenomena in nature. MDPSA code is developed which is expected to overcome limitations in compartment models while successfully deals with natural disruptive events. The R and D target for the TSPA is to develop the sufficient scenarios and their variation cases to understand the safety of KRS in every possible aspect. For this, reference scenarios, alternative scenarios covering engineered barrier failure and natural events are developed and assessed respectively for around 100 cases. The stylized template to assess the Korean reference biosphere is developed using the AMBER. Three critical groups, agricultural, freshwater and marine water fishing groups are identified to assess the DCF following the guidelines of ICRP. Based on the QA principles of T2R3, the web based QA system is developed using the procedures in the USNRC 10CFR50 Appendix B. The QA system is combined with the PAID and FEAS to create the

  10. Containment performance evaluation for the GESSAR-II plant for seismic initiating events

    International Nuclear Information System (INIS)

    Shiu, K.K.; Chu, T.; Ludewig, H.; Pratt, W.T.

    1986-01-01

    As a part of the overall effort undertaken by Brookhaven National Laboratory (BNL) to review the GESSAR-II probabilistic risk assessment, an independent containment performance evaluation was performed using the containment event tree approach. This evaluation focused principally on those accident sequences which are initiated by seismic events. This paper reports the findings of this study. 1 ref

  11. Introduction to radiological performance assessment

    International Nuclear Information System (INIS)

    Moss, G.

    1995-02-01

    A radiological performance assessment is conducted to provide reasonable assurance that performance objectives for low-level radioactive waste (LLW) disposal will be met. Beginning in the early stages of development, a radiological performance assessment continues through the operational phase, and is instrumental in the postclosure of the facility. Fundamental differences exist in the regulation of commercial and defense LLW, but the radiological performance assessment process is essentially the same for both. The purpose of this document is to describe that process in a concise and straightforward manner. This document focuses on radiological performance assessment as it pertains to commercial LLW disposal, but is applicable to US Department of Energy sites as well. Included are discussions on performance objectives, site characterization, and how a performance assessment is conducted. A case study is used to illustrate how the process works as a whole. A bibliography is provided to assist in locating additional information

  12. The process of performance assessment

    International Nuclear Information System (INIS)

    King, C.M.; Halford, D.K.

    1986-01-01

    An introductory review of the subject of ''Performance Assessment'' will be presented. Emphasis will be placed on the process of performance assessment from the standpoint of defining the process. Performance assessment, from evolving experience at DOE sites, has short-term and long-term subprograms, the components of which will be discussed. The role of mathematical modeling in performance assessment will be addressed including the pros and cons of current approaches. Finally, the ''system/site/technology'' issues as the focal point of this symposium will be reviewed

  13. CONPAS 1.0 (CONtainment Performance Analysis System). User's manual

    International Nuclear Information System (INIS)

    Ahn, Kwang Il; Jin, Young Ho

    1996-04-01

    CONPAS (CONtainment Performance Analysis System) is a verified computer code package to integrate the numerical, graphical, and results-operation aspects of Level 2 probabilistic safety assessments (PSA) for nuclear power plants automatically under a PC window environment. Compared with the existing DOS-based computer codes for Level 2 PSA, the most important merit of the window-based computer code is that user can easily describe and quantify the accident progression models, and manipulate the resultant outputs in a variety of ways. As a main logic for accident progression analysis, CONPAS employs a concept of the small containment phenomenological event tree (CPET) helpful to trace out visually individual accident progressions and of the large supporting event tree (LSET) for its detailed quantification. For the integrated analysis of Level 2 PSA, the code utilizes four distinct, but closely related modules; (1) ET Editor for construction of several event tree models describing the accident progressions, (2) Computer for quantification of the constructed event trees and graphical display of the resultant outputs, (3) Text Editor for preparation of input decks for quanification and utilization of calculational results, and (4) Mechanistic Code Plotter for utilization of results obtained from severe accident analysis codes. Compared with other existing computer codes for Level 2 PSA, the CONPAS code provides several advanced features: computational aspects including systematic uncertainty analysis, importance analysis, sensitivity analysis and data interpretation, reporting aspects including tabling and graphic as well as user-friend interface. 10 refs. (Author) .new

  14. Two-Stage Performance Engineering of Container-based Virtualization

    Directory of Open Access Journals (Sweden)

    Zheng Li

    2018-02-01

    Full Text Available Cloud computing has become a compelling paradigm built on compute and storage virtualization technologies. The current virtualization solution in the Cloud widely relies on hypervisor-based technologies. Given the recent booming of the container ecosystem, the container-based virtualization starts receiving more attention for being a promising alternative. Although the container technologies are generally considered to be lightweight, no virtualization solution is ideally resource-free, and the corresponding performance overheads will lead to negative impacts on the quality of Cloud services. To facilitate understanding container technologies from the performance engineering’s perspective, we conducted two-stage performance investigations into Docker containers as a concrete example. At the first stage, we used a physical machine with “just-enough” resource as a baseline to investigate the performance overhead of a standalone Docker container against a standalone virtual machine (VM. With findings contrary to the related work, our evaluation results show that the virtualization’s performance overhead could vary not only on a feature-by-feature basis but also on a job-to-job basis. Moreover, the hypervisor-based technology does not come with higher performance overhead in every case. For example, Docker containers particularly exhibit lower QoS in terms of storage transaction speed. At the ongoing second stage, we employed a physical machine with “fair-enough” resource to implement a container-based MapReduce application and try to optimize its performance. In fact, this machine failed in affording VM-based MapReduce clusters in the same scale. The performance tuning results show that the effects of different optimization strategies could largely be related to the data characteristics. For example, LZO compression can bring the most significant performance improvement when dealing with text data in our case.

  15. Technology Performance Level Assessment Methodology.

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, Jesse D.; Bull, Diana L; Malins, Robert Joseph; Costello, Ronan Patrick; Aurelien Babarit; Kim Nielsen; Claudio Bittencourt Ferreira; Ben Kennedy; Kathryn Dykes; Jochem Weber

    2017-04-01

    The technology performance level (TPL) assessments can be applied at all technology development stages and associated technology readiness levels (TRLs). Even, and particularly, at low TRLs the TPL assessment is very effective as it, holistically, considers a wide range of WEC attributes that determine the techno-economic performance potential of the WEC farm when fully developed for commercial operation. The TPL assessment also highlights potential showstoppers at the earliest possible stage of the WEC technology development. Hence, the TPL assessment identifies the technology independent “performance requirements.” In order to achieve a successful solution, the entirety of the performance requirements within the TPL must be considered because, in the end, all the stakeholder needs must be achieved. The basis for performing a TPL assessment comes from the information provided in a dedicated format, the Technical Submission Form (TSF). The TSF requests information from the WEC developer that is required to answer the questions posed in the TPL assessment document.

  16. About Microservices, Containers and their Underestimated Impact on Network Performance

    OpenAIRE

    Kratzke, Nane

    2017-01-01

    Microservices are used to build complex applications composed of small, independent and highly decoupled processes. Recently, microservices are often mentioned in one breath with container technologies like Docker. That is why operating system virtualization experiences a renaissance in cloud computing. These approaches shall provide horizontally scalable, easily deployable systems and a high-performance alternative to hypervisors. Nevertheless, performance impacts of containers on top of hyp...

  17. Containment

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The primary mission of the Containment Group is to ensure that underground nuclear tests are satisfactorily contained. The main goal is the development of sound technical bases for containment-related methodology. Major areas of activity include siting, geologic description, emplacement hole stemming, and phenomenological predictions. Performance results of sanded gypsum concrete plugs on the Jefferson, Panamint, Cornucopia, Labquark, and Bodie events are given. Activities are also described in the following areas: computational capabilities site description, predictive modeling, and cavity-pressure measurement. Containment publications are listed. 8 references

  18. Reliability-based condition assessment of steel containment and liners

    International Nuclear Information System (INIS)

    Ellingwood, B.; Bhattacharya, B.; Zheng, R.

    1996-11-01

    Steel containments and liners in nuclear power plants may be exposed to aggressive environments that may cause their strength and stiffness to decrease during the plant service life. Among the factors recognized as having the potential to cause structural deterioration are uniform, pitting or crevice corrosion; fatigue, including crack initiation and propagation to fracture; elevated temperature; and irradiation. The evaluation of steel containments and liners for continued service must provide assurance that they are able to withstand future extreme loads during the service period with a level of reliability that is sufficient for public safety. Rational methodologies to provide such assurances can be developed using modern structural reliability analysis principles that take uncertainties in loading, strength, and degradation resulting from environmental factors into account. The research described in this report is in support of the Steel Containments and Liners Program being conducted for the US Nuclear Regulatory Commission by the Oak Ridge National Laboratory. The research demonstrates the feasibility of using reliability analysis as a tool for performing condition assessments and service life predictions of steel containments and liners. Mathematical models that describe time-dependent changes in steel due to aggressive environmental factors are identified, and statistical data supporting the use of these models in time-dependent reliability analysis are summarized. The analysis of steel containment fragility is described, and simple illustrations of the impact on reliability of structural degradation are provided. The role of nondestructive evaluation in time-dependent reliability analysis, both in terms of defect detection and sizing, is examined. A Markov model provides a tool for accounting for time-dependent changes in damage condition of a structural component or system. 151 refs

  19. Effects of diets containing alkali-treated Soybeans on performance ...

    African Journals Online (AJOL)

    Effects of diets containing alkali-treated Soybeans on performance traits, nutrient digestibility and cost benefits of broiler chickens. ... These factors accounted for the overall best performance recorded in 1% K2CO3 - treated soybeans which was closely followed by 1% Na2CO3 treated soybean base diets. Keywords: ...

  20. Methods for assessing NPP containment pressure boundary integrity

    International Nuclear Information System (INIS)

    Naus, D.J.; Ellingwood, B.R.; Graves, H.L.

    2004-01-01

    Research is being conducted to address aging of the containment pressure boundary in light-water reactor plants. Objectives of this research are to (1) understand the significant factors relating to corrosion occurrence, efficacy of inspection, and structural capacity reduction of steel containments and of liners of concrete containments; (2) provide the U.S. Nuclear Regulatory Commission (USNRC) reviewers a means of establishing current structural capacity margins or estimating future residual structural capacity margins for steel containments and concrete containments as limited by liner integrity; and (3) provide recommendations, as appropriate, on information to be requested of licensees for guidance that could be utilized by USNRC reviewers in assessing the seriousness of reported incidences of containment degradation. Activities include development of a degradation assessment methodology; reviews of techniques and methods for inspection and repair of containment metallic pressure boundaries; evaluation of candidate techniques for inspection of inaccessible regions of containment metallic pressure boundaries; establishment of a methodology for reliability-based condition assessments of steel containments and liners; and fragility assessments of steel containments with localized corrosion

  1. High temperature performance limit of containment system of transport cask

    International Nuclear Information System (INIS)

    Kato, Osamu; Saegusa, Toshiari

    1998-01-01

    The containment performance of a containment system using elastomer gaskets for transport casks under a high temperature and high pressure was clarified. Major results are as follows; (1) The deformation characteristics of the gaskets were represented by the compressive permanent strain rate (Dp). The temperature and time dependence was shown by Larson-Miller Parameter (LMP). (2) Generally, the high temperature performance limit is obtained by a value of LMP when the Dp value reaches 80%. However, the gaskets (FKM, VMQ, EPDM) used for real transport casks were not damaged and the containment performance was not deteriorated as a conservative condition. (3) Assuming that the service period of the gaskets for transport casks is 3 months or 1 year, the high temperature performance limit of the gasket made of fluorine rubber (FKM) is 202degC or 182degC, respectively, which includes safety margin. (author)

  2. Assessment of gas flammability in transuranic waste container

    International Nuclear Information System (INIS)

    Connolly, M.J.; Loehr, C.A.; Djordjevic, S.M.; Spangler, L.R.

    1995-01-01

    The Safety Analysis Report for the TRUPACT-II Shipping Package [Transuranic Package Transporter-II (TRUPACT-II) SARP] set limits for gas generation rates, wattage limits, and flammable volatile organic compound (VOC) concentrations in transuranic (TRU) waste containers that would be shipped to the Waste Isolation Pilot Plant (WIPP). Based on existing headspace gas data for drums stored at the Idaho National Engineering Laboratory (INEL) and the Rocky Flats Environmental Technology Site (RFETS), over 30 percent of the contact-handled TRU waste drums contain flammable VOC concentrations greater than the limit. Additional requirements may be imposed for emplacement of waste in the WIPP facility. The conditional no-migration determination (NMD) for the test phase of the facility required that flame tests be performed if significant levels of flammable VOCs were present in TRU waste containers. This paper describes an approach for investigating the potential flammability of TRU waste drums, which would increase the allowable concentrations of flammable VOCS. A flammability assessment methodology is presented that will allow more drums to be shipped to WIPP without treatment or repackaging and reduce the need for flame testing on drums. The approach includes experimental work to determine mixture lower explosive limits (MLEL) for the types of gas mixtures observed in TRU waste, a model for predicting the MLEL for mixtures of VOCS, hydrogen, and methane, and revised screening limits for total flammable VOCs concentrations and concentrations of hydrogen and methane using existing drum headspace gas data and the model predictions

  3. Performance Assessment National Review Group

    International Nuclear Information System (INIS)

    Lieberman, J.A.; Davis, S.N.; Harleman, D.R.F.

    1985-02-01

    Performance assessment involves predicting the potential radiological impact of a nuclear waste disposal system, taking into account all of the natural and engineered components of the system. It includes the analysis and evaluation of predicted system and component performance to determine compliance with regulatory performance criteria. In the context of the nuclear waste management program, performance assessment has five major purposes: to assist in the evaluation and selection of repository sites; to guide the research, development, and testing programs; to assist in the evaluation of repository designs; to assist in the evaluation of the design and performance of engineered barriers; and to show regulatory compliance and support repository licensing. Current performance assessment methodologies are still in the developmental stage. Only the simplest of bounding calculations have produced quantitative predictions of radionuclide releases. The methodologies require considerable extension and validation before they can provide answers suitable for project decisions and licensing. 135 refs., 9 figs., 1 tab

  4. Seismic damage assessment of reinforced concrete containment structures

    International Nuclear Information System (INIS)

    Cho, HoHyun; Koh, Hyun-Moo; Hyun, Chang-Hun; Kim, Moon-Soo; Shin, Hyun Mock

    2003-01-01

    This paper presents a procedure for assessing seismic damage of concrete containment structures using the nonlinear time-history numerical analysis. For this purpose, two kinds of damage index are introduced at finite element and structural levels. Nonlinear finite element analysis for the containment structure applies PSC shell elements using a layered approach leading to damage indices at finite element and structural levels, which are then used to assess the seismic damage of the containment structure. As an example of such seismic damage assessment, seismic damages of the containment structure of Wolsong I nuclear power plant in Korea are evaluated against 30 artificial earthquakes generated with a wide range of PGA according to US NRC regulatory guide 1.60. Structural responses and corresponding damage index according to the level of PGA and nonlinearity are investigated. It is also shown that the containment structure behaves elastically for earthquakes corresponding to or lower than DBE. (author)

  5. Analysis of Depressurization Performance in Containment of Wolsong NPP Unit 1 through Containment Filtered Venting System

    International Nuclear Information System (INIS)

    Lee, Sunghan; Kim, Jinhyuck; Suh, Nam Duk; Cho, Songwon

    2014-01-01

    Containment filtered venting system (CFVS) is designed to open and to close isolation valves passively by an operator. CFVS is operated when the containment pressure exceeds the design pressure (225 kPa(a)) and is closed when the containment pressure decreases below 151 kPa(a). The aim of this study is to analyze the depressurization performance of Wolsong unit 1 through CFVS during SBO. The thermal-hydraulic behavior in containment of Wolsong unit 1 was evaluated using the MELCOR 1.8.6 code developed at Sandia National Laboratories (SNL) for the U.S. Nuclear Regulatory Commission (NRC). In addition, in order to evaluate the effects of the CFVS according to the venting area, a sensitivity study depending on different venting area of the CFVS was conducted. Finally, an analysis of the effects of filtering and scrubbing of radioactive material for CFVS is important but not treated in this paper. The SBO accident is chosen to analyze the thermal-hydraulic behavior of Wolsong unit 1. During SBO, the analysis of CFVS affecting on the depressurization of the containment was conducted using MELCOR 1.8.6 code. Also, a sensitivity study was carried out to evaluate the depressurization performance according to the venting area of CFVS. The results show that the containment pressure is considerably decreased and the integrity of the containment could be maintained in case of CFVS operating. Therefore, CFVS has the capacity to keep the containment pressure below the design pressure during SBO. In addition, there are large differences in the containment pressure depending on venting area. We found that the decreasing rate of the pressure in the containment and water level in CFVS depends on the venting area. In the future, a proper requirement for CFVS sizing criteria according to accident scenarios such as LBLOCA, SBLOCA and SGTR, etc. should be evaluated in order to review the licensing for CFVS. Finally, analyses of aerosols, fission product, and radioactive material

  6. Structural Integrity Assessment of Reactor Containment Subjected to Aircraft Crash

    International Nuclear Information System (INIS)

    Kim, Junyong; Chang, Yoonsuk

    2013-01-01

    When an accident occurs at the NPP, containment building which acts as the last barrier should be assessed and analyzed structural integrity by internal loading or external loading. On many occasions that can occur in the containment internal such as LOCA(Loss Of Coolant Accident) are already reflected to design. Likewise, there are several kinds of accidents that may occur from the outside of containment such as earthquakes, hurricanes and strong wind. However, aircraft crash that at outside of containment is not reflected yet in domestic because NPP sites have been selected based on the probabilistic method. After intentional aircraft crash such as World Trade Center and Pentagon accident in US, social awareness for safety of infrastructure like NPP was raised world widely and it is time for assessment of aircraft crash in domestic. The object of this paper is assessment of reactor containment subjected to aircraft crash by FEM(Finite Element Method). In this paper, assessment of structural integrity of containment building subjected to certain aircraft crash was carried out. Verification of structure integrity of containment by intentional severe accident. Maximum stress 61.21MPa of horizontal shell crash does not penetrate containment. Research for more realistic results needed by steel reinforced concrete model

  7. Capacity assessment of concrete containment vessels subjected to aircraft impact

    International Nuclear Information System (INIS)

    Andonov, Anton; Kostov, Marin; Iliev, Alexander

    2015-01-01

    Highlights: • An approach to assess the containment capacity to aircraft impact via fragility curves is proposed. • Momentum over Area was defined as most suitable reference parameter to describe the aircraft load. • The effect of the impact induced damages on the containment pressure capacity has been studied. • The studied containment shows no reduction of the pressure capacity for the investigated scenarios. • The effectiveness of innovative protective structure against aircraft impact has been evaluated. - Abstract: The paper describes the procedure and the results from the assessment of the vulnerability of a generic pre-stressed containment structure subjected to a large commercial aircraft impact. Impacts of Boeing 737, Boeing 767 and Boeing 747 have been considered. The containment vulnerability is expressed by fragility curves based on the results of a number of nonlinear dynamic analyses. Three reference parameters have been considered as impact intensity measure in the fragility curve definition: peak impact force (PIF), peak impact pressure (PIP) and Momentum over Area (MoA). Conclusions on the most suitable reference parameter as well on the vulnerability of such containment vessels are drawn. The influence of the aircraft impact induced damages on the containment ultimate pressure capacity is also assessed and some preliminary conclusions on this are drawn. The paper also addresses a conceptual design of a protective structure able to decrease the containment vulnerability and provide a preliminary assessment of the applicability of such concept.

  8. Capacity assessment of concrete containment vessels subjected to aircraft impact

    Energy Technology Data Exchange (ETDEWEB)

    Andonov, Anton, E-mail: anton.andonov@mottmac.com; Kostov, Marin; Iliev, Alexander

    2015-12-15

    Highlights: • An approach to assess the containment capacity to aircraft impact via fragility curves is proposed. • Momentum over Area was defined as most suitable reference parameter to describe the aircraft load. • The effect of the impact induced damages on the containment pressure capacity has been studied. • The studied containment shows no reduction of the pressure capacity for the investigated scenarios. • The effectiveness of innovative protective structure against aircraft impact has been evaluated. - Abstract: The paper describes the procedure and the results from the assessment of the vulnerability of a generic pre-stressed containment structure subjected to a large commercial aircraft impact. Impacts of Boeing 737, Boeing 767 and Boeing 747 have been considered. The containment vulnerability is expressed by fragility curves based on the results of a number of nonlinear dynamic analyses. Three reference parameters have been considered as impact intensity measure in the fragility curve definition: peak impact force (PIF), peak impact pressure (PIP) and Momentum over Area (MoA). Conclusions on the most suitable reference parameter as well on the vulnerability of such containment vessels are drawn. The influence of the aircraft impact induced damages on the containment ultimate pressure capacity is also assessed and some preliminary conclusions on this are drawn. The paper also addresses a conceptual design of a protective structure able to decrease the containment vulnerability and provide a preliminary assessment of the applicability of such concept.

  9. Evaluation of disposal site geochemical performance using a containment factor

    International Nuclear Information System (INIS)

    Lerman, A.; Domenico, P.A.; Bartlett, J.W.

    1988-01-01

    The containment factor is a measure of retention by geologic setting of wastes released from a repository. The factor is alternatively defined either in terms of several measurable hydrological and geochemical parameters, or in terms of amounts of waste components that may be released to the geologic setting and, subsequently, to the environment. Containment factors for individual waste components in a given geologic setting are functions of groundwater to rock volume ratios, sorption or exchange characteristics of the rocks, and containment time to groundwater travel time ratios. For high-level radioactive wastes, containment factors based on the NRC and EPA limit values for cumulative releases from waste and to the environment provide a measure of the geochemical performance of the geologic setting in tuff, basalt, and salt. The containment factor values for individual nuclides from high-level wastes indicate that for some of the nuclides containment may be achieved by groundwater travel time along. For other nuclides, additional performance functions need to be allocated to geochemical retention by such processes as sorption, ion-exchange or precipitation

  10. Some outstanding issues in severe accidents containment performance

    International Nuclear Information System (INIS)

    Sehgal, B.R.

    2004-01-01

    This paper describes the current status of the outstanding issues in severe accident performance of Light Water Reactor containments that have been raised in the last several years. The results of the research that has been performed on the topics concerning these issues will be described. Some of these issues have been resolved, some are close to resolution, while others need further evaluation and research results. (author)

  11. Performance assessment: a peer review

    International Nuclear Information System (INIS)

    Lieberman, J.A.; Lee, W.W.L.

    1986-01-01

    This paper describes the rationale, membership, operation and major observations of the Performance Assessment National Review Group. The Group was assembled by Weston at the request of the US Department of Energy Office of Civilian Radioactive Waste Management to review performance assessment work in the US basalt, salt and tuff repository projects. The purposes were to evaluate the adequacy of the current methods, identify deficiencies, and suggest potential improvement on repository performance assessment. To perform the review, Weston retained a group of distinguished consultants who have had extensive experience in disciplines pertinent to management of radioactive wastes including mathematical modeling of fluid transport. Topics reviewed included flow and transport, source term and uncertainty analysis. While the emphasis was on methodologies, the Projects were specifically requested to show currently available results so that the way they utilized familiar methodologies could be evaluated. This paper will highlight some of the technical observations of the Group as well as some managerial and institutional issues

  12. Numerical simulation of radioisotope's dependency on containment performance for large dry PWR containment under severe accidents

    International Nuclear Information System (INIS)

    Mehboob, Khurram; Xinrong, Cao; Ahmed, Raheel; Ali, Majid

    2013-01-01

    Highlights: • Calculation and comparison of activity of BURN-UP code with ORIGEN2 code. • Development of SASTC computer code. • Radioisotopes dependency on containment ESFs. • Mitigation in atmospheric release with ESFs operation. • Variation in radioisotopes source term with spray flow and pH value. -- Abstract: During the core melt accidents large amount of fission products can be released into the containment building. These fission products escape into the environment to contribute in accident source term. The mitigation in environmental release is demanded for such radiological consequences. Thus, countermeasures to source term, mitigations of release of radioactivity have been studied for 1000 MWe PWR reactor. The procedure of study is divided into five steps: (1) calculation and verification of core inventory, evaluated by BURN-UP code, (2) containment modeling based on radioactivity removal factors, (3) selection of potential accidents initiates the severe accident, (4) calculation of release of radioactivity, (5) study the dependency of release of radioactivity on containment engineering safety features (ESFs) inducing mitigation. Loss of coolant accident (LOCA), small break LOCA and flow blockage accidents (FBA) are selected as initiating accidents. The mitigation effect of ESFs on source term has been studied against ESFs performance. Parametric study of release of radioactivity has been carried out by modeling and simulating the containment parameters in MATLAB, which takes BURN-UP outcomes as input along with the probabilistic data. The dependency of iodine and aerosol source term on boric and caustic acid spray has been determined. The variation in source term mitigation with the variation of containment spray flow rate and pH values have been studied. The variation in containment retention factor (CRF) has also been studied with the ESF performance. A rapid decrease in source term is observed with the increase in pH value

  13. Reliability assessment of passive containment isolation system using APSRA methodology

    International Nuclear Information System (INIS)

    Nayak, A.K.; Jain, Vikas; Gartia, M.R.; Srivastava, A.; Prasad, Hari; Anthony, A.; Gaikwad, A.J.; Bhatia, S.; Sinha, R.K.

    2008-01-01

    In this paper, a methodology known as APSRA (Assessment of Passive System ReliAbility) has been employed for evaluation of the reliability of passive systems. The methodology has been applied to the passive containment isolation system (PCIS) of the Indian advanced heavy water reactor (AHWR). In the APSRA methodology, the passive system reliability evaluation is based on the failure probability of the system to carryout the desired function. The methodology first determines the operational characteristics of the system and the failure conditions by assigning a predetermined failure criterion. The failure surface is predicted using a best estimate code considering deviations of the operating parameters from their nominal states, which affect the PCIS performance. APSRA proposes to compare the code predictions with the test data to generate the uncertainties on the failure parameter prediction, which is later considered in the code for accurate prediction of failure surface of the system. Once the failure surface of the system is predicted, the cause of failure is examined through root diagnosis, which occurs mainly due to failure of mechanical components. The failure probability of these components is evaluated through a classical PSA treatment using the generic data. The reliability of the PCIS is evaluated from the probability of availability of the components for the success of the passive containment isolation system

  14. DOE site performance assessment activities

    International Nuclear Information System (INIS)

    1990-07-01

    Information on performance assessment capabilities and activities was collected from eight DOE sites. All eight sites either currently dispose of low-level radioactive waste (LLW) or plan to dispose of LLW in the near future. A survey questionnaire was developed and sent to key individuals involved in DOE Order 5820.2A performance assessment activities at each site. The sites surveyed included: Hanford Site (Hanford), Idaho National Engineering Laboratory (INEL), Los Alamos National Laboratory (LANL), Nevada Test Site (NTS), Oak Ridge National Laboratory (ORNL), Paducah Gaseous Diffusion Plant (Paducah), Portsmouth Gaseous Diffusion Plant (Portsmouth), and Savannah River Site (SRS). The questionnaire addressed all aspects of the performance assessment process; from waste source term to dose conversion factors. This report presents the information developed from the site questionnaire and provides a comparison of site-specific performance assessment approaches, data needs, and ongoing and planned activities. All sites are engaged in completing the radioactive waste disposal facility performance assessment required by DOE Order 5820.2A. Each site has achieved various degrees of progress and have identified a set of critical needs. Within several areas, however, the sites identified common needs and questions

  15. Identification and assessment of containment and release management strategies for a BWR Mark III containment

    International Nuclear Information System (INIS)

    Lin, C.C.; Lehner, J.R.; Vandenkieboom, J.J.

    1992-02-01

    This report identifies and assesses accident management strategies which could be important for preventing containment failure and/or mitigating the release of fission products during a severe accident in a BWR plant with a Mark III type of containment. Based on information available from probabilistic risk assessments and other existing severe accident research, and using simplified containment and release event trees, the report identifies the challenges a Mark III containment could face during the course of a severe accident, the mechanisms behind these challenges, and the strategies that could be used to mitigate the challenges. The strategies are linked to the general safety objectives which apply for containment and release management by means of a safety objective tree. The strategies were assessed by applying them to certain severe accident sequence categories deemed important for a Mark III containment because of one or more of the following characteristics: high probability of core damage, high consequences, lead to a number of challenges, and involve the failure of multiple systems

  16. Identification and assessment of containment and release management strategies for a BWR Mark II containment

    International Nuclear Information System (INIS)

    Lin, C.C.; Lehner, J.R.

    1992-06-01

    Accident management strategies that have the potential to maintain containment integrity and control or mitigate the release of radioactivity following a severe accident at a boiling water reactor with a Mark 2 type of containment are identified and evaluated. The strategies are referred to as containment and release strategies. Using information available from probabilistic risk assessments and other existing severe accident research, and employing simplified containment and release event trees, this report identified the challenges a Mark 2 containment may encounter during a severe accident, the mechanisms behind these challenges, and the strategies that could be used to mitigate the challenge. By means of a safety objective tree, the strategies are linked to the general safety objectives of containment and release management. As part of the assessment process, the strategies are applied to certain severe accident sequence categories deemed important to a Mark 2 containment. These sequence categories exhibit one or more of the following characteristics: high probability of core damage, high consequences, lead to a number of challenges, and involve the failure of multiple systems. The Limerick Generating Station is used as a representative Mark 2 plant to illustrate plant specifics in this report

  17. Performance assessment - risk assessment vive la differences

    International Nuclear Information System (INIS)

    Nitschke, R.L.

    1997-01-01

    In the sister worlds of radioactive waste management disposal and environmental restoration, there are two similar processes and computational approaches for determining the acceptability of the proposed activities. While similar, these two techniques can lead to confusion and misunderstanding if the differences are not recognized and appreciated. In the case of radioactive waste management, the performance assessment process is used to determine compliance with certain prescribed 'performance objectives'. These objectives are designed to ensure that the disposal of radioactive (high-level, low-level, and/or transuranic) waste will be protective of human health and the environment. The environmental link is primarily through assuring protection of the groundwater as a resource. In the case of environmental restoration, the risk assessment process is used to determine the proper remedial action response, if any, for a past hazardous waste release. The process compares the 'no action' or 'leave as is' option with both carcinogenic and noncarcinogenic values for human health to determine the need for any action and to help to help determine just what the appropriate action would need to be. The impacts to the ecological system are evaluated in a slightly, different but similar fashion. Now the common objectives between these two processes notwithstanding. There are some key and fundamental differences that need to be answered that make direct comparisons or a common approach inappropriate. Failure to recognize this can lead to confusion and misunderstanding. This can be particularly problematic when one is faced with an active disposal facility located within the boundaries of an environmental restoration site as is the case at the Idaho National Engineering Laboratory (INEL). Through a critical evaluation of the performance assessment and risk assessment processes, highlighting both similarities and differences, it is hoped that greater understanding and appreciation

  18. Power performance assessment. Final report

    International Nuclear Information System (INIS)

    Frandsen, S.

    1998-12-01

    In the increasingly commercialised wind power marketplace, the lack of precise assessment methods for the output of an investment is becoming a barrier for wider penetration of wind power. Thus, addressing this problem, the overall objectives of the project are to reduce the financial risk in investment in wind power projects by significantly improving the power performance assessment methods. Ultimately, if this objective is successfully met, the project may also result in improved tuning of the individual wind turbines and in optimisation methods for wind farm operation. The immediate, measurable objectives of the project are: To prepare a review of existing contractual aspects of power performance verification procedures of wind farms; to provide information on production sensitivity to specific terrain characteristics and wind turbine parameters by analyses of a larger number of wind farm power performance data available to the proposers; to improve the understanding of the physical parameters connected to power performance in complex environment by comparing real-life wind farm power performance data with 3D computational flow models and 3D-turbulence wind turbine models; to develop the statistical framework including uncertainty analysis for power performance assessment in complex environments; and to propose one or more procedures for power performance evaluation of wind power plants in complex environments to be applied in contractual agreements between purchasers and manufacturers on production warranties. Although the focus in this project is on power performance assessment the possible results will also be of benefit to energy yield forecasting, since the two tasks are strongly related. (au) JOULE III. 66 refs.; In Co-operation Renewable Energy System Ltd. (GB); Centre for Renewable Energy (GR); Aeronautic Research Centre (SE); National Engineering Lab. (GB); Public Power Cooperation (GR)

  19. Evaluation method for the drying performance of enzyme containing formulations

    DEFF Research Database (Denmark)

    Sloth, Jakob; Bach, P.; Jensen, Anker Degn

    2008-01-01

    A method is presented for fast and cheap evaluation of the performance of enzyme containing formulations in terms of preserving the highest enzyme activity during spray drying. The method is based on modeling the kinetics of the thermal inactivation reaction which occurs during the drying process....... Relevant kinetic parameters are determined from differential scanning calorimeter (DSC) experiments and the model is used to simulate the severity of the inactivation reaction for temperatures and moisture levels relevant for spray drying. After conducting experiments and subsequent simulations...... for a number of different formulations it may be deduced which formulation performs best. This is illustrated by a formulation design study where 4 different enzyme containing formulations are evaluated. The method is validated by comparison to pilot scale spray dryer experiments....

  20. A probabilistic approach to assessing radioactive waste container lifetimes

    International Nuclear Information System (INIS)

    Porter, F.M.; Naish, C.C.; Sharland, S.M.

    1994-01-01

    A general methodology has been developed to make assessments of the lifetime of specific radioactive waste container designs in a repository environment. The methodology employs a statistical approach, which aims to reflect uncertainty in the corrosion rates, and the evolution of the environmental conditions. In this paper, the methodology is demonstrated for an intermediate-level waste (ILW) container in the anticipated UK repository situation

  1. Considerations in the development of subsurface containment barrier performance standards

    International Nuclear Information System (INIS)

    Dunstan, S.; Zdinak, A.P.; Lodman, D.

    1997-01-01

    The U.S. Department of Energy (DOE) is supporting subsurface barriers as an alternative remedial option for management of contamination problems at their facilities. Past cleanup initiatives have sometimes proven ineffective or extremely expensive. Economic considerations coupled with changing public and regulatory philosophies regarding remediation techniques makes subsurface barriers a promising technology for future cleanup efforts. As part of the initiative to develop subsurface containment barriers as an alternative remedial option, DOE funded MSE Technology Applications, Inc. (MSE) to conduct a comprehensive review to identify performance considerations for the acceptability of subsurface barrier technologies as a containment method. Findings from this evaluation were intended to provide a basis for selection and application of containment technologies to address waste problems at DOE sites. Based on this study, the development of performance standards should consider: (1) sustainable low hydraulic conductivity; (2) capability to meet applicable regulations; (3) compatibility with subsurface environmental conditions; (4) durability and long-term stability; (5) repairability; and (6) verification and monitoring. This paper describes the approach for determining considerations for performance standards

  2. Shielding Performance Measurements of Spent Fuel Transportation Container

    Directory of Open Access Journals (Sweden)

    SUN Hong-chao

    2015-11-01

    Full Text Available The safety supervision of radioactive material transportation package has been further stressed and implemented. The shielding performance measurements of spent fuel transport container is the important content of supervision. However, some of the problems and difficulties reflected in practice need to be solved, such as the neutron dose rate on the surface of package is too difficult to measure exactly, the monitoring results are not always reliable, etc. The monitoring results using different spectrometers were compared and the simulation results of MCNP runs were considered. An improvement was provided to the shielding performance measurements technique and management of spent fuel transport.

  3. Risk-informed assessment of degraded containment structures

    International Nuclear Information System (INIS)

    Spencer, B.W.; Kunsman, D.M.; Graves, H.L.

    2003-01-01

    As nuclear power plants age, a number of degradation mechanisms may begin to affect the ability of critical containment structures to prevent radiation release during a severe accident. A research program is underway to quantify the effects of various types of containment degradation in a risk-informed manner. In this paper, corrosion is assumed to occur in the liner of a reinforced concrete containment at a 'typical' U.S. pressurized water reactor nuclear power plant, and its effect is investigated. Latin hypercube sampling is used in conjunction with finite element models of a typical steel-lined reinforced concrete containment to generate overpressurization fragilities of the containment with and without corrosion. An existing probabilistic risk assessment model of the plant is then used with these fragilities to determine the increase in risk caused by the corrosion. (author)

  4. Eddy Current Assessment of Engineered Components Containing Nanofibers

    Science.gov (United States)

    Ko, Ray T.; Hoppe, Wally; Pierce, Jenny

    2009-03-01

    The eddy current approach has been used to assess engineered components containing nanofibers. Five specimens with different programmed defects were fabricated. A 4-point collinear probe was used to verify the electrical resistivity of each specimen. The liftoff component of the eddy current signal was used to test two extreme cases with different nano contents. Additional eddy current measurements were also used in detecting a missing nano layer simulating a manufacturing process error. The results of this assessment suggest that eddy current liftoff measurement can be a useful tool in evaluating the electrical properties of materials containing nanofibers.

  5. PERFORMANCE ASSESSMENT FOR FIELD SPORTS

    Directory of Open Access Journals (Sweden)

    Christopher Carling

    2009-03-01

    Full Text Available DESCRIPTION The book covers the various sport science assessment procedures for sports such as soccer, rugby, field hockey and lacrosse. It provides detailed and clear information about laboratory and field-based methods that can be used to assess and improve both individual and team performance. PURPOSE The book aims to provide a contemporary reference tool for selection of appropriate testing procedures for sports across a range of scientific disciplines. FEATURES The text begins with a chapter on the rationales for performance assessments, the use of technology and the necessity for procedures to conform to scientific rigor, explaining the importance of test criteria. This chapter ends by emphasizing the importance of the feedback process and vital considerations for the practitioner when interpreting the data, selecting which information is most important and how to deliver this back to the athlete or coach in order to deliver a positive performance outcome. The next two chapters focus on psychological assessments with respect to skill acquisition, retention and execution providing a variety of qualitative and quantitative options, underpinned with scientific theory and contextualized in order to improve the understanding of the application of these methods to improve anticipation and decision-making to enhance game intelligence.Chapter 4 provides coverage of match analysis techniques in order to make assessments of technical, tactical and physical performances. Readers learn about a series of methodologies ranging from simplistic pen and paper options through to sophisticated technological systems with some exemplar data also provided. Chapters 5 through 7 cover the physiological based assessments, including aerobic, anaerobic and anthropometric procedures. Each chapter delivers a theoretical opening section before progressing to various assessment options and the authors make great efforts to relate to sport-specific settings. The final

  6. Reliability assessment of Indian Point Unit 3 containment structure

    International Nuclear Information System (INIS)

    Kawakami, J.; Hwang, H.; Chang, M.T.; Reich, M.

    1984-01-01

    In the current design criteria, the load combinations specified for design of concrete containment structures are in the deterministic formats. However, by applying the probability-based reliability method developed by BNL to the concrete containment structures designed according to the criteria, it is possible to evaluate the reliability levels implied in the current design criteria. For this purpose, the reliability analysis is applied to the Indian Point Unit No. 3 containment. The details of the containment structure such as the geometries and the rebar arrangements, etc., are taken from the working drawings and the final safety analysis reports. Three kinds of loads are considered in the reliability analysis. They are, dead load (D), accidental pressure due to a large LOCA (P), and earthquake ground acceleration (E). Reliability analysis of the containment subjected to all combinations of loads is performed. Results are presented in this report

  7. Identification and assessment of containment and release management strategies for a BWR Mark I containment

    International Nuclear Information System (INIS)

    Lin, C.C.; Lehner, J.R.

    1991-09-01

    This report identifies and assesses accident management strategies which could be important for preventing containment failure and/or mitigating the release of fission products during a severe accident in a BWR plant with a Mark 1 type of containment. Based on information available from probabilistic risk assessments and other existing severe accident research, and using simplified containment and release event trees, the report identifies the challenges a Mark 1 containment could face during the course of a severe accident, the mechanisms behind these challenges, and the strategies that could be used to mitigate the challenges. A safety objective tree is developed which provides the connection between the safety objectives, the safety functions, the challenges, and the strategies. The strategies were assessed by applying them to certain severe accident sequence categories which have one or more of the following characteristics: have high probability of core damage or high consequences, lead to a number of challenges, and involve the failure of multiple systems. 59 refs., 55 figs., 27 tabs

  8. Performance tests of the reactor containment structures of HTTR

    International Nuclear Information System (INIS)

    Sakaba, Nariaki; Iigaki, Kazuhiko; Kawaji, Satoshi; Iyoku, Tatsuo

    1998-03-01

    The containment structures of the HTTR consist of the reactor containment vessel (CV), service area (SA) and emergency air purification system, which minimize the release of FPs in the postulated accidents with FP release from the reactor facilities. The CV is designed to withstand the temperature and pressure transients and to be leak-tight within the specified leakage limit even in the case of a rupture of the primary concentric hot gas duct. The pressure of inside of the SA should be maintained slightly lower than that of atmosphere by the emergency air purification system. The radioactive materials are released from the stack to environment via the emergency air purification system under the accident condition. Then the emergency air purification system should remove airborne radio-activities and should maintain proper pressure in the SA. We established the method to measure leak rate of the CV with closed reactor coolant pressure boundary although it is normally measured under opened reactor coolant pressure boundary as employed in LWRs. The CV leak rate test was carried out by the newly developed method and the expected performance was obtained. The SA and emergency air purification system were also confirmed by the performance test. We concluded that the reactor containment structures were fabricated to minimize the release of FPs in the postulated accidents with FP release from the reactor facilities. (author)

  9. Performance Based Clustering for Benchmarking of Container Ports: an Application of Dea and Cluster Analysis Technique

    Directory of Open Access Journals (Sweden)

    Jie Wu

    2010-12-01

    Full Text Available The operational performance of container ports has received more and more attentions in both academic and practitioner circles, the performance evaluation and process improvement of container ports have also been the focus of several studies. In this paper, Data Envelopment Analysis (DEA, an effective tool for relative efficiency assessment, is utilized for measuring the performances and benchmarking of the 77 world container ports in 2007. The used approaches in the current study consider four inputs (Capacity of Cargo Handling Machines, Number of Berths, Terminal Area and Storage Capacity and a single output (Container Throughput. The results for the efficiency scores are analyzed, and a unique ordering of the ports based on average cross efficiency is provided, also cluster analysis technique is used to select the more appropriate targets for poorly performing ports to use as benchmarks.

  10. Assessment of materials for nuclear fuel immobilization containers

    Energy Technology Data Exchange (ETDEWEB)

    Nuttall, K; Urbanic, V F

    1981-09-01

    A wide range of engineering metals and alloys has been assessed for their suitability as container materials for irradiated nuclear fuel intended for permanent disposal in a deep, underground hard-rock vault. The expected range of service conditions in the disposal vault are discussed, as well as the material properties required for this application. An important requirement is that the container last at least 500 years without being breached. The assessment is treated in two parts. Part I concentrates on the physical and mechanical metallurgy, with special reference to strength, weldability, potential embrittlement mechanisms and some economic aspects. Part II discusses possible mechanisms of metallic corrosion for the various engineering alloys and the expected range of environmental conditions in the vault. Localized corrosion and delayed fracture processes are identified as being most likely to limit container lifetime. Hence an essential requirement is that such processes either be absent or proceed at an insignificant rate. Three groups of alloys are recommended for further consideration as possible container materials: AISI 300 series austenitic stainless steels, high nickel-base alloys and very dilute titanium-base alloys. Specific alloys from each group are indicated as having the optimum combination of required properties, including cost. For container designs where the outer container shell does not independently support the service loads, copper should also be considered. The final material selection will depend primarily on the enviromental conditions in the vault. 42 figures, 31 tables.

  11. Long-term performance of structures comprising nuclear power plants PART 1: Deterioration assessment of nuclear power station buildings PART 2: Long-term stability and the leak-tightness of reactor containments

    International Nuclear Information System (INIS)

    Pocock, D.C.; Worthington, J.C.; Oberpichler, R.; Van Exel, H.; Beukelmann, D.; Huth, R.; Rose, B.

    1990-01-01

    The objective of this research was to study the long-term performance of structures comprising nuclear power plants. The time period of interest for this study is 140 years (this figure is based on maximum periods of 40 years for operation and 100 years of storage). It was divided in two parts: - the first based on four UK nuclear power plants examine the principle deterioration mechanism of reinforced structure which is chloride ingress and carbonation penetration - the second based on 2 German nuclear power plants examine the long term behaviour of reinforced and prestressed concrete and also the corrosion of steel containments with particular reference on plastic seals and potential risk areas

  12. Linux containers networking: performance and scalability of kernel modules

    NARCIS (Netherlands)

    Claassen, J.; Koning, R.; Grosso, P.; Oktug Badonnel, S.; Ulema, M.; Cavdar, C.; Zambenedetti Granville, L.; dos Santos, C.R.P.

    2016-01-01

    Linux container virtualisation is gaining momentum as lightweight technology to support cloud and distributed computing. Applications relying on container architectures might at times rely on inter-container communication, and container networking solutions are emerging to address this need.

  13. Methodology for NDA performance assessment

    International Nuclear Information System (INIS)

    Cuypers, M.; Franklin, M.; Guardini, S.

    1986-01-01

    In the framework of the RandD programme of the Joint Research Centre of the Commission of the European Communities, a considerable effort is being dedicated to performance assessment of NDA techniques taking account of field conditions. By taking account of field conditions is meant measurement samples of the size encountered in practice and training which allows inspectors to design cost efficient verification plans for the real situations encountered in the field. Special laboratory facilities referred to as PERLA are being constructed for this purpose. These facilities will be used for measurement experiments and for training. In this paper, performance assessment is discussed under the headings of measurement capability and in-field effectiveness. Considerable emphasis is given to the role of method specific measurement error models. The authors outline the advantages of giving statistical error models a sounder basis in the physical phenomenology of the measurement method

  14. A performance-oriented and risk-based regulation for containment testing

    International Nuclear Information System (INIS)

    Dey, M.

    1994-01-01

    In August 1992, the NRC initiated a major initiative to develop requirements for containment testing that are less prescriptive, and more performance-oriented and risk-based. This action was a result of public comments and several studies that concluded that the economic burden of certain, present containment testing requirements are not commensurate with their safety benefits. The rulemaking will include consideration of relaxing the allowable containment leakage rate, increasing the interval for the integrated containment test, and establishing intervals for the local containment leak rate tests based on their performance. A study has been conducted to provide technical information for establishing the performance criteria for containment tests, the allowable leakage rate, commensurate with its significance to total public risk. The study used results of a recent comprehensive study conducted by the NRC, NUREG-1150, 'Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants,' to examine the sensitivity of containment leakage to public risk. Risk was found to be insensitive to containment leakage rate up to levels of about 100 percent-volume per day for certain types of containments. PRA methods have also been developed to establish risk-based intervals for containment tests based on their past experience. Preliminary evaluations show that increasing the interval for the integrated containment leakage test from three times to once every ten years would have an insignificant impact on public risk. Preliminary analyses of operational experience data for local leak rate tests show that performance-based testing, valves and penetrations that perform well are tested less frequently, is feasible with marginal impact on safety. The above technical studies are being used to develop efficient (cost-effective) requirements for containment tests. (author). 4 refs., 2 figs

  15. Preliminary melter performance assessment report

    International Nuclear Information System (INIS)

    Elliott, M.L.; Eyler, L.L.; Mahoney, L.A.; Cooper, M.F.; Whitney, L.D.; Shafer, P.J.

    1994-08-01

    The Melter Performance Assessment activity, a component of the Pacific Northwest Laboratory's (PNL) Vitrification Technology Development (PVTD) effort, was designed to determine the impact of noble metals on the operational life of the reference Hanford Waste Vitrification Plant (HWVP) melter. The melter performance assessment consisted of several activities, including a literature review of all work done with noble metals in glass, gradient furnace testing to study the behavior of noble metals during the melting process, research-scale and engineering-scale melter testing to evaluate effects of noble metals on melter operation, and computer modeling that used the experimental data to predict effects of noble metals on the full-scale melter. Feed used in these tests simulated neutralized current acid waste (NCAW) feed. This report summarizes the results of the melter performance assessment and predicts the lifetime of the HWVP melter. It should be noted that this work was conducted before the recent Tri-Party Agreement changes, so the reference melter referred to here is the Defense Waste Processing Facility (DWPF) melter design

  16. Damage assessment of nuclear containment against aircraft crash

    Energy Technology Data Exchange (ETDEWEB)

    Iqbal, Mohd Ashraf, E-mail: iqbal_ashraf@rediffmail.com; Sadique, Md. Rehan, E-mail: rehan.sadique@gmail.com; Bhargava, Pradeep, E-mail: bhpdpfce@iitr.ac.in; Bhandari, N.M., E-mail: nmbcefce@iitr.ac.in

    2014-10-15

    Highlights: • Damage assessment of nuclear containment is studied against aircraft crash. • Four impact locations have been identified at the outer containment shell. • The mid of the total height has been found to be most vulnerable location. • The crown of dome has been found to be the strongest location. • Phantom F4 caused more localized and severe damage compared to other aircrafts. - Abstract: The behavior of nuclear containment structure has been studied against aircraft crash with an emphasis on the influence of strike location. The impact locations identified on the BWR Mark III type nuclear containment structure are mid-height, junction of dome and cylinder, crown of dome and arc of dome. The containment at each of the above locations has been impacted normally by Phantom F-4, Boeing 707-320 and Airbus A320 aircrafts. The loading of the aircraft has been assigned through the corresponding reaction-time response curve. ABAQUS/Explicit finite element code has been used to carry out the three-dimensional numerical simulations. The concrete damaged plasticity model was used to simulate the behavior of concrete while the behavior of steel reinforcement was incorporated using the Johnson–Cook elasto-viscoplastic material model. The mid-height of containment has been found to experience most severe deformation against each aircraft. Phantom F4 has been found to be most disastrous at each location. The results have been compared with those of the available studies with respect to the containment deformation.

  17. Assessment of Residual Stresses in 3013 Inner and Outer Containers and Teardrop Samples

    Energy Technology Data Exchange (ETDEWEB)

    Stroud, Mary Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Prime, Michael Bruce [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Veirs, Douglas Kirk [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Berg, John M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Clausen, Bjorn [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Worl, Laura Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); DeWald, Adrian T. [Hill Engineering, LLC, Rancho Cordova, CA (United States)

    2015-12-08

    This report is an assessment performed by LANL that examines packaging for plutonium-bearing materials and the resilience of its design. This report discusses residual stresses in the 3013 outer, the SRS/Hanford and RFETS/LLNL inner containers, and teardrop samples used in studies to assess the potential for SCC in 3013 containers. Residual tensile stresses in the heat affected zones of the closure welds are of particular concern.

  18. Assessment of Residual Stresses in 3013 Inner and Outer Containers and Teardrop Samples

    International Nuclear Information System (INIS)

    Stroud, Mary Ann; Prime, Michael Bruce; Veirs, Douglas Kirk; Berg, John M.; Clausen, Bjorn; Worl, Laura Ann; DeWald, Adrian T.

    2015-01-01

    This report is an assessment performed by LANL that examines packaging for plutonium-bearing materials and the resilience of its design. This report discusses residual stresses in the 3013 outer, the SRS/Hanford and RFETS/LLNL inner containers, and teardrop samples used in studies to assess the potential for SCC in 3013 containers. Residual tensile stresses in the heat affected zones of the closure welds are of particular concern.

  19. Containment performance evaluation of prestressed concrete containment vessels with fiber reinforcement

    Energy Technology Data Exchange (ETDEWEB)

    Choun, Young Sun; Park, Hyung Kui [Integrated Safety Assessment Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-12-15

    Fibers in concrete resist the growth of cracks and enhance the postcracking behavior of structures. The addition of fibers into a conventional reinforced concrete can improve the structural and functional performance of safety-related concrete structures in nuclear power plants. The influence of fibers on the ultimate internal pressure capacity of a prestressed concrete containment vessel (PCCV) was investigated through a comparison of the ultimate pressure capacities between conventional and fiber-reinforced PCCVs. Steel and polyamide fibers were used. The tension behaviors of conventional concrete and fiber-reinforced concrete specimens were investigated through uniaxial tension tests and their tension-stiffening models were obtained. For a PCCV reinforced with 1% volume hooked-end steel fiber, the ultimate pressure capacity increased by approximately 12% in comparison with that for a conventional PCCV. For a PCCV reinforced with 1.5% volume polyamide fiber, an increase of approximately 3% was estimated for the ultimate pressure capacity. The ultimate pressure capacity can be greatly improved by introducing steel and polyamide fibers in a conventional reinforced concrete. Steel fibers are more effective at enhancing the containment performance of a PCCV than polyamide fibers. The fiber reinforcement was shown to be more effective at a high pressure loading and a low prestress level.

  20. Containment performance evaluation of prestressed concrete containment vessels with fiber reinforcement

    International Nuclear Information System (INIS)

    Choun, Young Sun; Park, Hyung Kui

    2015-01-01

    Fibers in concrete resist the growth of cracks and enhance the postcracking behavior of structures. The addition of fibers into a conventional reinforced concrete can improve the structural and functional performance of safety-related concrete structures in nuclear power plants. The influence of fibers on the ultimate internal pressure capacity of a prestressed concrete containment vessel (PCCV) was investigated through a comparison of the ultimate pressure capacities between conventional and fiber-reinforced PCCVs. Steel and polyamide fibers were used. The tension behaviors of conventional concrete and fiber-reinforced concrete specimens were investigated through uniaxial tension tests and their tension-stiffening models were obtained. For a PCCV reinforced with 1% volume hooked-end steel fiber, the ultimate pressure capacity increased by approximately 12% in comparison with that for a conventional PCCV. For a PCCV reinforced with 1.5% volume polyamide fiber, an increase of approximately 3% was estimated for the ultimate pressure capacity. The ultimate pressure capacity can be greatly improved by introducing steel and polyamide fibers in a conventional reinforced concrete. Steel fibers are more effective at enhancing the containment performance of a PCCV than polyamide fibers. The fiber reinforcement was shown to be more effective at a high pressure loading and a low prestress level

  1. Performance Assessment Institute-NV

    Energy Technology Data Exchange (ETDEWEB)

    Lombardo, Joesph [Univ. of Nevada, Las Vegas, NV (United States)

    2012-12-31

    The National Supercomputing Center for Energy and the Environment’s intention is to purchase a multi-purpose computer cluster in support of the Performance Assessment Institute (PA Institute). The PA Institute will serve as a research consortium located in Las Vegas Nevada with membership that includes: national laboratories, universities, industry partners, and domestic and international governments. This center will provide a one-of-a-kind centralized facility for the accumulation of information for use by Institutions of Higher Learning, the U.S. Government, and Regulatory Agencies and approved users. This initiative will enhance and extend High Performance Computing (HPC) resources in Nevada to support critical national and international needs in "scientific confirmation". The PA Institute will be promoted as the leading Modeling, Learning and Research Center worldwide. The program proposes to utilize the existing supercomputing capabilities and alliances of the University of Nevada Las Vegas as a base, and to extend these resource and capabilities through a collaborative relationship with its membership. The PA Institute will provide an academic setting for interactive sharing, learning, mentoring and monitoring of multi-disciplinary performance assessment and performance confirmation information. The role of the PA Institute is to facilitate research, knowledge-increase, and knowledge-sharing among users.

  2. TRAC analysis of passive containment cooling system performance

    International Nuclear Information System (INIS)

    Arai, Kenji; Kataoka, Kazuyoshi; Nagasaka, Hideo

    1993-01-01

    A passive containment cooling system (PCCS) is a promising concept to improve the reliability of decay heat removal during an accident. Toshiba has carried out analytical studies for PCCS development in addition to experimental studies, using a best estimate thermal hydraulic computer code TRAC. In order to establish an analytical model for the PCCS performance analysis, it is necessary for the analytical model to be qualified against experimental results and thoroughly address the phenomena important for PCCS performance analysis. In this paper, the TRAC qualification for PCCS application is reported. A TRAC model has been verified against a drain line break simulation test conducted at the PCCS integral test facility, GIRAFFE. The result shows that the TRAC model can accurately predict the major system response and the PCCS performance in the drain line break test. In addition, the results of several sensitivity analyses, showing various points concerning the modeling in the PCCS performance analysis, have been reported. The analyses have been carried out for the SBWR and the analytical points are closely related to important phenomena which can affect PCCS performance

  3. An assessment of materials for nuclear fuel immobilization containers

    International Nuclear Information System (INIS)

    Nuttall, K.; Urbanic, V.F.

    1981-09-01

    A wide range of engineering metals and alloys was assessed for their suitability as container materials for irradiated nuclear fuel intended for permanent disposal in a deep, underground hard-rock vault. The container must last at least 500 years without being breached. Materials were assessed for their physical and mechanical metallurgy, weldability, potential embrittlement mechanisms, and economics. A study of the possible mechanisms of metallic corrosion for the various engineering alloys and the expected range of environmental conditons in the vault showed that localized corrosion and delayed fracture processes are the most likely to limit container lifetime. Thus such processes either must be absent or proceed at an insignificant rate. Three groups of alloys are recommended for further study: AISI 300 series austenitic stainless steels, high nickel-base alloys and very dilute titanium-base alloys. Specific alloys from each group are indicated as having the optimum combination of required properties, including cost. For container designs where the outer container shell does not independently support the service loads, copper should also be considered. The final material selection will depend primarily on the environmental conditions in the vault

  4. AC-600 passive containment cooling system performance research

    International Nuclear Information System (INIS)

    Jia Baoshan; Yu Jiyang; Shi Junying

    1997-01-01

    a code named PCCSAC which is able to predict both the evaporating film on the outside surface of the vessel and the condensed film on its inside is developed successfully. It is a special software tool to analyze the passive containment cooling system (PCCS) performance in the design of AC-600. The author includes the establishment of physical models, selection of numerical methods, debugging and verification of the code and application of the code in the AC-600 PCCS. In physical models, the fundamental conservation equations about various areas and heat conduction equations are established. In order to make the equations to meet the closed form of solution, a lot of structure formulae are complemented. After repeated selection and demonstration of the numerical methods, the backward difference method Gear which is generally used for stiff problem is chosen for the solution of ordinary differential equations derived from the physical models. The results of standard example calculated by the PCCSAC code and the COMMIX code which is used to analyze westinghouse AP-600 are same in the main. The reliability and validity are verified from the calculations. The PCCSAC code is applied in the calculations of two important LOCA used in the containment safety analyses. The sensitivity of main parameters in the system based on LOCA are studied. All the results are reasonable and in agreement with the theoretical analyses. It can be concluded that the PCCSAC code is able to be used for the analyses of AC-600 PCCS performance

  5. Salt site performance assessment activities

    International Nuclear Information System (INIS)

    Kircher, J.F.; Gupta, S.K.

    1983-01-01

    During this year the first selection of the tools (codes) for performance assessments of potential salt sites have been tentatively selected and documented; the emphasis has shifted from code development to applications. During this period prior to detailed characterization of a salt site, the focus is on bounding calculations, sensitivity and with the data available. The development and application of improved methods for sensitivity and uncertainty analysis is a focus for the coming years activities and the subject of a following paper in these proceedings. Although the assessments to date are preliminary and based on admittedly scant data, the results indicate that suitable salt sites can be identified and repository subsystems designed which will meet the established criteria for protecting the health and safety of the public. 36 references, 5 figures, 2 tables

  6. Improving Seismic Data Accessibility and Performance Using HDF Containers

    Science.gov (United States)

    Evans, B. J. K.; Wang, J.; Yang, R.

    2017-12-01

    The performance of computational geophysical data processing and forward modelling relies on both computational and data. Significant efforts on developing new data formats and libraries have been made the community, such as IRIS/PASSCAL and ASDF in data, and programs and utilities such as ObsPy and SPECFEM. The National Computational Infrastructure hosts a national significant geophysical data collection that is co-located with a high performance computing facility and provides an opportunity to investigate how to improve the data formats from both a data management and a performance point of view. This paper investigates how to enhance the data usability in several perspectives: 1) propose a convention for the seismic (both active and passive) community to improve the data accessibility and interoperability; 2) recommend the convention used in the HDF container when data is made available in PH5 or ASDF formats; 3) provide tools to convert between various seismic data formats; 4) provide performance benchmark cases using ObsPy library and SPECFEM3D to demonstrate how different data organization in terms of chunking size and compression impact on the performance by comparing new data formats, such as PH5 and ASDF to traditional formats such as SEGY, SEED, SAC, etc. In this work we apply our knowledge and experience on data standards and conventions, such as CF and ACDD from the climate community to the seismology community. The generic global attributes widely used in climate community are combined with the existing convention in the seismology community, such as CMT and QuakeML, StationXML, SEGY header convention. We also extend such convention by including the provenance and benchmarking records so that the r user can learn the footprint of the data together with its baseline performance. In practise we convert the example wide angle reflection seismic data from SEGY to PH5 or ASDF by using ObsPy and pyasdf libraries. It quantitatively demonstrates how the

  7. The DECADE performance assessment program

    International Nuclear Information System (INIS)

    Weber, B.V.; Ottinger, P.F.; Commisso, R.J.; Thompson, J.; Rowley, J.E.; Filios, P.; Babineau, M.A.

    1996-01-01

    Previous analyses of DECADE Module 1 experiments indicated significant current loss between the plasma opening switch (POS) and an electron-beam load. A program was initiated to diagnose and improve the power flow to assess the performance of a multi-module DECADE system. Power flow measurements between the POS and load indicate high vacuum flow, distributed current loss and azimuthal asymmetries. A decreased load impedance reduces the fraction of the load current flowing in vacuum. Improved plasma source symmetry reduces losses near the load for long conduction times. Increased POS impedance is required to significantly improve the power coupling to the load. (author). 6 figs., 9 refs

  8. The DECADE performance assessment program

    Energy Technology Data Exchange (ETDEWEB)

    Weber, B V; Ottinger, P F; Commisso, R J [Naval Research Lab., Washington, DC (United States). Plasma Physics Div.; Goyer, J R; Kortbawi, D [Physics International Co., Berkeley, CA (United States); Thompson, J [Maxwell Labs., San Diego, CA (United States); Rowley, J E; Filios, P [Defense Nuclear Agency, Alexandria, VA (United States); Babineau, M A [Sverdlup Technology, Tullahoma, TN (United States)

    1997-12-31

    Previous analyses of DECADE Module 1 experiments indicated significant current loss between the plasma opening switch (POS) and an electron-beam load. A program was initiated to diagnose and improve the power flow to assess the performance of a multi-module DECADE system. Power flow measurements between the POS and load indicate high vacuum flow, distributed current loss and azimuthal asymmetries. A decreased load impedance reduces the fraction of the load current flowing in vacuum. Improved plasma source symmetry reduces losses near the load for long conduction times. Increased POS impedance is required to significantly improve the power coupling to the load. (author). 6 figs., 9 refs.

  9. Performance assessment of coupled processes

    International Nuclear Information System (INIS)

    Pigford, T.H.

    1987-01-01

    The author considers all processes to be coupled. For example, a waste package heats the surrounding rock and its pore water, creating gradients in density and pressure that result in increased water flow. That process can be described as coupled, in that the flow is a consequence of heating. In a narrower sense, one speaks also of the more weakly coupled transport processes, expressed by the Onsager reciprocal relations, that state that a transport current, i.e., flux, of heat is accompanied by a small transport current of material, as evidenced in isotope separation by thermal diffusion, the Thompson effect in thermoelectricity, etc. This paper presents a performance assessment of coupled processes

  10. Identification and assessment of containment and release management strategies

    International Nuclear Information System (INIS)

    Lehner, J.R.; Lin, C.C.; Neogy, P.

    1990-01-01

    Brookhaven National Laboratory, under the auspices of the US Nuclear Regulatory Commission, is investigating accident management strategies which could help preserve containment integrity or minimize releases during a severe accident. The objective is to make use of existing plant systems and equipment in innovative ways to reduce the likelihood of containment failure or to mitigate the release of fission products to the environment if failure cannot be prevented. Many of the strategies would be implemented during the later stages of a severe accident. The identification and assessment process for containment and release strategies is described, and some insights derived from its application to a BWR Mark 1 plant are presented here. 13 refs., 2 figs

  11. Assessment of Containment Structures Against Missile Impact Threats

    Institute of Scientific and Technical Information of China (English)

    LI Q M

    2006-01-01

    In order to ensure the highest safety requirements,nuclear power plant structures (the containment structures,the fuel storages and transportation systems) should be assessed against all possible internal and external impact threats.The internal impact threats include kinetic missiles generated by the failure of high pressure vessels and pipes,the failure of high speed rotating machineries and accidental drops.The external impact threats may come from airborne missiles,aircraft impact,explosion blast and fragments.The impact effects of these threats on concrete and steel structures in a nuclear power plant are discussed.Methods and procedures for the impact assessment of nuclear power plants are introduced.Recent studies on penetration and perforation mechanics as well as progresses on dynamic properties of concrete-like materials are presented to increase the understanding of the impact effects on concrete containment structures.

  12. Reactor containment purge and vent valve performance experiments

    International Nuclear Information System (INIS)

    Hunter, J.A.; Steele, R.; Watkins, J.C.

    1985-01-01

    Three nuclear-designed butterfly valves typical of those used in domestic nuclear power plant containment purge and vent applications were tested. For a comparison of responses, two eight-inch nominal pipe size valves with differing internal design were tested. For extrapolation insights, a 24-inch nominal pipe size valve was also tested. The valve experiments were performed with various piping configurations and valve disc orientations to the flow, to simulate various installation options in field application. As a standard for comparing the effects of the installation options, testing was also performed in a standard ANSI test section. Test cycles were performed at inlet pressures of 5 to 60 psig, while monitoring numerous test parameters, such as the valve disc position, valve shaft torque, mass flow rate, and the pressure and temperature at multiple locations throughout the test section. An experimental data base was developed to assist in the evaluation of the current analytical methods and to determine the influence of inlet pressure, inlet duct geometry, and valve orientation to the flow media on valve torque requirements, along with any resulting limitations to the extrapolation methods. 2 refs., 15 figs

  13. Thermal Performance of the Storage Brick Containing Microencapsulated PCM

    International Nuclear Information System (INIS)

    Lee, Dong Gyu

    1998-02-01

    The utilization of microencapsulated phase change materials(PCMs) provides several advantages over conventional PCM application. The heat storage system, as well as heat recovery system, can be built to a smaller size than the normal systems for a given thermal cycling capacity. This microencapsulated PCM technique has not yet been commercialized, however. In this work sodium acetate trihydrate(CH 3 COONa · 3H 2 O) was selected for the PCM and was encapsulated. This microencapsulated PCM was mixed with cement mortar for utilization as a floor heating system. In this experiment performed here the main purpose was to investigate the thermal performance of a storage brick with microencapsulated PCM concentration. The thermal performance of this storage brick is dependent on PCM concentration, flow rate and cooling temperature of the heat transfer fluid, etc. The results showed that cycle time was shortened as the PCM content was increased and as the mass flow rate was increased. The same effect was obtained when the cooling temperature was decreased. For each thermal storage brick the overall heat transfer coefficient(U-value) was constant for a 0% brick, but was increased with time for the bricks containing microencapsulated PCM. For the same mass flow rate, as the cooling temperature decreased, the amount of heat withdrawn increased, and in particular a critical cooling temperature was found for each thermal storage brick. The average effectiveness of each thermal storage brick was found to be approximately 48%, 51% and 58% respectively

  14. Performance of Cement Containing Laterite as Supplementary Cementing Material

    Directory of Open Access Journals (Sweden)

    Abbas Bukhari, Z. S.

    2013-03-01

    Full Text Available The utilization of different industrial waste, by-products or other materials such as ground granulated blast furnace slag, silica fume, fly ash, limestone, and kiln dust, etc. as supplemen- tary cementing materials has received considerable attention in recent years. A study has been conducted to look into the performance of laterite as Supplementary Cementing Materials (SCM. The study focuses on compressive strength performance of blended cement containing different percentage of laterite. The cement is replaced accordingly with percentage of 2 %, 5 %, 7 % and 10 % by weight. In addition, the effect of use of three chemically different laterites have been studied on physical performance of cement as in setting time, Le-Chatlier expansion, loss on ignition, insoluble residue, free lime and specifically compressive strength of cement cubes tested at the age of 3, 7, and 28 days. The results show that the strength of cement blended with laterite as SCM is enhanced. Key words: Portland cement, supplementary cementing materials (SCM, laterite, compressive strength KUI – 6/2013 Received January 4, 2012 Accepted February 11, 2013

  15. Detecting nuclear materials smuggling: performance evaluation of container inspection policies.

    Science.gov (United States)

    Gaukler, Gary M; Li, Chenhua; Ding, Yu; Chirayath, Sunil S

    2012-03-01

    In recent years, the United States, along with many other countries, has significantly increased its detection and defense mechanisms against terrorist attacks. A potential attack with a nuclear weapon, using nuclear materials smuggled into the country, has been identified as a particularly grave threat. The system for detecting illicit nuclear materials that is currently in place at U.S. ports of entry relies heavily on passive radiation detectors and a risk-scoring approach using the automated targeting system (ATS). In this article we analyze this existing inspection system and demonstrate its performance for several smuggling scenarios. We provide evidence that the current inspection system is inherently incapable of reliably detecting sophisticated smuggling attempts that use small quantities of well-shielded nuclear material. To counter the weaknesses of the current ATS-based inspection system, we propose two new inspection systems: the hardness control system (HCS) and the hybrid inspection system (HYB). The HCS uses radiography information to classify incoming containers based on their cargo content into "hard" or "soft" containers, which then go through different inspection treatment. The HYB combines the radiography information with the intelligence information from the ATS. We compare and contrast the relative performance of these two new inspection systems with the existing ATS-based system. Our studies indicate that the HCS and HYB policies outperform the ATS-based policy for a wide range of realistic smuggling scenarios. We also examine the impact of changes in adversary behavior on the new inspection systems and find that they effectively preclude strategic gaming behavior of the adversary. © 2011 Society for Risk Analysis.

  16. Designing Second Language Performance Assessments. Technical Report.

    Science.gov (United States)

    Norris, John M.; Brown, James Dean; Hudson, Thom; Yoshioka, Jim

    This technical report focuses on the decision-making potential provided by second language performance assessments. First, performance assessment is situated within the broader discussion of alternatives in language assessment and in educational assessment in general. Next, issues in performance assessment design, implementation, reliability, and…

  17. A study on the influence diagrams for the application to containment performance analysis

    International Nuclear Information System (INIS)

    Park, Joon Won

    1995-02-01

    Influence diagrams have been applied to containment performance analysis of Young-Gwang 3 and 4 in an effort to explicitly display the dependencies between events and to treat operator intervention more generally. This study has been initiated to remove the three major drawbacks of the current event tree methodology: 1) Event tree cannot express dependency between events explicitly. 2) Accident Progression Event Tree (APET) cannot represent entire containment system. 3) It is difficult to consider operator intervention with event tree. To resolve these problems, a new approach, i.e., influence diagrams, are proposed. In the present work, the applicability of the influence diagrams have been demonstrated to YGN 3 and 4 containment performance analysis and an assessment of accident management strategies. To show that the results of the application of influence diagrams are reasonable, results are compared with that of YGN 3 and 4 IPE. Both results are in good agreement. In addition, influence diagrams are used to assess two accident management strategies: 1) RCS depressurization, 2) cavity flooding. Cavity flooding has a favorable effect to late containment failure and basemat melt-through, and depressurization of RCS is good for steam generator tube rupture. However, early containment failure probability is worse in both cases. As a result of the present study, it is shown that influence diagrams can be applied to the containment performance analysis

  18. Insulated Containers for Bottled Water (ICB)-Performance Evaluation

    Science.gov (United States)

    2017-04-21

    Plastic   Wrapped  Cordura  Rubberized traction pad  PE  Plastic   Liner  No  Yes  Yes  No  Safe Tie‐Down  Capability  Yes  Yes  Yes  No  Easy Access...mounted Soldiers. The ICBs are lighter, require less storage space, and have more effective tie-down characteristics than coolers often used to carry...bottled water in vehicles. The performance of the ICBs and a commonly used cooler was assessed to determine whether the easier-to-stow ICBs would be as

  19. Quality assurance in performance assessments

    International Nuclear Information System (INIS)

    Maul, P.R.; Watkins, B.M.; Salter, P.; Mcleod, R

    1999-01-01

    Following publication of the Site-94 report, SKI wishes to review how Quality Assurance (QA) issues could be treated in future work both in undertaking their own Performance Assessment (PA) calculations and in scrutinising documents supplied by SKB (on planning a repository for spent fuels in Sweden). The aim of this report is to identify the key QA issues and to outline the nature and content of a QA plan which would be suitable for SKI, bearing in mind the requirements and recommendations of relevant standards. Emphasis is on issues which are specific to Performance Assessments for deep repositories for radioactive wastes, but consideration is also given to issues which need to be addressed in all large projects. Given the long time over which the performance of a deep repository system must be evaluated, the demonstration that a repository is likely to perform satisfactorily relies on the use of computer-generated model predictions of system performance. This raises particular QA issues which are generally not encountered in other technical areas (for instance, power station operations). The traceability of the arguments used is a key QA issue, as are conceptual model uncertainty, and code verification and validation; these were all included in the consideration of overall uncertainties in the Site-94 project. Additionally, issues which are particularly relevant to SKI include: How QA in a PA fits in with the general QA procedures of the organisation undertaking the work. The relationship between QA as applied by the regulator and the implementor of a repository development programme. Section 2 introduces the discussion of these issues by reviewing the standards and guidance which are available from national and international organisations. This is followed in Section 3 by a review of specific issues which arise from the Site-94 exercise. An outline procedure for managing QA issues in SKI is put forward as a basis for discussion in Section 4. It is hoped that

  20. Quality assurance in performance assessments

    Energy Technology Data Exchange (ETDEWEB)

    Maul, P.R.; Watkins, B.M.; Salter, P.; Mcleod, R [QuantiSci Ltd, Henley-on-Thames (United Kingdom)

    1999-01-01

    Following publication of the Site-94 report, SKI wishes to review how Quality Assurance (QA) issues could be treated in future work both in undertaking their own Performance Assessment (PA) calculations and in scrutinising documents supplied by SKB (on planning a repository for spent fuels in Sweden). The aim of this report is to identify the key QA issues and to outline the nature and content of a QA plan which would be suitable for SKI, bearing in mind the requirements and recommendations of relevant standards. Emphasis is on issues which are specific to Performance Assessments for deep repositories for radioactive wastes, but consideration is also given to issues which need to be addressed in all large projects. Given the long time over which the performance of a deep repository system must be evaluated, the demonstration that a repository is likely to perform satisfactorily relies on the use of computer-generated model predictions of system performance. This raises particular QA issues which are generally not encountered in other technical areas (for instance, power station operations). The traceability of the arguments used is a key QA issue, as are conceptual model uncertainty, and code verification and validation; these were all included in the consideration of overall uncertainties in the Site-94 project. Additionally, issues which are particularly relevant to SKI include: How QA in a PA fits in with the general QA procedures of the organisation undertaking the work. The relationship between QA as applied by the regulator and the implementor of a repository development programme. Section 2 introduces the discussion of these issues by reviewing the standards and guidance which are available from national and international organisations. This is followed in Section 3 by a review of specific issues which arise from the Site-94 exercise. An outline procedure for managing QA issues in SKI is put forward as a basis for discussion in Section 4. It is hoped that

  1. Communicating Performance Assessments Results - 13609

    International Nuclear Information System (INIS)

    Layton, Mark

    2013-01-01

    The F-Area Tank Farms (FTF) and H-Area Tank Farm (HTF) are owned by the U.S. Department of Energy (DOE) and operated by Savannah River Remediation LLC (SRR), Liquid Waste Operations contractor at DOE's Savannah River Site (SRS). The FTF and HTF are active radioactive waste storage and treatment facilities consisting of 51 carbon steel waste tanks and ancillary equipment such as transfer lines, evaporators and pump tanks. Performance Assessments (PAs) for each Tank Farm have been prepared to support the eventual closure of the underground radioactive waste tanks and ancillary equipment. PAs provide the technical bases and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements for final closure of the Tank Farms. The Tank Farms are subject to a number of regulatory requirements. The State regulates Tank Farm operations through an industrial waste water permit and through a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Closure documentation will include State-approved Tank Farm Closure Plans and tank-specific closure modules utilizing information from the PAs. For this reason, the State of South Carolina and the EPA must be involved in the performance assessment review process. The residual material remaining after tank cleaning is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005. PAs are performance-based, risk-informed analyses of the fate and transport of FTF and HTF residual wastes following final closure of the Tank Farms. Since the PAs serve as the primary risk assessment tools in evaluating readiness for closure, it is vital that PA conclusions be communicated effectively. In the course of developing the FTF and HTF PAs, several lessons learned have emerged regarding communicating PA results. When communicating PA results it is

  2. Improved power performance assessment methods

    Energy Technology Data Exchange (ETDEWEB)

    Frandsen, S; Antoniou, I; Dahlberg, J A [and others

    1999-03-01

    The uncertainty of presently-used methods for retrospective assessment of the productive capacity of wind farms is unacceptably large. The possibilities of improving the accuracy have been investigated and are reported. A method is presented that includes an extended power curve and site calibration. In addition, blockage effects with respect to reference wind speed measurements are analysed. It is found that significant accuracy improvements are possible by the introduction of more input variables such as turbulence and wind shear, in addition to mean wind speed and air density. Also, the testing of several or all machines in the wind farm - instead of only one or two - may provide a better estimate of the average performance. (au)

  3. Identification and assessment of containment and release management strategies

    International Nuclear Information System (INIS)

    Lehner, J.R.; Lin, C.C.; Neogy, P.

    1993-01-01

    Brookhaven National Laboratory, under the auspices of the U.S. Nuclear Regulatory Commission, is investigating accident management strategies which could help preserve containment integrity or minimize the release of radioactivity during a severe accident in a nuclear reactor. The objective is to make use of existing plant systems and equipment in innovative ways to reduce the likelihood of containment failure or to mitigate the release of fission products to the environment if failure cannot be prevented. Many of these strategies would be implemented during the later stages of a severe accident, i.e. after the molten core penetrates the reactor vessel. Significant uncertainties exist regarding some of the phenomena involved with this phase of a severe accident. The identification and assessment process for containment and release strategies is described, and some insights derived from its application to a BWR Mark I plant are presented. A station blackout accident for this kind of plant is considered. The challenges encountered are identified and existing emergency guidelines are reviewed, where needed and when possible, new strategies are devised. The feasibility and effectiveness of these new strategies are assessed, making due allowances for the complicated phenomena and associated uncertainties involved. Both beneficial and adverse effects of the suggested strategies are considered. (orig.)

  4. Development and assessment of the CONTAIN hybrid flow solver

    International Nuclear Information System (INIS)

    Murata, K.K.; Stamps, D.W.

    1996-11-01

    A new gravitational head formulation for the treatment of stratified conditions has been developed for CONTAIN 1.2, a control volume code used primarily for the analyses of postulated accidents in nuclear power plants. The new CONTAIN formulation of gravitational heads, termed the hybrid formulation, is described. This method of calculating stratified conditions is compared with the old, average-density formulation used in code versions prior to CONTAIN 1.2. Both formulations are assessed in this report with experimental data from three large-scale experiments in which stratified conditions formed by injection of a buoyant gas were observed. In general, the hybrid formulation gives a substantially higher degree of stratification than the old formulation. For stable, fully developed stratifications, the hybrid formulation also gives much better agreement with the measured degree of stratification than the old formulation. In addition, the predicted degree of stratification is robust and not sensitive to nodalization, provided a set of nodalization guidelines are followed. However, for stratification behavior controlled by special physics not modeled in CONTAIN, such as momentum convection, plume entrainment, or bulk molecular diffusion, one should not expect good agreement with experiment unless special measures to accommodate the missing physics are taken

  5. Generic Containment: Detailed comparison of containment simulations performed on plant scale

    International Nuclear Information System (INIS)

    Kelm, St.; Klauck, M.; Beck, S.; Allelein, H.-J.; Preusser, G.; Sangiorgi, M.; Klein-Hessling, W.; Bakalov, I.; Bleyer, A.; Bentaib, A.; Kljenak, I.; Stempniewicz, M.; Kostka, P.; Morandi, S.; Ada del Corno, B.; Bratfisch, C.; Risken, T.; Denk, L.; Parduba, Z.; Paci, S.

    2014-01-01

    Highlights: • Consequent implementation of the recommendations derived from the OECD/NEA ISP-47. • Phenomenological code-to-code comparison performed on plant scale. • Systematic identification and elimination of the user effect. • Identification of fundamental differences in the model basis. • Application to PAR system analysis. - Abstract: One outcome of the OECD/NEA ISP-47 activity was the recommendation to elaborate a ‘Generic Containment’ in order to allow comparing and rating the results obtained by different lumped-parameter models on plant scale. Within the European SARNET2 project ( (http://www.sar-net.eu)), such a Generic Containment nodalisation, based on a German PWR (1300 MW el ), was defined. This agreement on the nodalisation allows investigating the remaining differences among the results, especially the ‘user-effect’, related to the modelling choices, as well as fundamental differences in the underlying model basis in detail. The methodology applied in order to compare the different code predictions consisted of a series of three benchmark steps with increasing complexity as well as a systematic comparison of characteristic variables and observations. This paper summarises the benchmark series, the lessons learned during specifying the steps, comparing and discussing the results and finally gives an outlook on future steps

  6. Containment performance working group report. Draft report for comment

    International Nuclear Information System (INIS)

    1985-05-01

    Containment buildings for power reactors have been studied to estimate their leak rate as a function of increasing internal pressure and temperature associated with severe accident sequences involving significant core damage. Potential leak paths through containment penetration assemblies (such as equipment hatches, airlocks, purge and vent valves, and electrical penetrations) have been identified and their contributions to leak area for the containment are incorporated into containment response analyses of selected severe accident sequences to predict the containment leak rate and pressure/temperature response as a function of time. Because of lack of reliable experimental data on the leakage behavior of containment penetrations and isolation barriers at pressures beyond their design conditions, an analytical approach has been used to estimate the leakage behavior of components found in specific reference plants that approximately characterize the various containment types

  7. HTGR containment design options: an application of probabilistic risk assessment

    International Nuclear Information System (INIS)

    1977-08-01

    Through the use of probabilistic risk assessment (PRA), it is possible to quantitatively evaluate the radiological risk associated with a given reactor design and to place such risk into perspective with alternative designs. The merits are discussed for several containment alternatives for the HTGR from the viewpoints of economics and licensability, as well as public risk. The quantification of cost savings and public risk indicates that presently acceptable public risk can be maintained and cost savings of $40 million can result from use of a vented confinement for the HTGR

  8. Seismic reliability assessment methodology for CANDU concrete containment structures

    International Nuclear Information System (INIS)

    Stephens, M.J.; Nessim, M.A.; Hong, H.P.

    1995-05-01

    A study was undertaken to develop a reliability-based methodology for the assessment of existing CANDU concrete containment structures with respect to seismic loading. The focus of the study was on defining appropriate specified values and partial safety factors for earthquake loading and resistance parameters. Key issues addressed in the work were the identification of an approach to select design earthquake spectra that satisfy consistent safety levels, and the use of structure-specific data in the evaluation of structural resistance. (author). 23 refs., 9 tabs., 15 figs

  9. Verification of the CONPAS (CONtainment Performance Analysis System) code package

    International Nuclear Information System (INIS)

    Kim, See Darl; Ahn, Kwang Il; Song, Yong Man; Choi, Young; Park, Soo Yong; Kim, Dong Ha; Jin, Young Ho.

    1997-09-01

    CONPAS is a computer code package to integrate the numerical, graphical, and results-oriented aspects of Level 2 probabilistic safety assessment (PSA) for nuclear power plants under a PC window environment automatically. For the integrated analysis of Level 2 PSA, the code utilizes four distinct, but closely related modules: (1) ET Editor, (2) Computer, (3) Text Editor, and (4) Mechanistic Code Plotter. Compared with other existing computer codes for Level 2 PSA, and CONPAS code provides several advanced features: computational aspects including systematic uncertainty analysis, importance analysis, sensitivity analysis and data interpretation, reporting aspects including tabling and graphic as well as user-friendly interface. The computational performance of CONPAS has been verified through a Level 2 PSA to a reference plant. The results of the CONPAS code was compared with an existing level 2 PSA code (NUCAP+) and the comparison proves that CONPAS is appropriate for Level 2 PSA. (author). 9 refs., 8 tabs., 14 figs

  10. Communicating Performance Assessments Results - 13609

    Energy Technology Data Exchange (ETDEWEB)

    Layton, Mark [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)

    2013-07-01

    The F-Area Tank Farms (FTF) and H-Area Tank Farm (HTF) are owned by the U.S. Department of Energy (DOE) and operated by Savannah River Remediation LLC (SRR), Liquid Waste Operations contractor at DOE's Savannah River Site (SRS). The FTF and HTF are active radioactive waste storage and treatment facilities consisting of 51 carbon steel waste tanks and ancillary equipment such as transfer lines, evaporators and pump tanks. Performance Assessments (PAs) for each Tank Farm have been prepared to support the eventual closure of the underground radioactive waste tanks and ancillary equipment. PAs provide the technical bases and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements for final closure of the Tank Farms. The Tank Farms are subject to a number of regulatory requirements. The State regulates Tank Farm operations through an industrial waste water permit and through a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Closure documentation will include State-approved Tank Farm Closure Plans and tank-specific closure modules utilizing information from the PAs. For this reason, the State of South Carolina and the EPA must be involved in the performance assessment review process. The residual material remaining after tank cleaning is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005. PAs are performance-based, risk-informed analyses of the fate and transport of FTF and HTF residual wastes following final closure of the Tank Farms. Since the PAs serve as the primary risk assessment tools in evaluating readiness for closure, it is vital that PA conclusions be communicated effectively. In the course of developing the FTF and HTF PAs, several lessons learned have emerged regarding communicating PA results. When communicating PA results it is

  11. Quantitative risk assessment of foods containing peanut advisory labeling.

    Science.gov (United States)

    Remington, Benjamin C; Baumert, Joseph L; Marx, David B; Taylor, Steve L

    2013-12-01

    Foods with advisory labeling (i.e. "may contain") continue to be prevalent and the warning may be increasingly ignored by allergic consumers. We sought to determine the residual levels of peanut in various packaged foods bearing advisory labeling, compare similar data from 2005 and 2009, and determine any potential risk for peanut-allergic consumers. Of food products bearing advisory statements regarding peanut or products that had peanut listed as a minor ingredient, 8.6% and 37.5% contained detectable levels of peanut (>2.5 ppm whole peanut), respectively. Peanut-allergic individuals should be advised to avoid such products regardless of the wording of the advisory statement. Peanut was detected at similar rates and levels in products tested in both 2005 and 2009. Advisory labeled nutrition bars contained the highest levels of peanut and an additional market survey of 399 products was conducted. Probabilistic risk assessment showed the risk of a reaction to peanut-allergic consumers from advisory labeled nutrition bars was significant but brand-dependent. Peanut advisory labeling may be overused on some nutrition bars but prudently used on others. The probabilistic approach could provide the food industry with a quantitative method to assist with determining when advisory labeling is most appropriate. Copyright © 2013 Elsevier Ltd. All rights reserved.

  12. Behavior model for performance assessment

    International Nuclear Information System (INIS)

    Brown-VanHoozer, S. A.

    1999-01-01

    Every individual channels information differently based on their preference of the sensory modality or representational system (visual auditory or kinesthetic) we tend to favor most (our primary representational system (PRS)). Therefore, some of us access and store our information primarily visually first, some auditorily, and others kinesthetically (through feel and touch); which in turn establishes our information processing patterns and strategies and external to internal (and subsequently vice versa) experiential language representation. Because of the different ways we channel our information, each of us will respond differently to a task--the way we gather and process the external information (input), our response time (process), and the outcome (behavior). Traditional human models of decision making and response time focus on perception, cognitive and motor systems stimulated and influenced by the three sensory modalities, visual, auditory and kinesthetic. For us, these are the building blocks to knowing how someone is thinking. Being aware of what is taking place and how to ask questions is essential in assessing performance toward reducing human errors. Existing models give predications based on time values or response times for a particular event, and may be summed and averaged for a generalization of behavior(s). However, by our not establishing a basic understanding of the foundation of how the behavior was predicated through a decision making strategy process, predicative models are overall inefficient in their analysis of the means by which behavior was generated. What is seen is the end result

  13. Behavior model for performance assessment.

    Energy Technology Data Exchange (ETDEWEB)

    Borwn-VanHoozer, S. A.

    1999-07-23

    Every individual channels information differently based on their preference of the sensory modality or representational system (visual auditory or kinesthetic) we tend to favor most (our primary representational system (PRS)). Therefore, some of us access and store our information primarily visually first, some auditorily, and others kinesthetically (through feel and touch); which in turn establishes our information processing patterns and strategies and external to internal (and subsequently vice versa) experiential language representation. Because of the different ways we channel our information, each of us will respond differently to a task--the way we gather and process the external information (input), our response time (process), and the outcome (behavior). Traditional human models of decision making and response time focus on perception, cognitive and motor systems stimulated and influenced by the three sensory modalities, visual, auditory and kinesthetic. For us, these are the building blocks to knowing how someone is thinking. Being aware of what is taking place and how to ask questions is essential in assessing performance toward reducing human errors. Existing models give predications based on time values or response times for a particular event, and may be summed and averaged for a generalization of behavior(s). However, by our not establishing a basic understanding of the foundation of how the behavior was predicated through a decision making strategy process, predicative models are overall inefficient in their analysis of the means by which behavior was generated. What is seen is the end result.

  14. 24 CFR 115.206 - Performance assessments; Performance standards.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 1 2010-04-01 2010-04-01 false Performance assessments; Performance standards. 115.206 Section 115.206 Housing and Urban Development Regulations Relating to Housing... AGENCIES Certification of Substantially Equivalent Agencies § 115.206 Performance assessments; Performance...

  15. Risk assessment of genotoxic and carcinogenic alkenylbenzenes in botanical containing products present on the Chinese market

    NARCIS (Netherlands)

    Ning, Jia; Cui, Xin Yue; Kong, Xiang Nan; Tang, Yi Fei; Wulandari, Riana; Chen, Lu; Wesseling, Sebas; Rietjens, Ivonne M.C.M.

    2018-01-01

    In the present study, a risk assessment of plant food supplements (PFS), traditional Chinese medicines (TCM) and herbal teas containing alkenylbenzenes was performed using the Margin of Exposure (MOE) approach. The levels of alkenylbenzenes in botanical preparations collected on the Chinese market

  16. Statistical analysis in MSW collection performance assessment.

    Science.gov (United States)

    Teixeira, Carlos Afonso; Avelino, Catarina; Ferreira, Fátima; Bentes, Isabel

    2014-09-01

    The increase of Municipal Solid Waste (MSW) generated over the last years forces waste managers pursuing more effective collection schemes, technically viable, environmentally effective and economically sustainable. The assessment of MSW services using performance indicators plays a crucial role for improving service quality. In this work, we focus on the relevance of regular system monitoring as a service assessment tool. In particular, we select and test a core-set of MSW collection performance indicators (effective collection distance, effective collection time and effective fuel consumption) that highlights collection system strengths and weaknesses and supports pro-active management decision-making and strategic planning. A statistical analysis was conducted with data collected in mixed collection system of Oporto Municipality, Portugal, during one year, a week per month. This analysis provides collection circuits' operational assessment and supports effective short-term municipality collection strategies at the level of, e.g., collection frequency and timetables, and type of containers. Copyright © 2014 Elsevier Ltd. All rights reserved.

  17. Structural-performance testing of titanium-shell lead-matrix container MM2

    Energy Technology Data Exchange (ETDEWEB)

    Hosaluk, L. J.; Barrie, J. N.

    1992-05-15

    This report describes the hydrostatic structural-performance testing of a half-scale, titanium-shell, lead-matrix container (MM2) with a large, simulated volumetric casting defect. Mechancial behaviour of the container is assessed from extensive surface-strain measurements and post-test non-destructive and destructive examinations. Measured strain data are compared briefly with analytical results from a finite-element model of a previous test prototype, MM1, and with data generated by a finite-difference computer code. Finally, procedures are recommended for more detailed analytical modelling. (auth)

  18. Tax Performance Assessment in Scandinavian Countries

    Directory of Open Access Journals (Sweden)

    Bunescu Liliana

    2015-04-01

    Full Text Available The aim of this paper is to evaluate fiscal policy performance level in Nordic countries of Europe by quantifying the gap between their performance and an optimum benchmark value. In this study it was selected Denmark, Finland, Sweden and Norway. These countries occupy the first places in the ranking of countries with the highest rate of tax burden in Europe. The first part of paper contains general aspects of fiscal performance in international research and an overview of the Nordic tax systems model. The second part of paper focuses on evaluation of tax policy performance in these countries by using OptimTax scoring analysis. The research is based on a multivariate analysis instrument that uses quantitative data on various aspects of tax policy. OptimTax achieves a score for assessing the degree of optimization of fiscal policy. The results reveal high levels of tax performance in Scandinavian countries and a trend that seems to be more constant than ascending, except Norway.

  19. Doses per vaccine vial container: An understated and underestimated driver of performance that needs more evidence.

    Science.gov (United States)

    Heaton, Alexis; Krudwig, Kirstin; Lorenson, Tina; Burgess, Craig; Cunningham, Andrew; Steinglass, Robert

    2017-04-19

    The widespread use of multidose vaccine containers in low and middle income countries' immunization programs is assumed to have multiple benefits and efficiencies for health systems, yet the broader impacts on immunization coverage, costs, and safety are not well understood. To document what is known on this topic, how it has been studied, and confirm the gaps in evidence that allow us to assess the complex system interactions, the authors undertook a review of published literature that explored the relationship between doses per container and immunization systems. The relationships examined in this study are organized within a systems framework consisting of operational costs, timely coverage, safety, product costs/wastage, and policy/correct use, with the idea that a change in dose per container affects all of them, and the optimal solution will depend on what is prioritized and used to measure performance. Studies on this topic are limited and largely rely on modeling to assess the relationship between doses per container and other aspects of immunization systems. Very few studies attempt to look at how a change in doses per container affects vaccination coverage rates and other systems components simultaneously. This article summarizes the published knowledge on this topic to date and suggests areas of current and future research to ultimately improve decision making around vaccine doses per container and increase understanding of how this decision relates to other program goals. Copyright © 2016 The Author(s). Published by Elsevier Ltd.. All rights reserved.

  20. Insulated Containers For Bottled Water (ICB)- Performance Evaluation

    Science.gov (United States)

    2017-04-21

    WATER STOWAGE PROTOTYPES BOTTLED WATER HIGH TEMPERATURE WEIGHT EJECTION CONTAINERS ...Soldiers are ineffectively mounting commercially  available  coolers and they,  as well as the bottles they  contain , are becoming projectile hazards... container  (shown in Figure 15). The tie‐down procedures were determined by a professional  rigger; a video of the procedures is  available  from NSRDEC

  1. Mechanical performance assessment of half warm recycled asphalt mixes containing up to 100 % RAP; Evaluación del comportamiento mecánico de mezclas asfálticas templadas con 100 % de material reciclado

    Energy Technology Data Exchange (ETDEWEB)

    Lizárraga, J. M.; Jiménez del Barco-Carrión, A.; Ramírez, A.; Díaz, P.; Moreno-Navarro, F.; Rubio, M.C.

    2017-07-01

    The use of Half Warm Mixes with high Reclaimed Asphalt content (HWMRA) has the potential to generate significant environmental advantages such as the reduction in consumption of natural resources and the emission of gases into the atmosphere. This paper therefore focuses on demonstrating the viability of using these types of mixes in wearing courses. For this purpose, an HWMRA with 70 % and 100 % Reclaimed Asphalt Pavement (RAP) and emulsion were designed in the laboratory. The performance of the mixes was then assessed and compared with that of conventional Hot Mix Asphalt. In a second stage, the mixes were manufactured in-plant, and laid and compacted in an Accelerated Pavement Test track. The cores were then extracted and tested for stiffness modulus and resistance to fatigue. The results from the tests conducted with both the laboratory specimens and the cores showed that the performance of HWMRA is comparable to that of HMA. These findings encourage greater confidence in promoting the use of these types of sustainable asphalt mixes. [Spanish] La utilización de mezclas asfálticas templadas con alto contenido de asfalto reciclado (HWMRA) conlleva ventajas medioambientales como la reducción del consumo de recursos naturales y la emisión de gases a la atmósfera. Este artículo se centra en mostrar la viabilidad de este tipo de mezclas para capas de rodadura. Para ello, se diseñaron mezclas HWMRA con 70 % y 100 % de asfalto reciclado en el laboratorio y se evaluó y comparó su comportamiento con una mezcla caliente convencional. En una segunda etapa, las mezclas fueron fabricadas en planta, extendidas y compactadas en una pista de ensayo acelerado de pavimentos. A continuación, se extrajeron testigos y se ensayaron para conocer su módulo de rigidez y resistencia a fatiga. Tanto los resultados de laboratorio como tras la fabricación en planta y puesta en obra mostraron que el comportamiento de mezclas HWMRA es comparable al de mezclas calientes

  2. Making Performance Assessments a Part of Accountability

    Science.gov (United States)

    Haun, Billy

    2018-01-01

    The purpose of this commentary is to describe recent efforts in Virginia to develop and use performance assessments, including the challenges that emerged during this process and key considerations for states that integrate performance assessment into their systems. Performance assessments can play an important role in preparing students for…

  3. An Assessment for A Filtered Containment Venting Strategy Using Decision Tree Models

    International Nuclear Information System (INIS)

    Shin, Hoyoung; Jae, Moosung

    2016-01-01

    In this study, a probabilistic assessment of the severe accident management strategy through a filtered containment venting system was performed by using decision tree models. In Korea, the filtered containment venting system has been installed for the first time in Wolsong unit 1 as a part of Fukushima follow-up steps, and it is planned to be applied gradually for all the remaining reactors. Filtered containment venting system, one of severe accident countermeasures, prevents a gradual pressurization of the containment building exhausting noncondensable gas and vapor to the outside of the containment building. In this study, a probabilistic assessment of the filtered containment venting strategy, one of the severe accident management strategies, was performed by using decision tree models. Containment failure frequencies of each decision were evaluated by the developed decision tree model. The optimum accident management strategies were evaluated by comparing the results. Various strategies in severe accident management guidelines (SAMG) could be improved by utilizing the methodology in this study and the offsite risk analysis methodology

  4. An Assessment for A Filtered Containment Venting Strategy Using Decision Tree Models

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Hoyoung; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of)

    2016-10-15

    In this study, a probabilistic assessment of the severe accident management strategy through a filtered containment venting system was performed by using decision tree models. In Korea, the filtered containment venting system has been installed for the first time in Wolsong unit 1 as a part of Fukushima follow-up steps, and it is planned to be applied gradually for all the remaining reactors. Filtered containment venting system, one of severe accident countermeasures, prevents a gradual pressurization of the containment building exhausting noncondensable gas and vapor to the outside of the containment building. In this study, a probabilistic assessment of the filtered containment venting strategy, one of the severe accident management strategies, was performed by using decision tree models. Containment failure frequencies of each decision were evaluated by the developed decision tree model. The optimum accident management strategies were evaluated by comparing the results. Various strategies in severe accident management guidelines (SAMG) could be improved by utilizing the methodology in this study and the offsite risk analysis methodology.

  5. Performance Evaluation of Deep Learning Tools in Docker Containers

    OpenAIRE

    Xu, Pengfei; Shi, Shaohuai; Chu, Xiaowen

    2017-01-01

    With the success of deep learning techniques in a broad range of application domains, many deep learning software frameworks have been developed and are being updated frequently to adapt to new hardware features and software libraries, which bring a big challenge for end users and system administrators. To address this problem, container techniques are widely used to simplify the deployment and management of deep learning software. However, it remains unknown whether container techniques brin...

  6. A program to assess microbial impacts on nuclear waste containment

    International Nuclear Information System (INIS)

    Horn, J.; Meike, A.

    1996-01-01

    In this paper we discuss aspects of a comprehensive program to identify and bound potential effects of microorganisms on long-term nuclear waste containment, using as examples, studies conducted within the Yucca Mountain Project. A comprehensive program has been formulated which cuts across standard disciplinary lines to address the specific concerns of microbial activity in a radioactive waste repository. Collectively, this program provides bounding parameters of microbial activities that modify the ambient geochemistry and hydrology, modify corrosion rates, and transport and transform radionuclides under conditions expected to be encountered after geological waste emplacement. This program is intended to provide microbial reaction rates and bounding conditions in a form that can be integrated into existing chemical and hydrological models. The inclusion of microbial effects will allow those models to more accurately assess long term repository integrity

  7. Life Cycle Assessment of Lubricant Oil Plastic Containers in Brazil

    Directory of Open Access Journals (Sweden)

    Maria Clara Oliveira

    2017-04-01

    Full Text Available Brazil, like many emerging countries, has experienced a fast growth in the demand for automobiles in recent decades. This has produced a significant increase in the amount of hazardous waste to be disposed of, including used lubricant oil. Restrictive regulations are being used by many nations to deal with this problem, focusing on treatments, such as recycling, to avoid resource depletion. Specific rules for disposal of used lubricant oil already exist in various countries, including Brazil, but not for its containers. Using the life cycle assessment methodology, this article evaluates different management options for the destination of Lubricant Oil Plastic Containers (LOPCs, comparing recycling and incineration to disposal in an industrial landfill. Results show that reducing the proportion of LOPCs destined to the landfill has positive impacts in lowering the burdens caused in the life cycle of LOPCs. Incineration, which is not a technology used for destination of LOPCs in Brazil, proved to be a promising option when combined with recycling for treatment of this kind of waste. Combining different destinations is also a good option as long as economic, logistics and the environment are taken into consideration. The present paper concludes that emerging countries are able to manage hazardous waste provided that there is adequate legislation and political will along with cooperation from the private sector. This study can be helpful to the decision-making processes concerning hazardous waste, especially for industrial strategies and policy makers.

  8. Materials performance in off-gas systems containing iodine

    International Nuclear Information System (INIS)

    Beavers, J.A.; Berry, W.E.; Griess, J.C.

    1981-11-01

    During the reprocessing of spent reactor fuel elements, iodine is released to gas streams from which it is ultimately removed by conversion to nonvolatile iodic acid. Under some conditions iodine can produce severe corrosion in off-gas lines; in this study these conditions were established. Iron- and nickel-based alloys containing more than 6% molybdenum, such as Hastelloy G (7%), Inconel 625 (9%), and Hastelloy C-276 (16%), as well as titanium and zirconium, remained free of attack under all conditions tested. When the other materials, notably the austenitic stainless steels, were exposed to gas streams containing even only low concentrations of iodine and water vapors at 25 and 40 0 C, a highly corrosive, brownish-green liquid formed on their surfaces. In the complete absence of water vapor, the iodine-containing liquid did not form and all materials remained unaffected. The liquid that formed had a low pH (usually 2 inhibited attack

  9. Phytotoxicity Assessment of Certain Phytochemical Products Containing Pyrrolizidine Alkaloids

    Directory of Open Access Journals (Sweden)

    Cristina Șeremet Oana

    2013-10-01

    Full Text Available Introduction: Tussilago farfara (coltsfoot, Petasites hybridus (common butterbur, Senecio vernalis (eastern groundsel and Symphytum officinale (comfrey are species traditionally used in phytotherapy that besides the therapeutic compounds contain toxic pyrrolizidine alkaloids (PAs. The aim of the paper is to determine the total PAs content and the phytotoxicity of the above species. Material and methods: The quantitative determination of pyrrolizidine alkaloids is based on the stoichiometric reaction of protonated alkaloids with methyl orange. In acidic conditions the dye is released from the complex and its color is assessed spectrophotometrically using a linear regression curve of senecionine as a standard. The phytotoxicity was assessed by Triticum bioassay that studies the effect of the extracts (0.001-5.00%, w/v upon root elongation (inhibitory concentration - IC50 and on the karyokinetic film. Results: The highest amount of total PAs was found in Senecio vernalis (654.8 ± 35.96 μg/g dry plant and the lowest in Petasites hybridus. The lowest IC50 was found for Tussilago farfara followed by Petasites hybridus, Senecio vernalis, and Symphytum officinale. The results were supported by microscopic examination. Conclusions: The results of the spectrophotometric assay are consistent with the ones found in the literature. All extracts inhibited the elongation of the main root of wheat caryopses, however, no correlation between phytotoxicity and the PAs concentration could be emphasized

  10. Reliability assessment of the containment of a PWR

    International Nuclear Information System (INIS)

    Schueller, G.I.; Wellein, R.; Wittmann, F.H.; Boulahdour, T.; Mihashi, M.; Zorn, N.F.; Bauer, J.

    1981-09-01

    The aim of this research effort was to contribute to the development of methods to quantify the risk involved with nuclear power plants. Using a large component, i.e. the containment of the reference plant BIBLIS B (PWR) as sample structure a reliability analysis was performed which is based on realistic assumptions of loads and material properties. For this purpose in many fields it was necessary to develop new methods, collect data, and where not available, obtain data in tests. This effort concentrated on partial aspects and on the other hand on the development of a methodology for an overall reliability concept. According to the results of the previous project, the keypoints of this effort are the treatment of loss of coolant accidents (small leak), earthquake loading, the possibly resulting crackpropagation in the steel hull, and the structural mechanics and material strength aspects of the reinforced concrete hull subjected to impact loading (aircraft impact). (orig./HP) [de

  11. Analytical studies related to Indian PHWR containment system performance

    International Nuclear Information System (INIS)

    Haware, S.K.; Markandeya, S.G.; Ghosh, A.K.; Kushwaha, H.S.; Venkat Raj, V.

    1998-01-01

    Build-up of pressure in a multi-compartment containment after a postulated accident, the growth, transportation and removal of aerosols in the containment are complex processes of vital importance in deciding the source term. The release of hydrogen and its combustion increases the overpressure. In order to analyze these complex processes and to enable proper estimation of the source term, well tested analytical tools are necessary. This paper gives a detailed account of the analytical tools developed/adapted for PSA level 2 studies. (author)

  12. Performance assessment of nuclear waste isolation systems

    International Nuclear Information System (INIS)

    Lee, W.L.

    1984-01-01

    A number of concepts have been proposed for the isolation of highly radioactive wastes, and it will be necessary to demonstrate the safety of such systems. In many countries including the U.S., the waste isolation system of choice is deep mined geologic repositories. Because of the complex nature of the multiple isolation barriers afforded by mined geologic disposal systems, and the long isolation periods involved, this demonstration can only be indirect. In recent years this indirect demonstration, mostly through mathematical modeling, is called performance assessment. Performance Assessment can be defined to mean the development, testing, and application of a series of mathematical models and computer codes which traces the movement of radionuclides from a waste isolation system to the biosphere and any resultant dose to man. In modeling such a repository system, it is often convenient to divide it into a number of subsystems, there may be several different processes that need to be modeled, individually and interactively. For instance, this waste package will probably consist of a waste form such as borosilicate glass containing the radioisotopes, a canister, an overpack material such as steel or copper, and a buffer material such as bentonite. The processes to be modeled at the waste package scale include radioisotope inventory and decay, thermal radiation, radiolysis effects, corrosion, leading and fluid flow. In tracing radionuclide transport through rock, the processes of importance are probably groundwater flow, and sorption and retardation of radionuclide movement

  13. Improving the performance of sorter systems by scheduling inbound containers

    NARCIS (Netherlands)

    Haneyah, S.W.A.; Schutten, Johannes M.J.; Fikse, K.

    2013-01-01

    This paper addresses the inbound containers scheduling problem for automated sorter systems in two different industrial sectors: parcel & postal sorting and baggage handling. We build on existing literature, particularly on the dynamic load balancing algorithm designed for the parcel hub scheduling

  14. Performance assessment of Mochovce repository

    Energy Technology Data Exchange (ETDEWEB)

    Mrskova, A; Hanusik, V [Dept. of Accident Management and Risk Assessment, Vyskumny Ustav Jadrovych Elektrarni, Trnava (Slovakia)

    2000-07-01

    The near-surface disposal site at Mochovce is designed for low-level and intermediate level radioactive waste. It is a vault-type concrete structure housing the reinforced concrete containers as the final waste packages. This paper shortly presents the long-term safety analysis methods applied for the post-closure phase of the repository. The main aim of paper is description of the philosophy of analysis, development of the scenarios, their modeling and comparing of the results of normal evolution scenario, alternative scenario and intruders scenario for some radionuclides. (author)

  15. Performance assessment of Mochovce repository

    International Nuclear Information System (INIS)

    Mrskova, A.; Hanusik, V.

    2000-01-01

    The near-surface disposal site at Mochovce is designed for low-level and intermediate level radioactive waste. It is a vault-type concrete structure housing the reinforced concrete containers as the final waste packages. This paper shortly presents the long-term safety analysis methods applied for the post-closure phase of the repository. The main aim of paper is description of the philosophy of analysis, development of the scenarios, their modeling and comparing of the results of normal evolution scenario, alternative scenario and intruders scenario for some radionuclides. (author)

  16. Serviceability design load factors and reliability assessments for reinforced concrete containment structures

    International Nuclear Information System (INIS)

    Han Bong Koo

    1998-01-01

    A reinforced concrete nuclear power plant containment structure is subjected to various random static and stochastic loads during its lifetime. Since these loads involve inherent randomness and other uncertainties, an appropriate probabilistic model for each load must be established in order to perform reliability analysis. The current ASME code for reinforced concrete containment structures are not based on probability concepts. The stochastic nature of natural hazard or accidental loads and the variations of material properties require a probabilistic approach for a rational assessment of structural safety and performance. The paper develops probability-based load factors for the limit state design of reinforced concrete containment structures. The purpose of constructing reinforced concrete containment structure is to protect against radioactive release, and so the use of a serviceability limit state against crack failure that can cause the emission of radioactive materials is suggested as a critical limit state for reinforced concrete containment structures. Load factors for the design of reinforced concrete containment structures are proposed and carried out the reliability assessments. (orig.)

  17. Analytical predictions for the performance of a reinforced concrete containment model subject to overpressurization

    International Nuclear Information System (INIS)

    Weatherby, J.R.; Clauss, D.B.

    1987-01-01

    Under the sponsorship of the US Nuclear Regulatory Commission, Sandia National Laboratories is investigating methods for predicting the structural performance of nuclear reactor containment buildings under hypothesized severe accident conditions. As part of this program, a 1/6th-scale reinforced concrete containment model will be pressurized to failure in early 1987. Data generated by the test will be compared to analytical predictions of the structural response in order to assess the accuracy and reliability of the analytical techniques. As part of the pretest analysis effort, Sandia has conducted a number of analyses of the containment structure using the ABAQUS general purpose finite element code. This paper describes results from a nonlinear axisymmetric shell analysis as well as the material models and failure criteria used in conjunction with the analysis

  18. Contractor Performance Assessment Reporting System

    Data.gov (United States)

    US Agency for International Development — CPARS is a web-based system used to input data on contractor performance. Reports from the system are used as an aid in awarding contracts to contractors that...

  19. Performance Assessment in Courts - The Swiss Case

    Directory of Open Access Journals (Sweden)

    Andreas Lienhard

    2014-12-01

    Full Text Available Abstract Performance assessments have become commonplace in management, even in the public sector. With the increasing pressure on courts to perform while making efficient use of resources, performance assessments in the justice system are also gaining in importance. However, the need for judicial independence poses special challenges for performance assessments in courts. Against this background, this article conducts a constitutional appraisal, and contrasts the need for judicial independence with the principles governing effectiveness and efficiency, self-government and supervision, and appointment and re-appointment. A duty to guarantee justice can be derived from this that does not in principle exclude the performance assessment of judges, but even renders it essential, subject to compliance with certain requirements. In these circumstances, it seems hardly surprising that numerous countries conduct performance assessments of judges and also that various international institutions have developed principles for this purpose, a summary of which is presented – in Switzerland’s case based on a recently conducted survey. In the field of conflict between the guaranteeing justice and protecting the judiciary, the following key questions arise in particular: What is the purpose of performance assessments and what are the consequences?What is subjected to a performance assessment and what are the assessment criteria?How is performance recorded as the basis for the performance assessment?Who is subjected to a performance assessment, and must a distinction be made between judges in higher and lower courts?Who carries out the performance assessment and what methods of protecting one’s rights are available?Who should receive the results of the performance assessment?The contribution sketches out possible answers to these key questions and aims to encourage academics and practitioners to give further consideration to this subject.

  20. VISUAL ART TEACHERS AND PERFORMANCE ASSESSMENT ...

    African Journals Online (AJOL)

    Charles

    qualitative research design; an aspect of descriptive survey research aiming at ... the competence and use of assessment strategies is determined by the type of ... Visual Art Teachers and Performance Assessment Methods in Nigerian Senior ...

  1. Expert judgement in performance assessment

    International Nuclear Information System (INIS)

    Wilmot, R.D.; Galson, D.A.

    2000-01-01

    This report is a pilot study that systematically describes the various types of expert judgement that are made throughout the development of a PA, and summarizes existing tools and practices for dealing with expert judgements. The report also includes recommendations for further work in the area of expert judgement. Expert judgements can be classified in a number of ways, including classification according to why the judgements are made and according to how the judgements are made. In terms of why judgements are made, there is a broad distinction between: Judgements concerning data that are made because alternatives are not feasible; and Judgements about the conduct of a PA that are made because there are no alternative approaches for making the decision. In the case of how judgements are made, the report distinguishes between non-elicited judgements made by individuals, non-elicited judgements made by groups, and elicited judgements made by individuals or groups. These types of judgement can generally be distinguished by the extent of the associated documentation, and hence their traceability. Tools for assessing judgements vary depending on the type of judgements being examined. Key tools are peer review, an appropriate QA regime, documentation, and elicitation. Dialogue with stake holders is also identified as important in establishing whether judgements are justified in the context in which they are used. The PA process comprises a number of stages, from establishing the assessment context, through site selection and repository design, to scenario and model development and parametrisation. The report discusses how judgements are used in each of these stages, and identifies which of the tools and procedures for assessing judgements are most appropriate at each stage. Recommendations for further work include the conduct of a trial expert elicitation to gain experience in the advantages and disadvantages of this technique, the development of guidance for peer

  2. Expert judgement in performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Wilmot, R.D.; Galson, D.A. [Galson Sciences Ltd, Oakham (United Kingdom)

    2000-01-01

    This report is a pilot study that systematically describes the various types of expert judgement that are made throughout the development of a PA, and summarizes existing tools and practices for dealing with expert judgements. The report also includes recommendations for further work in the area of expert judgement. Expert judgements can be classified in a number of ways, including classification according to why the judgements are made and according to how the judgements are made. In terms of why judgements are made, there is a broad distinction between: Judgements concerning data that are made because alternatives are not feasible; and Judgements about the conduct of a PA that are made because there are no alternative approaches for making the decision. In the case of how judgements are made, the report distinguishes between non-elicited judgements made by individuals, non-elicited judgements made by groups, and elicited judgements made by individuals or groups. These types of judgement can generally be distinguished by the extent of the associated documentation, and hence their traceability. Tools for assessing judgements vary depending on the type of judgements being examined. Key tools are peer review, an appropriate QA regime, documentation, and elicitation. Dialogue with stake holders is also identified as important in establishing whether judgements are justified in the context in which they are used. The PA process comprises a number of stages, from establishing the assessment context, through site selection and repository design, to scenario and model development and parametrisation. The report discusses how judgements are used in each of these stages, and identifies which of the tools and procedures for assessing judgements are most appropriate at each stage. Recommendations for further work include the conduct of a trial expert elicitation to gain experience in the advantages and disadvantages of this technique, the development of guidance for peer

  3. Reliability assessment of Passive Containment Cooling System of an Advanced Reactor using APSRA methodology

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, Mukesh, E-mail: mukeshd@barc.gov.in [Reactor Engineering Division, Bhabha Atomic Research Centre, Mumbai 400085 (India); Chakravarty, Aranyak [School of Nuclear Studies and Application, Jadavpur University, Kolkata 700032 (India); Nayak, A.K. [Reactor Engineering Division, Bhabha Atomic Research Centre, Mumbai 400085 (India); Prasad, Hari; Gopika, V. [Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai 400085 (India)

    2014-10-15

    Highlights: • The paper deals with the reliability assessment of Passive Containment Cooling System of Advanced Heavy Water Reactor. • Assessment of Passive System ReliAbility (APSRA) methodology is used for reliability assessment. • Performance assessment of the PCCS is initially performed during a postulated design basis LOCA. • The parameters affecting the system performance are then identified and considered for further analysis. • The failure probabilities of the various components are assessed through a classical PSA treatment using generic data. - Abstract: Passive Systems are increasingly playing a prominent role in the advanced nuclear reactor systems and are being utilised in normal operations as well as safety systems of the reactors following an accident. The Passive Containment Cooling System (PCCS) is one of the several passive safety features in an Advanced Reactor (AHWR). In this paper, the APSRA methodology has been employed for reliability evaluation of the PCCS of AHWR. Performance assessment of the PCCS is initially performed during a postulated design basis LOCA using the best-estimate code RELAP5/Mod 3.2. The parameters affecting the system performance are then identified and considered for further analysis. Based on some pre-determined failure criterion, the failure surface for the system is predicted using the best-estimate code taking into account the deviations of the identified parameters from their nominal states as well as the model uncertainties inherent to the best estimate code. Root diagnosis is then carried out to determine the various failure causes, which occurs mainly due to malfunctioning of mechanical components. The failure probabilities of the various components are assessed through a classical PSA treatment using generic data. The reliability of the PCCS is then evaluated from the probability of availability of these components.

  4. Reliability assessment of Passive Containment Cooling System of an Advanced Reactor using APSRA methodology

    International Nuclear Information System (INIS)

    Kumar, Mukesh; Chakravarty, Aranyak; Nayak, A.K.; Prasad, Hari; Gopika, V.

    2014-01-01

    Highlights: • The paper deals with the reliability assessment of Passive Containment Cooling System of Advanced Heavy Water Reactor. • Assessment of Passive System ReliAbility (APSRA) methodology is used for reliability assessment. • Performance assessment of the PCCS is initially performed during a postulated design basis LOCA. • The parameters affecting the system performance are then identified and considered for further analysis. • The failure probabilities of the various components are assessed through a classical PSA treatment using generic data. - Abstract: Passive Systems are increasingly playing a prominent role in the advanced nuclear reactor systems and are being utilised in normal operations as well as safety systems of the reactors following an accident. The Passive Containment Cooling System (PCCS) is one of the several passive safety features in an Advanced Reactor (AHWR). In this paper, the APSRA methodology has been employed for reliability evaluation of the PCCS of AHWR. Performance assessment of the PCCS is initially performed during a postulated design basis LOCA using the best-estimate code RELAP5/Mod 3.2. The parameters affecting the system performance are then identified and considered for further analysis. Based on some pre-determined failure criterion, the failure surface for the system is predicted using the best-estimate code taking into account the deviations of the identified parameters from their nominal states as well as the model uncertainties inherent to the best estimate code. Root diagnosis is then carried out to determine the various failure causes, which occurs mainly due to malfunctioning of mechanical components. The failure probabilities of the various components are assessed through a classical PSA treatment using generic data. The reliability of the PCCS is then evaluated from the probability of availability of these components

  5. Assessing school performance and motivation

    OpenAIRE

    Pavelková, Isabella; Kubíková, Katerina

    2016-01-01

    We verify the theoretical hypothesis that individual reference norm helps the development of positive achievement motivation and lowers the performance fear of pupils. The research was carried out with pupils aged 9 to 12 years. The article presents the results of the research in using reference norms with 61 teachers in connection with achievement motivation of their 1144 pupils. The research also mapped the real school situations for the teachers involved, based partly on observation during...

  6. Development of Seismic Safety Assessment Technology for Containment Structure

    Energy Technology Data Exchange (ETDEWEB)

    Jang, J.B.; Suh, Y.P.; Lee, J.R. [Korea Electric Power Research Institute, Taejon (Korea)

    2002-07-01

    This final report is made based on the research results of seismic analysis and seismic margin assessment field, carried out during 3rd stage ('01.4.1{approx}'02.3.31) under financial support of MOST(Ministry of Science and Technology). The objective of this research is to develop the soil - structure interaction analysis technique with high reliability, the main research subjects, performed during 3rd stage are as follows. 1) Preparation of user's guide manual for SSI analysis with high accuracy. 2) Sensitivity analysis of effective shear strain and seismic input motion. 3) Database construction of Hualien earthquake recorded data. (author). 21 refs., 27 figs., 2 tabs.

  7. Fatigue life assessment of free spanning pipelines containing corrosion defects

    Energy Technology Data Exchange (ETDEWEB)

    Lopes, Rita de Kassia D.; Campello, Georga C.; Matt, Cyntia G. da Costa; Benjamin, Adilson C.; Franciss, Ricardo [PETROBRAS S.A., Rio de Janeiro, RJ (Brazil). Centro de Pesquisas (CENPES)

    2009-12-19

    The free spanning pipelines assessment is a highlighted issue to be considered during the project and maintenance of the submarine pipelines. It is required to evaluate the fatigue life and the maximum stress due to VIV (Vortex Induced Vibration) as well as wave forces when applicable in case of shallow water. The code DNV-RP-F105 (2006) presents a methodology to calculate the fatigue life for free spanning pipelines. Such methodology however considers the pipe with no kind of defects. Nevertheless, sometimes corrosion defects are detected in periodic inspections and therefore their effects need to be taken into account in the fatigue life evaluation. The purpose of this paper thus is to present a procedure to assess the influence of the corrosion defects in the fatigue life of free spanning pipelines. Some FE analyses were performed to determine the stress concentrate factor (SCF) of the corrosion defects, which were used as input in the methodology presented in the code DNV-RP-F105 (2006). Curves of damage and so lifetime have been generated as function of the span length and water depth. As a practical application, this methodology was applied to a sub sea pipeline with several corrosion defects, localized in shallow water offshore Brazil. (author)

  8. The achievement and assessment of safety in systems containing software

    International Nuclear Information System (INIS)

    Ball, A.; Dale, C.J.; Butterfield, M.H.

    1986-01-01

    In order to establish confidence in the safe operation of a reactor protection system, there is a need to establish, as far as it is possible, that: (i) the algorithms used are correct; (ii) the system is a correct implementation of the algorithms; and (iii) the hardware is sufficiently reliable. This paper concentrates principally on the second of these, as it applies to the software aspect of the more accurate and complex trip functions to be performed by modern reactor protection systems. In order to engineer safety into software, there is a need to use a development strategy which will stand a high chance of achieving a correct implementation of the trip algorithms. This paper describes three broad methodologies by which it is possible to enhance the integrity of software: fault avoidance, fault tolerance and fault removal. Fault avoidance is concerned with making the software as fault free as possible by appropriate choice of specification, design and implementation methods. A fault tolerant strategy may be advisable in many safety critical applications, in order to guard against residual faults present in the software of the installed system. Fault detection and removal techniques are used to remove as many faults as possible of those introduced during software development. The paper also discusses safety and reliability assessment as it applies to software, outlining the various approaches available. Finally, there is an outline of a research project underway in the UKAEA which is intended to assess methods for developing and testing safety and protection systems involving software. (author)

  9. Performance assessment in algebra learning process

    Science.gov (United States)

    Lestariani, Ida; Sujadi, Imam; Pramudya, Ikrar

    2017-12-01

    The purpose of research to describe the implementation of performance assessment on algebra learning process. The subject in this research is math educator of SMAN 1 Ngawi class X. This research includes descriptive qualitative research type. Techniques of data collecting are done by observation method, interview, and documentation. Data analysis technique is done by data reduction, data presentation, and conclusion. The results showed any indication that the steps taken by the educator in applying the performance assessment are 1) preparing individual worksheets and group worksheets, 2) preparing rubric assessments for independent worksheets and groups and 3) making performance assessments rubric to learners’ performance results with individual or groups task.

  10. Operational human performance reliability assessment (OHPRA)

    International Nuclear Information System (INIS)

    Haas, P.M.; Swanson, P.J.; Connelly, E.M.

    1993-01-01

    Operational Human Performance Reliability Assessment (OHPRA) is an approach for assessing human performance that is being developed in response to demands from modern process industries for practical and effective tools to assess and improve human performance, and therefore overall system performance and safety. The single most distinguishing feature of the approach is that is defines human performance in open-quotes operationalclose quotes terms. OHPRA is focused not on generation of human error probabilities, but on practical analysis of human performance to aid management in (1) identifying open-quotes fixableclose quotes problems and (2) providing input on the importance and nature of potential improvements. Development of the model in progress uses a unique approach for eliciting expert strategies for assessing performance. A PC-based model incorporating this expertise is planned. A preliminary version of the approach has already been used successfully to identify practical human performance problems in reactor and chemical process plant operations

  11. Life cycle assessment of façade coating systems containing manufactured nanomaterials

    Energy Technology Data Exchange (ETDEWEB)

    Hischier, Roland, E-mail: roland.hischier@empa.ch; Nowack, Bernd [Swiss Federal Laboratories for Materials Science and Technology (Empa), Technology and Society Lab (TSL) (Switzerland); Gottschalk, Fadri [ETSS (Switzerland); Hincapie, Ingrid [Swiss Federal Laboratories for Materials Science and Technology (Empa), Technology and Society Lab (TSL) (Switzerland); Steinfeldt, Michael [University of Bremen FB 4/FG 10 Technological Design and Development (Germany); Som, Claudia [Swiss Federal Laboratories for Materials Science and Technology (Empa), Technology and Society Lab (TSL) (Switzerland)

    2015-02-15

    Nanotechnologies are expected to hold considerable potential for the development of new materials in the construction sector. Up to now the environmental benefits and risks of products containing manufactured nanomaterials (MNM) have been quantified only to a limited extent. This study aims to assess the potential environmental, health and safety impacts of coatings containing MNM using Life-cycle assessment: Do paints containing MNM result in a better environmental performance than paints not containing MNM? The study shows that the results depend on a number of factors: (i) The MNM have to substitute an (active) ingredient of the initial paint composition and not simply be an additional ingredient. (ii) The new composition has to extend the lifetime of the paint for such a time period that the consumption of paint along the life cycle of a building is reduced. (iii) Releases of MNM have to be reduced to the lowest level possible (in particular by dumping unused paint together with the packaging). Only when all these boundary conditions are fulfilled, which is the case only for one of the three paint systems examined, is an improved environmental performance of the MNM-containing paint possible for the paint compositions examined in this study.

  12. Engineering Performance of High Strength Concrete Containing Steel Fibre Reinforcement

    Directory of Open Access Journals (Sweden)

    Md Azree Othuman Mydin

    2013-09-01

    Full Text Available The development and utilization of the high strength concrete in the construction industry have been increasing rapidly. Fiber reinforced concrete is introduced to overcome the weakness of the conventional concrete because concrete normally can crack under a low tensile force and it is known to be brittle. Steel fibre is proved to be the popular and best combination in the high strength concrete to result the best in the mechanical and durability properties of high strength concrete with consideration of curing time, steel fibre geometry, concrete grade and else more. The incorporation of steel fibre in the mortar mixture is known as steel fibre reinforced concrete have the potential to produce improvement in the workability, strength, ductility and the deformation of high strength concrete. Besides that, steel fibre also increases the tensile strength of concrete and improves the mechanical properties of the steel fibre reinforced concrete. The range for any high strength concrete is between 60MPa-100MPa. Steel fibre reinforced concrete which contains straight fibres has poorer physical properties than that containing hooked end stainless steel fibre due to the length and the hooked steel fibre provide a better effective aspects ratio. Normally, steel fibre tensile strength is in the range of 1100MPa-1700MPa. Addition of less steel fibre volumes in the range of 0.5% to 1.0% can produce better increase in the flexural fatigue strength. The strength can be increased with addition of steel fibre up to certain percentage. This paper will review and present some basic properties of steel fibre reinforced concrete such as mechanical, workability and durability properties.

  13. Performance assessment of a microsprinkler

    Directory of Open Access Journals (Sweden)

    Edivaldo Lopes Thomaz

    2014-04-01

    Full Text Available Surface hydrological processes are essential to the understanding and prediction of soil erosion. Several equipments are used to measure infiltration rate, runoff and soil loss. However, researchers build their own equipment due to the specific sites where the measurements are performed. This study evaluated the performance of a microsprinkler developed to measure the hydrological processes on unpaved rural roads. The microsprinkler is portable, lightweight, easy to operate, and also low cost. The measured parameters refer to different physical aspects of the rainfall produced as: intensity, drop size, kinetic energy and the simulation area. The microsprinkler was tested at different heights and pressures. The main results obtained: the intensity of simulated rainfall was 71.4 - 148.3 mmh-1, the drop size ranged from 0.3 to 1.2 mm (mean 0.7 mm, the kinetic energy of rainfall varied between 51 and 77% compared with a natural rainfall of similar intensity, and the simulation area had 0.28 - 0.56 m2 (mean 0.40 m2. The parameters obtained in this study are within the limit of others simulators reported in the literature.

  14. Nitrogen-containing hydrothermal carbons with superior performance in supercapacitors

    Energy Technology Data Exchange (ETDEWEB)

    Zhao, Li [Colloid Chemistry Department, Max-Planck Institute for Colloids and Interfaces, Am Muehlenberg 1, 14424 Potsdam (Germany); Institute of Coal Chemistry, Chinese Academy of Sciences, 27th Taoyuan South Road, 030001 Taiyuan (China); Fan, Li-Zhen; Zhou, Meng-Qi; Guan, Hui; Qiao, Suyan [School of Materials Science and Engineering, University of Science and Technology Beijing, 100083 Beijing (China); Antonietti, Markus; Titirici, Maria-Magdalena [Colloid Chemistry Department, Max-Planck Institute for Colloids and Interfaces, Am Muehlenberg 1, 14424 Potsdam (Germany)

    2010-12-01

    Microporous nitrogen-doped carbons produced by hydrothermal carbonization of biomass derivative followed by chemical activation showed excellent supercapacitive capacitance performance both in acid and base electrolytes. (Copyright copyright 2010 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  15. Assessment of severe accident prevention and mitigation features: PWR, large dry containment design

    International Nuclear Information System (INIS)

    Perkins, K.R.; Hsu, C.J.; Lehner, J.R.; Luckas, W.J.; Cho, N.; Fitzpatrick, R.G.; Pratt, W.T.; Eltawila, F.; Maly, J.A.

    1988-07-01

    Plant features and operator actions which have been found to be important in either preventing or mitigating severe accidents in PWRs with large dry containments have been identified. These features and actions were developed from insights derived from reviews of risk assessments performed specifically for the Zion plant and from assessments of other relevant studies. Accident sequences that dominate the core-damage frequency and those accident sequences that are of potentially high consequence were identified. Vulnerabilities of the large dry containment to severe accident containment loads were also identified. In addition, those features of a PWR with a large dry containment, which are important for preventing core damage and are available for mitigating fission-product release to the environment were identified. The report is issued to provide focus to the analyst examining an individual plant. The report calls attention to plant features and operator actions and provides a list of deterministic tributes for assessing those features and actions found to be helpful in reducing the overall risk for Zion and other PWRs with large dry containments. Thus, the guidance is offered as a resource in examining the subject plant to determine if the same, or similar, plant features and operator actions will be of value in reducing overall plant risk. This report is intended to serve solely as guidance

  16. Assessment of severe accident prevention and mitigation features: PWR, ice-condenser containment design

    International Nuclear Information System (INIS)

    Hsu, C.J.; Perkins, K.R.; Luckas, W.J.; Fitzpatrick, R.G.; Cho, N.; Lehner, J.R.; Pratt, W.T.; Eltawila, F.; Maly, J.A.

    1988-07-01

    Plant features and operator actions which have been found to be important in either preventing and mitigating severe accidents in PWRs with ice-condenser containments have been identified. Thus features and actions were developed from insights derived from reviews of risk assessments performed specifically for the Sequoyah plant and from assessments of other relevant studies. Accident sequences that dominate the core-damage frequency and those accident sequences that are of potentially high consequence were identified. Vulnerabilities of the ice-condenser containment to sever accident containment loads were also identified. In addition, those features of a PWR with an ice-condenser containment, which are important for preventing core damage and are available for mitigating fission-product release to the environment were identified. This report is issued to provide focus to an analyst examining an individual plant. The report calls attention to plant features and operator actions and provides a list of deterministic attributes for assessing those features and actions found to be helpful in reducing the overall risk for Sequoyah and other PWRs with ice-condenser containments. Thus, the guidance is offered as a resource in examining the subject plant to determine if the same, or similar, plant features and operator actions will be of value in reducing overall plant risk. This report is intended to serve solely as guidance. 14 tabs

  17. Competency Assessment Using Key Performance Indicators

    OpenAIRE

    Elena Alexandra Toader; Laura Brad

    2015-01-01

    The paper proposes a method for computing the scores of the key performance indicators resulted in the competency assessment process. The key performance indicators are estimated considering four performance levels that an IT professional can obtain at the end of the assessment process. We suggest as the best approach for estimating the performance key indicators an online questionnaire filled by 60 employees that work in IT Romanian companies. The results provide evidence that the difference...

  18. Probabilistic assessments of fuel performance

    International Nuclear Information System (INIS)

    Kelppe, S.; Ranta-Puska, K.

    1998-01-01

    The probabilistic Monte Carlo Method, coupled with quasi-random sampling, is applied for the fuel performance analyses. By using known distributions of fabrication parameters and real power histories with their randomly selected combinations, and by making a large number of ENIGMA code calculations, one expects to find out the state of the whole reactor fuel. Good statistics requires thousands of runs. A sample case representing VVER-440 reactor fuel indicates relatively low fuel temperatures and mainly athermal fission gas release if any. The rod internal pressure remains typically below 2.5 MPa, which leaves a large margin to the system pressure of 12 MPa Gap conductance, an essential parameter in the accident evaluations, shows no decrease from its start-of-life value. (orig.)

  19. Thermal performance enhancement in nanofluids containing diamond nanoparticles

    International Nuclear Information System (INIS)

    Xie Huaqing; Yu Wei; Li Yang

    2009-01-01

    Nanofluids, nanoparticle suspensions prepared by dispersing nanoscale particles in a base fluid, have been gaining interest lately due to their potential to greatly outperform traditional thermal transport liquids. Diamond has the highest thermal transport capacity in nature and diamond particles are often used as filler in mixtures for upgrading the performance of a matrix. It is reasonable to expect that the addition of diamond nanoparticles (DNPs) would lead to thermal performance enhancement in a base fluid. In this study, homogeneous and stable nanofluids composed of DNPs as the inclusions and a mixture of ethylene glycol (EG) and water as base fluid have been prepared. Acid mixtures of perchloric acid, nitric acid and hydrochloric acid were employed to purify and tailor the DNPs to eliminate impurities and to enhance their dispersibilty. Ultrasound and the alkalinity of solution are beneficial to the deaggregation of the soft DNP aggregations. The thermal conductivity enhancement of the DNP nanofluids increases with DNP loading and the thermal conductivity enhancement is more than 18.0% for a nanofluid at a DNP volume fraction of 0.02. Viscosity measurements show that the DNP nanofluids demonstrate Newtonian behaviour, and the viscosity significantly decreases with temperature. With increasing volume fraction of DNPs, the convective heat transfer coefficient increases first, and then decreases with a further increase in the volume fraction of DNPs. The nanofluid with a volume fraction of 0.005 has optimal overall thermal performance.

  20. Containment performance observations and insights of LWRs based on the IPEs

    International Nuclear Information System (INIS)

    Lehner, J.; Pratt, W.T.; Lane, J.; Chow, E.; Ridgely, J.

    1994-01-01

    Generic Letter 88-20, open-quotes Individual Plant Examination for Severe Accident Vulnerabilities - 10CFR 50.54(f),close quotes requesting the IPEs, was issued by the NRC on November 23, 1988. U.S. licensee were requested to conduct an Individual Plant Examination (IPE) in order to identify potential severe accident vulnerabilities at their plant and to implement cost-effective plant improvements to reduce or eliminate these vulnerabilities. Supplements to the Generic Letter forwarded technical insights obtained by the NRC staff through its Containment Performance Improvement (CPI) program. These insights were deemed important enough by the staff to bring to the attention of the licensees for use, as they deemed appropriate, in the IPEs which they were preparing. Coupled to their Level 1 results, licensees were requested to report the results of their analyses regarding containment performance. These results included those related to the general methodology used, plant data, plant features, plant damage states, models and methods used in the accident progression analysis, containment failure characterization, containment event trees and their end states, and radionuclide release characterization. At this time, most of the IPEs have been submitted by the licensees. In a follow-up effort to support regulatory activities, the NRC staff with assistance from Brookhaven National Laboratory, has initiated a program involving a global examination of the containment performance results documented in the IPEs. The objective is to identify insights of potential generic safety significance relative to plant design, operation and maintenance, as well as to assess response to the previously forwarded CPI insights

  1. Performance Assessment of Mergers and Acquisitions

    DEFF Research Database (Denmark)

    Wang, Daojuan; Moini, Hamid

    2012-01-01

    on the performance measures and benchmarks adopted in M&A research field and the relevant empirical results. We find that the definitions of performance varied in terms of accounting, financial, operational and perceptual metrics. And performance assessment is sensitive to the definition of performance, methodology......Corporate mergers and acquisitions (M&As) have been increasing popular during these decades. However, a majority of research show failure rate (40% - 80%) has not significantly changed. This “success paradox” triggers us to reflect on performance assessment of M&As: how the performance of M...

  2. The Effects of Performance-Based Assessment Criteria on Student Performance and Self-Assessment Skills

    Science.gov (United States)

    Fastre, Greet Mia Jos; van der Klink, Marcel R.; van Merrienboer, Jeroen J. G.

    2010-01-01

    This study investigated the effect of performance-based versus competence-based assessment criteria on task performance and self-assessment skills among 39 novice secondary vocational education students in the domain of nursing and care. In a performance-based assessment group students are provided with a preset list of performance-based…

  3. Identification and assessment of containment and release management strategies

    International Nuclear Information System (INIS)

    Lehner, J.R.; Lin, C.C.; Neogy, P.

    1990-01-01

    Brookhaven National Laboratory, under the auspices of the U.S. Nuclear Regulatory Commission, is investigating accident management strategies which could help preserve containment integrity or minimize releases during a severe accident. The objective is to make use of existing plant systems and equipment in innovative ways to reduce the likelihood of containment failure or to mitigate the release of fission products to the environment if failure cannot be prevented. Many of these strategies would be implemented during the later stages of a severe accident (i.e., after vessel breach) and sizeable uncertainties exist regarding some of the phenomena involved. A majority of the strategies identified go well beyond existing procedures and often depend on the specific containment type. Strategies for all of the five different containments used in the U.S. are being considered: BWR Mark I, Mark II, and Mark III, as well as PWR ice condenser and large dry containments. Accident management strategies related to the in-vessel phase of a severe core melt accident are being dealt with under another NRC program. For each containment type the most likely challenges are identified and existing emergency guidelines and procedures are reviewed as to how they address these challenges

  4. Microstructure of ultra high performance concrete containing lithium slag.

    Science.gov (United States)

    He, Zhi-Hai; Du, Shi-Gui; Chen, Deng

    2018-04-03

    Lithium slag (LS) is discharged as a byproduct in the process of the lithium carbonate, and it is very urgent to explore an efficient way to recycle LS in order to protect the environments and save resources. Many available supplementary cementitious materials for partial replacement of cement and/or silica fume (SF) can be used to prepare ultra high performance concrete (UHPC). The effect of LS to replace SF partially by weight used as a supplementary cementitious material (0%, 5%, 10% and 15% of binder) on the compressive strengths and microstructure evolution of UHPC has experimentally been studied by multi-techniques including mercury intrusion porosimetry, scanning electron microscope and nanoindentation technique. The results show that the use of LS degrades the microstructure of UHPC at early ages, and however, the use of LS with the appropriate content improves microstructure of UHPC at later ages. The hydration products of UHPC are mainly dominated by ultra-high density calcium-silicate-hydrate (UHD C-S-H) and interfacial transition zone (ITZ) in UHPC has similar compact microstructure with the matrix. The use of LS improves the hydration degree of UHPC and increases the elastic modulus of ITZ in UHPC. LS is a promising substitute for SF for preparation UHPC. Copyright © 2018 Elsevier B.V. All rights reserved.

  5. Assessment of the sealing system of an ilw transport container in a 9m regulatory impact

    International Nuclear Information System (INIS)

    Sievwright, R.W.T.; Gray, I.L.S.; Bernasconi, D.J.; McGuinn, P.; Tso, C.F.

    1998-01-01

    UK Nirex Ltd is developing a range of reusable shielded transport containers (RSTCs) to ensure the safe transport of immobilised intermediate level waste to a future UK deep repository for disposal. The RSTCs use an inset lid for mechanical strength and radiation shielding, but the containment boundary is provided by a separate lid seal member (LSM). The LSM is a semi-flexible steel diaphragm surrounded by a rim which carries a double O-ring seal. The LSM rim is clamped to a flat mating surface on the container body. A finite element model has been developed for an RSTC with a wall thickness of 285 mm, in order to assess its containment performance in 9m regulatory drop tests (IAEA 1996). The challenge was to predict the size of small gaps that might appear between the LSM rim and the RSTC body seal face ; this level of detail would be 1-2 orders of magnitude smaller than the displacements experienced in the impact zone. The model was first validated against a series of one-third scale model drop tests of the RSTC. The validated model was then analysed for 9m regulatory impacts in the six worst impact attitudes. The behavior of the LSM was assessed for each attitude and the seal face (gaps) between the LSM and the body were determined. Although small gaps of about 0.5 mm are predicted, it is likely that containment would be preserved. (authors)

  6. Annual Performance Reports: 2002-2003 State Assessment Data

    Science.gov (United States)

    Thurlow, Martha L.; Moen, Ross E.; Wiley, Hilda I.

    2005-01-01

    States and other educational entities receiving Part B funding under the Individuals with Disabilities Education Act (IDEA) submitted their Annual Performance Reports to the U.S. Secretary of Education on or before March 31, 2004. These reports contained information on a variety of indicators, including assessment participation and performance…

  7. Numerical simulation of radioisotope's dependency on containment performance for large dry PWR containment under severe accidents

    Energy Technology Data Exchange (ETDEWEB)

    Mehboob, Khurram, E-mail: khurramhrbeu@gmail.com [College of Nuclear Science and Technology, Harbin Engineering University, 145-31 Nantong Street, Nangang District, Harbin, Heilongjiang 150001 (China); Xinrong, Cao [College of Nuclear Science and Technology, Harbin Engineering University, 145-31 Nantong Street, Nangang District, Harbin, Heilongjiang 150001 (China); Ahmed, Raheel [College of Automation, Harbin Engineering University, 145-31 Nantong Street, Nangang District, Harbin, Heilongjiang 150001 (China); Ali, Majid [College of Nuclear Science and Technology, Harbin Engineering University, 145-31 Nantong Street, Nangang District, Harbin, Heilongjiang 150001 (China)

    2013-09-15

    Highlights: • Calculation and comparison of activity of BURN-UP code with ORIGEN2 code. • Development of SASTC computer code. • Radioisotopes dependency on containment ESFs. • Mitigation in atmospheric release with ESFs operation. • Variation in radioisotopes source term with spray flow and pH value. -- Abstract: During the core melt accidents large amount of fission products can be released into the containment building. These fission products escape into the environment to contribute in accident source term. The mitigation in environmental release is demanded for such radiological consequences. Thus, countermeasures to source term, mitigations of release of radioactivity have been studied for 1000 MWe PWR reactor. The procedure of study is divided into five steps: (1) calculation and verification of core inventory, evaluated by BURN-UP code, (2) containment modeling based on radioactivity removal factors, (3) selection of potential accidents initiates the severe accident, (4) calculation of release of radioactivity, (5) study the dependency of release of radioactivity on containment engineering safety features (ESFs) inducing mitigation. Loss of coolant accident (LOCA), small break LOCA and flow blockage accidents (FBA) are selected as initiating accidents. The mitigation effect of ESFs on source term has been studied against ESFs performance. Parametric study of release of radioactivity has been carried out by modeling and simulating the containment parameters in MATLAB, which takes BURN-UP outcomes as input along with the probabilistic data. The dependency of iodine and aerosol source term on boric and caustic acid spray has been determined. The variation in source term mitigation with the variation of containment spray flow rate and pH values have been studied. The variation in containment retention factor (CRF) has also been studied with the ESF performance. A rapid decrease in source term is observed with the increase in pH value.

  8. Review of SR 97 performance assessment

    International Nuclear Information System (INIS)

    Glynn, P.D.

    2000-01-01

    This review has identified many technical problems in the SR 97 performance assessment. The general impression of this reviewer is that SKB has been disingenuous in its performance assessment effort. It has not cited important differences of opinion with its own views. Furthermore, there are many inconsistencies in the SR 97 report that all together leave the impression that there are many more uncertainties in the SR 97 performance assessment than SKB would perhaps care to admit. Additionally, despite SKB's statements to the contrary, many of the analyses conducted for the SR 97 performance assessment can be clearly shown not to have been based on 'conservative' assumptions. Finally, SKB has made little effort to consider possible coupling effects between their different scenarios in SR 97. This is a serious flaw in the SR 97 performance assessment. The comments in this review should not be taken to imply that the KBS-3 nuclear waste disposal method will not be able to meet the safety and radiation protection requirements which SKI and SSI have specified in recent years. Instead, my conclusion is simply that the SR 97 performance assessment of the KBS-3 method would have been more believable had it been based on a forthright and comprehensive discussion of facts, uncertainties and opinions, and on a more conservative choice of assumptions. As it stands, the SR 97 performance assessment is not very credible

  9. Failure assessment techniques to ensure shipping container integrity

    International Nuclear Information System (INIS)

    McConnell, P.

    1986-02-01

    This report discusses several methodologies which may be used to ensure the structural integrity of containment systems to be used for the transport and storage of high-level radioactive substances. For economic reasons, shipping containers constructed of ferritic materials are being considered for manufacture by vendors in the US and Europe. Ferritic show an inherent transition from a ductile, high energy failure mode to a brittle, low energy fracture mode with decreasing temperature. Therefore, formal consideration of means by which to avoid unstable brittle fracture is necessary prior to the licensing of ferritic casks. It is suggested that failure of a shipping container wall be defined as occurring when a flaw extends through the outer wall of the containment system. Crack initiation which may lead to unstable brittle crack growth should therefore be prevented. It is suggested that a fundamental linear elastic fracture mechanics (lefm) approach be adopted on a case-by-case basis, applied perhaps by means of appropriate modifications to ASMA Section III or Section XI. A lefm analysis requires information concerning service temperatures, loading rates, flaw sizes, and applied stresses. Tentative judgments regarding these parameters for typical shipping containers have been made

  10. Development of Integrated Assessment Technology of Risk and Performance

    International Nuclear Information System (INIS)

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

    2010-04-01

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

  11. Minimum containment pressure and its effect on ECCS performance of APR-1400

    International Nuclear Information System (INIS)

    Kim, In Goo; Bang, Young S.; Kim, Hho Jung

    2004-01-01

    The containment pressure has a strong effect on the late reheat behavior for a large break LOCA, associated with the DVI issue. The downcomer boiling, which occurs during the post-reflood phase, has a negative effect on core cooling for a LBLOCA. Because the downcomer boiling is enhanced as the containment pressure decreases, how to determine containment pressure is important to the evaluation of ECCS performance. In spite of its importance of containment pressure, there are few studies on the containment pressure and the interaction between RCS and containment thermal hydraulics. To have a better knowledge of the effect of containment pressure on APR-1400 ECCS performance, a parametric study for containment pressure has been carried out. Also, the interaction between RCS and containment behavior has been also investigated

  12. VISUAL ART TEACHERS AND PERFORMANCE ASSESSMENT ...

    African Journals Online (AJOL)

    Charles

    Senior Secondary school visual art teachers constituted the sample of this ... and Performance Assessment Methods in Nigerian Senior Secondary Schools – Bello .... definition includes knowledge, skills, attitudes, metacognition and strategic ...

  13. The link between performance assessment and quality of data

    International Nuclear Information System (INIS)

    Csullog, G.W.

    1990-11-01

    Performance assessments, using both individual and cumulative inventories, produce estimates of the risk or dose consequences for repository concepts. Unacceptable risk or dose for a given contaminant identify it as a problem contaminant. While risk or dose consequences are common outputs of safety assessments, results can also be reported as estimates of the safe inventory limit for each contaminant in a repository scenario. Once problem contaminants are identified, it may be useful to: validate the data used in the performance assessment; restrict contaminant inventories in the repository; or, improve the containment capability of the repository (including improved packaging). A key point is that performance assessments define the quality of data to be collected. If a contaminant's inventory will be far below its estimated safe inventory limit for a repository, then it is reasonable to accept inventory estimates that have high variances and low confidence. For contaminants that have a significant impact upon performance assessments, efforts must be made to provide the best inventory (source term) estimates practicable. One important goal of characterization programs should be to establish the adequacy of data used in performance assessments. There is little value in striving to improve confidence in data for some waste streams if they are assessed to have a minor impact upon repository performance. Streams that have a major impact upon performance deserve the time, attention and money to be characterized adequately. Waste acceptance must be linked to the quality of characterization data provided by generators. This link sets compliance monitoring requirements

  14. Development of an accident management expert system for containment assessment

    International Nuclear Information System (INIS)

    Nelson, W.R.; Sebo, D.E.; Haney, L.N.

    1987-01-01

    The United States Nuclear Regulatory Commission (USNRSC) is sponsoring a program at the Idaho National Engineering Laboratory (INEL) to develop an accident management expert system. The intended users of the system are the personnel of the NRC Operations Center in Washington, D.C. The expert system will be used to help NRC personnel monitor and evaluate the status and management of the containment during a severe reactor accident. The knowledge base will include severe accident knowledge regarding the maintenance of the critical safety functions, especially containment integrity, during an accident. This paper summarizes the concepts that have been developed for the accident management expert system, and the plans that have been developed for its implementation

  15. Enabling performance skills: Assessment in engineering education

    Science.gov (United States)

    Ferrone, Jenny Kristina

    Current reform in engineering education is part of a national trend emphasizing student learning as well as accountability in instruction. Assessing student performance to demonstrate accountability has become a necessity in academia. In newly adopted criterion proposed by the Accreditation Board for Engineering and Technology (ABET), undergraduates are expected to demonstrate proficiency in outcomes considered essential for graduating engineers. The case study was designed as a formative evaluation of freshman engineering students to assess the perceived effectiveness of performance skills in a design laboratory environment. The mixed methodology used both quantitative and qualitative approaches to assess students' performance skills and congruency among the respondents, based on individual, team, and faculty perceptions of team effectiveness in three ABET areas: Communications Skills. Design Skills, and Teamwork. The findings of the research were used to address future use of the assessment tool and process. The results of the study found statistically significant differences in perceptions of Teamwork Skills (p performance skills, such as teamwork, among freshman engineering students; (2) incorporate feedback into the learning process; (3) strengthen the assessment process with a follow-up plan that specifically targets performance skill deficiencies, and (4) integrate the assessment instrument and practice with ongoing curriculum development. The findings generated by this study provides engineering departments engaged in assessment activity, opportunity to reflect, refine, and develop their programs as it continues. It also extends research on ABET competencies of engineering students in an under-investigated topic of factors correlated with team processes, behavior, and student learning.

  16. Personality, Assessment Methods and Academic Performance

    Science.gov (United States)

    Furnham, Adrian; Nuygards, Sarah; Chamorro-Premuzic, Tomas

    2013-01-01

    This study examines the relationship between personality and two different academic performance (AP) assessment methods, namely exams and coursework. It aimed to examine whether the relationship between traits and AP was consistent across self-reported versus documented exam results, two different assessment techniques and across different…

  17. Nursery response of container Pinus palustris seedlings to nitrogen supply and subsequent effects on outplanting performance

    Science.gov (United States)

    D. Paul Jackson; R. Kasten Dumroese; James P. Barnett

    2012-01-01

    Container longleaf pine (Pinus palustris) seedlings often survive and grow better after outplanting than bareroot seedlings. Because of this, most longleaf pine are now produced in containers. Little is known about nursery fertilization effects on the quality of container longleaf pine seedlings and how that influences outplanting performance. We compared various...

  18. Assessing Vocal Performances Using Analytical Assessment: A Case Study

    Science.gov (United States)

    Gynnild, Vidar

    2016-01-01

    This study investigated ways to improve the appraisal of vocal performances within a national academy of music. Since a criterion-based assessment framework had already been adopted, the conceptual foundation of an assessment rubric was used as a guide in an action research project. The group of teachers involved wanted to explore thinking…

  19. Physician Performance Assessment: Prevention of Cardiovascular Disease

    Science.gov (United States)

    Lipner, Rebecca S.; Weng, Weifeng; Caverzagie, Kelly J.; Hess, Brian J.

    2013-01-01

    Given the rising burden of healthcare costs, both patients and healthcare purchasers are interested in discerning which physicians deliver quality care. We proposed a methodology to assess physician clinical performance in preventive cardiology care, and determined a benchmark for minimally acceptable performance. We used data on eight…

  20. Assessing irrigation performance by using remote sensing

    NARCIS (Netherlands)

    Bandara, K.M.P.S.

    2006-01-01

    Keywords: Performance indicators, performance assessment, diagnostic approach, SEBAL, target level, grain yield, water productivity, error estimation, spatio-temporal resolution.

    In

  1. Performing the lockout/tagout risk assessment.

    Science.gov (United States)

    Wallace, W Jon

    2007-03-01

    Lockout/tagout provides the greatest level routine, repetitive, and integral to the production process, a risk assessment should be performed. If the task performed poses an unacceptable risk, acceptable risk reduction methods should be implemented to reduce the risk to acceptable levels.

  2. Leaching assessment of road materials containing primary lead and zinc slags.

    Science.gov (United States)

    Barna, R; Moszkowicz, P; Gervais, C

    2004-01-01

    Characterisation of the leaching behaviour of waste-containing materials is a crucial step in the environmental assessment for reuse scenarios. In our research we applied the multi-step European methodology ENV 12-920 to the leaching assessment of road materials containing metallurgical slag. A Zn slag from an imperial smelting furnace (ISF) and a Pb slag from a lead blast furnace (LBF) are investigated. The two slags contain up to 11.2 wt% of lead and 3.5 wt% of zinc and were introduced as a partial substitute for sand in two road materials, namely sand-cement and sand-bitumen. At the laboratory scale, a leaching assessment was performed first through batch equilibrium leaching tests. Second, the release rate of the contaminants was evaluated using saturated leaching tests on monolithic material. Third, laboratory tests were conducted on monolithic samples under intermittent wetting conditions. Pilot-scale tests were conducted for field testing of intermittent wetting conditions. The results show that the release of Pb and Zn from the materials in a saturated scenario was controlled by the pH of the leachates. For the intermittent wetting conditions, an additional factor, blocking of the pores by precipitation during the drying phase is proposed. Pilot-scale leaching behaviour only partially matched with the laboratory-scale test results: new mass transfer mechanisms and adapted laboratory leaching tests are discussed.

  3. Assessing the credibility of diverting through containment penetrations

    International Nuclear Information System (INIS)

    Cooley, J.N.; Swindle, D.W. Jr.

    1980-01-01

    A viable approach has been developed for identifying those containment penetrations in a nuclear fuel reprocessing plant which are credible diversion routes. The approach is based upon systematic engineering and design analyses and is applied to each type of penetration to determine which penetrations could be utilized to divert nuclear material from a reprocessing facility. The approach is described and the results of an application are discussed. In addition, the concept of credibility is developed and discussed. For a typical reprocessing plant design, the number of penetrations determined to be credible without process or piping modifications was approx. 16% of the penetrations originally identified

  4. Review and assessment of thermodynamic and transport properties for the CONTAIN Code

    International Nuclear Information System (INIS)

    Valdez, G.D.

    1988-12-01

    A study was carried out to review available data and correlations on the thermodynamic and transport properties of materials applicable to the CONTAIN computer code. CONTAIN is the NRC's best-estimate, mechanistic computer code for modeling containment response to a severe accident. Where appropriate, recommendations have been made for suitable approximations for material properties of interests. Based on a modified Benedict-Webb-Rubin (BWR) equation of state, a procedure is introduced for calculating thermodynamic properties for common gases in the CONTAIN code. These gases are nitrogen, oxygen, hydrogen, carbon dioxide, carbon monoxide, steam, helium, and argon. The thermodynamic equations for density, currently represented in CONTAIN by relatively simple fits, were independently checked and are recommended to be replaced by the Lee-Kesler equation of state which substantially improves accuracy without too much sacrifice in computational efficiency. The accuracy of the calculated values have been found to be generally acceptable. Various correlations and models for single component gas transport properties, viscosity and thermal conductivity, were also assessed with available experimental data. When a suitable correlation or model was not available, transport properties were obtained by performing least-squares fit on experimental data. 50 refs., 126 figs., 3 tabs

  5. A preliminary assessment of the assignment of Intermediate Level Waste streams to designs of transport containers

    International Nuclear Information System (INIS)

    Mairs, J.H.

    1984-08-01

    This paper considers the assignment of ILW to designs of transport container. Estimates are made of the radiation levels penetrating the transport containers and assesses the duration of any storage required prior to transportation. (author)

  6. Containment Emergency Sump Performance. Technical findings related to Unresolved Safety Issue A-43. Revision 1

    International Nuclear Information System (INIS)

    1985-10-01

    This report summarizes key technical findings related to Unresolved Safety Issue (USI) A-43, Containment Emergency Sump Performance. Both BWRs and PWRs are considered in this report. Emergency core cooling systems require a clean, reliable water source to maintain long-term recirculation following a loss-of-coolant accident (LOCA). PWRs rely on the containment emergency sump to provide such a water supply to residual heat removal pumps and containment spray pumps. BWRs rely on pump suction intakes in the suppression pool or wet well to provide water to residual heat removal and core spray systems. Thus, the technical findings in this report provide information on post-LOCA recirculation. These findings have been derived from extensive experimental studies, generic plant studies, and assessments of sumps used for long-term cooling. Results of hydraulic tests have shown that the potential for air ingestion is less severe than previously hypothesized. The effects of debris blockage on NPSH margin must be dealt with on a plant-specific basis. These findings have been used to develop revisions to Regulatory Guide 1.82 and Standard Review Plan Section 6.2.2 (NUREG-0800)

  7. Aircraft Impact Assessment of APR1400 Reactor Containment Building

    International Nuclear Information System (INIS)

    Moon, Il Hwan; Kim, Do Yeon; Kim, Jae Hee; Kim, Sang Yun

    2011-01-01

    The implementation of a protection to withstand aircraft impact on safety-related structures and systems is basically based on a probabilistic evaluation for each site, if the licensing body doesn't require a deterministic approach. Existing nuclear power plants in Korea were designed based on the probabilistic approach, and the aircraft impact hazard remained less than a probability of 10 -7 . However, a man-made aircraft impact have been considered as a possible external accident for the nuclear power plant. New plant designs that are to be constructed in the U.S. after July 2009 must consider the effect of impact from a large commercial aircraft according to the requirements of 10 CFR 50.150. Especially, Reactor Containment Building (RCB) housing the safety-related equipment and fuels should be protected safely against aircraft crash without perforation and scabbing failure of external wall. APR1400 RCB is constructed as a prestressed concrete containment vessel (PCCV) which is surrounded by the auxiliary building housing additional safety-related equipment and other systems. In this study, the aircraft impact analyses for the RCB are carried out using Riera forcing function and aircraft model. Considered external wall thickness is 4 ft 6 in. for the cylindrical wall and 4 ft for the dome. Actual strengths of concrete and steel are considered as the material properties. For these analyses, the dynamic increment factor and concrete aging effect are considered in accordance with NEI 07-13(2011)

  8. Gamma camera performance: technical assessment protocol

    International Nuclear Information System (INIS)

    Bolster, A.A.; Waddington, W.A.

    1996-01-01

    This protocol addresses the performance assessment of single and dual headed gamma cameras. No attempt is made to assess the performance of any associated computing systems. Evaluations are usually performed on a gamma camera commercially available within the United Kingdom and recently installed at a clinical site. In consultation with the manufacturer, GCAT selects the site and liaises with local staff to arrange a mutually convenient time for assessment. The manufacturer is encouraged to have a representative present during the evaluation. Three to four days are typically required for the evaluation team to perform the necessary measurements. When access time is limited, the team will modify the protocol to test the camera as thoroughly as possible. Data are acquired on the camera's computer system and are subsequently transferred to the independent GCAT computer system for analysis. This transfer from site computer to the independent system is effected via a hardware interface and Interfile data transfer. (author)

  9. Gamma camera performance: technical assessment protocol

    Energy Technology Data Exchange (ETDEWEB)

    Bolster, A.A. [West Glasgow Hospitals NHS Trust, London (United Kingdom). Dept. of Clinical Physics; Waddington, W.A. [University College London Hospitals NHS Trust, London (United Kingdom). Inst. of Nuclear Medicine

    1996-12-31

    This protocol addresses the performance assessment of single and dual headed gamma cameras. No attempt is made to assess the performance of any associated computing systems. Evaluations are usually performed on a gamma camera commercially available within the United Kingdom and recently installed at a clinical site. In consultation with the manufacturer, GCAT selects the site and liaises with local staff to arrange a mutually convenient time for assessment. The manufacturer is encouraged to have a representative present during the evaluation. Three to four days are typically required for the evaluation team to perform the necessary measurements. When access time is limited, the team will modify the protocol to test the camera as thoroughly as possible. Data are acquired on the camera`s computer system and are subsequently transferred to the independent GCAT computer system for analysis. This transfer from site computer to the independent system is effected via a hardware interface and Interfile data transfer. (author).

  10. Effect of areal power density and relative humidity on corrosion resistant container performance

    International Nuclear Information System (INIS)

    Gansemer, J.D.

    1994-10-01

    The impact of the rewetting process on the performance of waste containers at the Yucca Mountain repository is analyzed. This paper explores the impact of the temperature-humidity relationships on pitting corrosion failure of stainless steel containers for different areal power densities (APDs)in the repository. It compares the likely performance of containers in a repository with a low APD, 55 Kw/acre, and a high APD, 110 kW/acre

  11. Performance of laying hens fed diets containing DAS-59122-7 maize grain compared with diets containing nontransgenic maize grain.

    Science.gov (United States)

    Jacobs, C M; Utterback, P L; Parsons, C M; Rice, D; Smith, B; Hinds, M; Liebergesell, M; Sauber, T

    2008-03-01

    An experiment using 216 Hy-Line W-36 pullets was conducted to evaluate transgenic maize grain containing the cry34Ab1 and cry35Ab1 genes from a Bacillus thuringiensis (Bt) strain and the phosphinothricin ace-tyltransferase (pat) gene from Streptomyces viridochromogenes. Expression of the cry34Ab1 and cry35Ab1 genes confers resistance to corn rootworms, and the pat gene confers tolerance to herbicides containing glufosinate-ammonium. Pullets (20 wk of age) were placed in cage lots (3 hens/cage, 2 cages/lot) and were randomly assigned to 1 of 3 corn-soybean meal dietary treatments (12 lots/treatment) formulated with the following maize grains: near-isogenic control (control), conventional maize, and transgenic test corn line 59122 containing event DAS-59122-7. Differences between 59122 and control group means were evaluated with statistical significance at P < 0.05. Body weight and gain, egg production, egg mass, and feed efficiency for hens fed the 59122 corn were not significantly different from the respective values for hens fed diets formulated with control maize grain. Egg component weights, Haugh unit measures, and egg weight class distribution were similar regardless of the corn source. This research indicates that performance of hens fed diets containing 59122 maize grain, as measured by egg production and egg quality, was similar to that of hens fed diets formulated with near-isogenic corn grain.

  12. High organic containing tanks: Assessing the hazard potential

    International Nuclear Information System (INIS)

    Hill, R.C.P.; Babad, H.

    1991-09-01

    Eight Hanford Site tanks contain organic chemicals at concentrations believed to be greater than 10 mole percent sodium acetate equivalent mixed with the oxidizing salts sodium nitrate/sodium nitrite. Also, three of the hydrogen and ferrocyanide tanks appear on the organic tank list. Concentrations of organics that may be present in some tanks could cause an exothermic reaction given a sufficient driving force, such as high temperatures. However, the difference between ignition temperatures and actual tank temperatures measured is so large that the probability of such a reaction is considered very low. The consequences of the postulated reaction are about the same as the scenarios for an explosion in a ''burping'' hydrogen tank. Although work on this issue is just beginning, consideration of hazards associated with heating nitrate-nitrite mixtures containing organic materials is an integral part of both the hydrogen and ferrocyanide tank efforts. High concentrations of organic compounds have been inferred (from tank transfer, flow sheet records, and limited analytical data) in eight single-shell tanks. Many organic chemicals, if present in concentrations above 10 dry weight percent (sodium acetate equivalent), have the potential to react with nitrate-nitrites constituents at temperatures above 200 degree C (392 degree F) in an exothermic manner. The concentrations of organic materials in the listed single-shell tanks, and their chemical identity, is not accurately known at present. A tank sampling program has been planned to provide more information on the contents of these tanks and to serve as a basis for laboratory testing and safety evaluations. 2 refs., 1 fig., 2 tabs

  13. Preliminary assessment of the controlled release of radionuclides from waste packages containing borosilicate waste glass

    International Nuclear Information System (INIS)

    Strachan, D.M.; McGrail, B.P.; Apted, M.J.; Engle, D.W.; Eslinger, P.W.

    1990-06-01

    The purpose of this report is to provide a preliminary assessment of the release-rate for an engineered barriers subsystem (EBS) containing waste packages of defense high-level waste borosilicate glass at geochemical and hydrological conditions similar to the those at Yucca Mountain. The relationship between the proposed Waste Acceptance Preliminary Specifications (WAPS) test of glass- dissolution rate and compliance with the NRC's release-rate criterion is also evaluated. Calculations are reported for three hierarchical levels: EBS analysis, waste-package analysis, and waste-glass analysis. The following conclusions identify those factors that most acutely affect the magnitude of, or uncertainty in, release-rate performance

  14. 5th Total System Performance Assessment Workshop

    International Nuclear Information System (INIS)

    Hwang, Yong Soo; Lee, Youn Myoung; Kang, Chul Hyung; Lee, Sung Ho

    2009-07-01

    Research items on safety assessment of high-level waste repository have been proposed by external invited experts outside KAERI and discussed extensively during the annual 5th performance assessment workshop prepared by safety assessment group in KAERI. This could be useful to set up R and D plans necessary for the next phase of mid- and long-term reaserch area regarding the safety assessment of high-level waste repository. Through the research and the presentation, HLW-related research and development area including such specific research items as current status of HLW safety assessment research, current requirement for the licensing of the repository system, priority on research area, data base building for the safety assessment, source-term modeling as well as safety case, among many others, have been discussed and summarized

  15. Fucose-containing sulfated polysaccharides from brown seaweed: Extraction technolgy and bioactivity assessment

    DEFF Research Database (Denmark)

    Ale, Marcel Tutor

    will generate new valuable products that may help lessen coastal pollution by seaweeds and create new seaweed-based resources. Thus, utilization of these natural resources is of great importance. The objectives of this PhD study were to develop a technology to extract bioactive compounds from nuisance brown...... seaweeds, and investigate their bioactivity. To this effect, designed optimized extraction of fucose-containing sulfated polysaccharides (FCSPs) and/or crude fucoidan from brown seaweed were performed, and the bioactivity of the isolated FCSPs was investigated. Moreover, to assess the potential of seaweed...... to assimilate nitrogen-based nutrients, a technology for accurate monitoring of differential seaweed growth responses to nutrient assimilation was also developed. Fucoidan is a term used to describe a class of sulfated polysaccharides extracted from brown seaweed, which contains substantial amounts of fucose...

  16. Small animal PET: aspects of performance assessment

    International Nuclear Information System (INIS)

    Weber, Simone; Bauer, Andreas

    2004-01-01

    Dedicated small animal positron emission tomography (PET) systems are increasingly prevalent in industry (e.g. for preclinical drug development) and biological research. Such systems permit researchers to perform animal studies of a longitudinal design characterised by repeated measurements in single animals. With the advent of commercial systems, scanners have become readily available and increasingly popular. As a consequence, technical specifications are becoming more diverse, making scanner systems less broadly applicable. The investigator has, therefore, to make a decision regarding which type of scanner is most suitable for the intended experiments. This decision should be based on gantry characteristics and the physical performance. The first few steps have been taken towards standardisation of the assessment of performance characteristics of dedicated animal PET systems, though such assessment is not yet routinely implemented. In this review, we describe current methods of evaluation of physical performance parameters of small animal PET scanners. Effects of methodologically different approaches on the results are assessed. It is underscored that particular attention has to be paid to spatial resolution, sensitivity, scatter fraction and count rate performance. Differences in performance measurement methods are described with regard to commercially available systems, namely the Concorde MicroPET systems P4 and R4 and the quad-HIDAC. Lastly, consequences of differences in scanner performance parameters are rated with respect to applications of small animal PET. (orig.)

  17. Performance success from self-assessments

    International Nuclear Information System (INIS)

    Hughes, G.

    1996-01-01

    This paper provides information on and successes of self-assessments completed at the Callaway plant. It stresses the vital needs and substantial benefits from these continual self-improvement efforts. The Callaway plant staff use a variety of methods and techniques to do self-assessments with the focus on performance outcomes. Self-assessments help Callaway focus on the priority issues and direct resources properly. Callaway's success has been due to this learning culture. The Callaway plant is a Westinghouse four-loop plant in the state of Missouri and has been operational since 1984

  18. Containment Performance Analysis with Large Break LOCA for EU-APR1400

    International Nuclear Information System (INIS)

    Hwang, Do Hyun; Lee, Keun Sung; Kim, Yong Soo

    2013-01-01

    In this paper for containment performance analysis, the containment pressurization analysis is performed and thermo-hydraulic response analysis of containment structure is carried out to provide basic understanding of containment transient states under a severe accident sequence. Especially, in EU-APR1400 design, to reduce containment pressure and temperature, Severe Accident Containment Spray System (SACSS) is designed to be actuated automatically when Core Exit Temperature (CET) reaches 922 K (649 .deg. C). The containment performance analysis was carried on LBLOCA sequence for EU-APR1400 with SACSS through MAAP code. If SACSS is actuated when CET reaches 922 K (649 .deg. C) , the containment pressure and temperature decrease to a sufficient low level. The predicted atmospheric pressure of containment will not exceed the ultimate pressure capacity (UPC) and have a sufficient margin to it even though the UPC of the reference plant (Shin-Kori Units 3 and 4) is used instead because the UPC calculation for EU-APR1400 has not been completed. The largest load on the containment by LBLOCA is estimated at 306.1 kPa. Thus the margin to UPC is estimated to be 330 % in comparison with 1.329 MPa as UPC for the reference plant.

  19. Assessing the Performance of Natural Resource Systems

    Directory of Open Access Journals (Sweden)

    Bruce Campbell

    2002-01-01

    Full Text Available Assessing the performance of management is central to natural resource management, in terms of improving the efficiency of interventions in an adaptive-learning cycle. This is not simple, given that such systems generally have multiple scales of interaction and response; high frequency of nonlinearity, uncertainty, and time lags; multiple stakeholders with contrasting objectives; and a high degree of context specificity. The importance of bounding the problem and preparing a conceptual model of the system is highlighted. We suggest that the capital assets approach to livelihoods may be an appropriate organizing principle for the selection of indicators of system performance. In this approach, five capital assets are recognized: physical, financial, social, natural, and human. A number of principles can be derived for each capital asset; indicators for assessing system performance should cover all of the principles. To cater for multiple stakeholders, participatory selection of indicators is appropriate, although when cross-site comparability is required, some generic indicators are suitable. Because of the high degree of context specificity of natural resource management systems, a typology of landscapes or resource management domains may be useful to allow extrapolation to broader systems. The problems of nonlinearities, uncertainty, and time lags in natural resource management systems suggest that systems modeling is crucial for performance assessment, in terms of deriving "what would have happened anyway" scenarios for comparison to the measured trajectory of systems. Given that a number of indicators are necessary for assessing performance, the question becomes whether these can be combined to give an integrative assessment. We explore five possible approaches: (1 simple additive index, as used for the Human Development Index; (2 derived variables (e.g., principal components as the indices of performance; (3 two-dimensional plots of

  20. Guidelines for Assessment and Abatement of Asbestos-Containing Materials in Buildings.

    Science.gov (United States)

    Pielert, James H.; Mathey, Robert G.

    This report presents guidelines, based on available information, for the assessment and abatement of asbestos-containing materials in buildings. Section 1 provides background information on the history and use of asbestos-containing products in buildings, the characteristics of asbestos fibers, products and materials containing asbestos, and…

  1. Historical data summary of the Systematic Assessment of Licensee Performance

    International Nuclear Information System (INIS)

    Johnson, M.R.; Waterman, D.K.

    1987-04-01

    This report presents a history of Systematic Assessment of Licensee Performance (SALP) ratings for nuclear power plant facilities in operation and under construction. The SALP results are listed by NRC region in three sections: the most recent report, operating facilities, and facilities under construction. The historical data summary report has been prepared by the NRC Office of Inspection and Enforcement (IE). Information contained in this report has been updated to include those published SALP reports received before March 13, 1987

  2. Historical data summary of the systematic assessment of licensee performance

    International Nuclear Information System (INIS)

    1986-10-01

    This report presents a history of Systematic Assessment of Licensee Performance (SALP) ratings for nuclear power plant facilities in operation and under construction. The SALP results are listed by NRC region in three sections: the most recent report, operating facilities, and facilities under construction. The historical data summary report has been prepared by the NRC Office of Inspection and Enforcement (IE). Information contained in this report has been updated to include those published SALP reports received before September 16, 1986

  3. Dehydration: physiology, assessment, and performance effects.

    Science.gov (United States)

    Cheuvront, Samuel N; Kenefick, Robert W

    2014-01-01

    This article provides a comprehensive review of dehydration assessment and presents a unique evaluation of the dehydration and performance literature. The importance of osmolality and volume are emphasized when discussing the physiology, assessment, and performance effects of dehydration. The underappreciated physiologic distinction between a loss of hypo-osmotic body water (intracellular dehydration) and an iso-osmotic loss of body water (extracellular dehydration) is presented and argued as the single most essential aspect of dehydration assessment. The importance of diagnostic and biological variation analyses to dehydration assessment methods is reviewed and their use in gauging the true potential of any dehydration assessment method highlighted. The necessity for establishing proper baselines is discussed, as is the magnitude of dehydration required to elicit reliable and detectable osmotic or volume-mediated compensatory physiologic responses. The discussion of physiologic responses further helps inform and explain our analysis of the literature suggesting a ≥ 2% dehydration threshold for impaired endurance exercise performance mediated by volume loss. In contrast, no clear threshold or plausible mechanism(s) support the marginal, but potentially important, impairment in strength, and power observed with dehydration. Similarly, the potential for dehydration to impair cognition appears small and related primarily to distraction or discomfort. The impact of dehydration on any particular sport skill or task is therefore likely dependent upon the makeup of the task itself (e.g., endurance, strength, cognitive, and motor skill). © 2014 American Physiological Society.

  4. Performance assessment of gamma cameras. Part 1

    International Nuclear Information System (INIS)

    Elliot, A.T.; Short, M.D.; Potter, D.C.; Barnes, K.J.

    1980-11-01

    The Dept. of Health and Social Security and the Scottish Home and Health Dept. has sponsored a programme of measurements of the important performance characteristics of 15 leading types of gamma cameras providing a routine radionuclide imaging service in hospitals throughout the UK. Measurements have been made of intrinsic resolution, system resolution, non-uniformity, spatial distortion, count rate performance, sensitivity, energy resolution and shield leakage. The main aim of this performance assessment was to provide sound information to the NHS to ease the task of those responsible for the purchase of gamma cameras. (U.K.)

  5. Performance Assessment Position Paper: Time for Compliance

    International Nuclear Information System (INIS)

    Wilhite, E.L.

    2003-01-01

    This study lays out the historical development of the time frame for a low-level waste disposal facility to demonstrate compliance with the DOE performance objectives and requirements. The study recommends that 1,000 years should be used as the time for compliance for all of the performance objectives and requirements (i.e., for the all-pathways, air pathway, radon emanation, water resource protection and inadvertent intruder analyses) for all low-level waste disposal facility performance assessments at the Savannah River Site

  6. Containment-emergency-sump performance. Technical findings related to Unresolved Safety Issue A-43

    International Nuclear Information System (INIS)

    1983-04-01

    This report summarizes key technical findings related to the Unresolved Safety Issue A-43, Containment Emergency Sump Performance, and provides recommendations for resolution of attendant safety issues. The key safety questions relate to: (a) effects of insulation debris on sump performance; (b) sump hydraulic performance as determined by design features, submergence, and plant induced effects, and (c) recirculation pump performance wherein air and/or particulate ingestion can occur. The technical findings presented in this report provide information relevant to the design and performance evaluation of the containment emergency sump

  7. Assessing the Performance of Business Unit Managers

    NARCIS (Netherlands)

    Bouwens, J.F.M.G.; van Lent, L.A.G.M.

    2006-01-01

    Using a sample of 140 managers, we investigate the use of various performance metrics in determining the periodic assessment, bonus decisions, and career paths of business unit managers.We show that the weight on accounting return measures is associated with the authority of these managers, and we

  8. The Visible Hand of Research Performance Assessment

    Science.gov (United States)

    Hamann, Julian

    2016-01-01

    Far from allowing a governance of universities by the invisible hand of market forces, research performance assessments do not just measure differences in research quality, but yield themselves visible symptoms in terms of a stratification and standardization of disciplines. The article illustrates this with a case study of UK history departments…

  9. Performance assessment of indigenously developed FBG strain ...

    Indian Academy of Sciences (India)

    Use of FBG sensors for real time health monitoring of various civil engineering structures is well-established in western world since last decade, whereas in the Indian context this technology is still in a nascent stage. In this paper, performance assessment of indigenously developed FBG sensors for the application of health ...

  10. An overview of performance assessment methodology

    International Nuclear Information System (INIS)

    Hongnian Jow

    2010-01-01

    The definition of performance assessment (PA) within the context of a geologic repository program is a post-closure safety assessment; a system analysis of hazards associated with the facility and the ability of the site and the design of the facility to provide for the safety functions. For the last few decades, PA methodology bas been developed and applied to different waste disposal programs around the world. PA has been used in the safety analyses for waste disposal repositories for low-level waste, intermediate level waste, and high-level waste including spent nuclear fuels. This paper provides an overview of the performance assessment methodology and gives examples of its applications for the Yucca Mountain Project. (authors)

  11. CONPAS 1.0 (CONtainment Performance Analysis System). User`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Kwang Il; Jin, Young Ho [Korea Atomic Energy Research Institute, Daeduk (Korea, Republic of)

    1996-04-01

    CONPAS (CONtainment Performance Analysis System) is a verified computer code package to integrate the numerical, graphical, and results-operation aspects of Level 2 probabilistic safety assessments (PSA) for nuclear power plants automatically under a PC window environment. Compared with the existing DOS-based computer codes for Level 2 PSA, the most important merit of the window-based computer code is that user can easily describe and quantify the accident progression models, and manipulate the resultant outputs in a variety of ways. As a main logic for accident progression analysis, CONPAS employs a concept of the small containment phenomenological event tree (CPET) helpful to trace out visually individual accident progressions and of the large supporting event tree (LSET) for its detailed quantification. For the integrated analysis of Level 2 PSA, the code utilizes four distinct, but closely related modules; (1) ET Editor for construction of several event tree models describing the accident progressions, (2) Computer for quantification of the constructed event trees and graphical display of the resultant outputs, (3) Text Editor for preparation of input decks for quanification and utilization of calculational results, and (4) Mechanistic Code Plotter for utilization of results obtained from severe accident analysis codes. Compared with other existing computer codes for Level 2 PSA, the CONPAS code provides several advanced features: computational aspects including systematic uncertainty analysis, importance analysis, sensitivity analysis and data interpretation, reporting aspects including tabling and graphic as well as user-friend interface. 10 refs. (Author) .new.

  12. Radioactive Waste Management Complex performance assessment: Draft

    Energy Technology Data Exchange (ETDEWEB)

    Case, M.J.; Maheras, S.J.; McKenzie-Carter, M.A.; Sussman, M.E.; Voilleque, P.

    1990-06-01

    A radiological performance assessment of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory was conducted to demonstrate compliance with appropriate radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the general public. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the general public via air, ground water, and food chain pathways. Projections of doses were made for both offsite receptors and individuals intruding onto the site after closure. In addition, uncertainty analyses were performed. Results of calculations made using nominal data indicate that the radiological doses will be below appropriate radiological criteria throughout operations and after closure of the facility. Recommendations were made for future performance assessment calculations.

  13. Radioactive Waste Management Complex performance assessment: Draft

    International Nuclear Information System (INIS)

    Case, M.J.; Maheras, S.J.; McKenzie-Carter, M.A.; Sussman, M.E.; Voilleque, P.

    1990-06-01

    A radiological performance assessment of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory was conducted to demonstrate compliance with appropriate radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the general public. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the general public via air, ground water, and food chain pathways. Projections of doses were made for both offsite receptors and individuals intruding onto the site after closure. In addition, uncertainty analyses were performed. Results of calculations made using nominal data indicate that the radiological doses will be below appropriate radiological criteria throughout operations and after closure of the facility. Recommendations were made for future performance assessment calculations

  14. The effects of performance-based assessment criteria on student performance and self-assessment skills

    NARCIS (Netherlands)

    Fastré, Greet; Van der Klink, Marcel; Van Merriënboer, Jeroen

    2010-01-01

    Fastré, G. M. J., Van der Klink, M. R., & Van Merriënboer, J. J. G. (2010). The effects of performance-based assessment criteria on student performance and self-assessment skills. Advances in Health Science Education, 15(4), 517-532.

  15. Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 3

    International Nuclear Information System (INIS)

    Ulm, Franz-Josef

    2000-01-01

    OAK-B135 Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 3(NOTE: Part II A item 1 indicates ''PAPER'', but a report is attached electronically)

  16. Assessment of GOTHIC and TRACE codes against selected PANDA experiments on a Passive Containment Condenser

    Energy Technology Data Exchange (ETDEWEB)

    Papini, Davide, E-mail: davide.papini@psi.ch; Adamsson, Carl; Andreani, Michele; Prasser, Horst-Michael

    2014-10-15

    Highlights: • Code comparison on the performance of a Passive Containment Condenser. • Simulation of separate effect tests with pure steam and non-condensable gases. • Role of the secondary side and accuracy of pool boiling models are discussed. • GOTHIC and TRACE predict the experimental performance with slight underestimation. • Recirculatory flow pattern with injection of light non-condensable gas is inferred. - Abstract: Typical passive safety systems for ALWRs (Advanced Light Water Reactors) rely on the condensation of steam to remove the decay heat from the core or the containment. In the present paper the three-dimensional containment code GOTHIC and the one-dimensional system code TRACE are compared on the calculation of a variety of phenomena characterizing the response of a passive condenser submerged in a boiling pool. The investigation addresses the conditions of interest for the Passive Containment Cooling System (PCCS) proposed for the ESBWR (Economic Simplified Boiling Water Reactor). The analysis of selected separate effect tests carried out on a PCC (Passive Containment Condenser) unit in the PANDA large-scale thermal-hydraulic facility is presented to assess the code predictions. Both pure steam conditions (operating pressure of 3 bar, 6 bar and 9 bar) and the effect on the condensation heat transfer of non-condensable gases heavier than steam (air) and lighter than steam (helium) are considered. The role of the secondary side (pool side) heat transfer on the condenser performance is examined too. In general, this study shows that both the GOTHIC and TRACE codes are able to reasonably predict the heat transfer capability of the PCC as well as the influence of non-condensable gas on the system. A slight underestimation of the condenser performance is obtained with both codes. For those tests where the experimental and simulated efficiencies agree better the possibility of compensating errors among different parts of the heat transfer

  17. Corrosion models for predictions of performance of high-level radioactive-waste containers

    Energy Technology Data Exchange (ETDEWEB)

    Farmer, J.C.; McCright, R.D. [Lawrence Livermore National Lab., CA (United States); Gdowski, G.E. [KMI Energy Services, Livermore, CA (United States)

    1991-11-01

    The present plan for disposal of high-level radioactive waste in the US is to seal it in containers before emplacement in a geologic repository. A proposed site at Yucca Mountain, Nevada, is being evaluated for its suitability as a geologic repository. The containers will probably be made of either an austenitic or a copper-based alloy. Models of alloy degradation are being used to predict the long-term performance of the containers under repository conditions. The models are of uniform oxidation and corrosion, localized corrosion, and stress corrosion cracking, and are applicable to worst-case scenarios of container degradation. This paper reviews several of the models.

  18. Performance of broiler chickens fed diets containing DAS-68416-4 soybean meal.

    Science.gov (United States)

    Herman, Rod A; Dunville, Christina M; Juberg, Daland R; Fletcher, Dale W; Cromwell, Gary L

    2011-01-01

    Broiler chickens are a fast growing monogastric animal commonly used to evaluate the equivalence between transgenic and non-transgenic grains as part of the human safety assessment process. While commonly viewed like other livestock feeding trials, such studies are performed with transgenic crops with input traits (that are not designed to improve nutrition) to aid regulatory authorities in evaluating safety. Studies of this type are actually more similar to toxicology studies in purpose, with sensitive endpoints like growth used to detect metabolic perturbations. DAS-68416-4 soybean expresses the aryloxyalkanoate dioxygenase-12 (AAD-12) enzyme which inactivates 2,4-diclorophenoxyacetic acid (2,4-D) and provides DAS-68416-4 soybeans tolerance to this herbicide. DAS-68416-4 also expresses the phosphinothricin acetyltransferase (PAT) enzyme from Streptomyces viridochromogenes which confers tolerance to glufosinate-ammonium herbicides. A 6-week broiler study was conducted with diets containing toasted DAS-68416-4 soybean meal (40, 36, and 32% in starter, grower and finisher diets, respectively) to evaluate nutritional wholesomeness and safety compared with conventional comparators. Toasting soybean meal is required to inactivate endogenous antinutrients making soybean suitable for consumption by monogastric animals like broiler chickens. Toasting was found to denature both the AAD-12 and PAT proteins rendering them non-detectable by enzyme linked immunosorbent assays. Broiler growth and performance parameters were measured over a 6-week period of exposure to diets containing different sources of toasted soybean meal, and results indicate that DAS-68416-4 soybean is nutritionally equivalent to non-transgenic soybean.

  19. Determination and risk assessment of naturally occurring genotoxic and carcinogenic alkenylbenzenes in basil-containing sauce of pesto

    NARCIS (Netherlands)

    Al-Malahmeh, Amer J.; Al-Ajlouni, Abdalmajeed M.; Wesseling, Sebas; Vervoort, Jacques; Rietjens, Ivonne M.C.M.

    2017-01-01

    A risk assessment of basil-based pesto sauces containing methyleugenol and related alkenylbenzenes was performed based on their levels detected in a series of pesto sauces available on the Dutch market. The estimated daily intake (EDI) values of alkenylbenzenes as a result of consumption of the

  20. Risk assessment of combined exposure to alkenylbenzenes through consumption of plant food supplements containing parsley and dill

    NARCIS (Netherlands)

    Alajlouni, Abdalmajeed M.; Al-Malahmeh, Amer J.; Wesseling, Sebastiaan; Kalli, Marina; Vervoort, Jacques; Rietjens, Ivonne M.C.M.

    2017-01-01

    A risk assessment was performed of parsley- and dill-based plant food supplements (PFS) containing apiol and related alkenylbenzenes. First, the levels of the alkenylbenzenes in the PFS and the resulting estimated daily intake (EDI) resulting from use of the PFS were quantified. Since most PFS

  1. Control Performance Management in Industrial Automation Assessment, Diagnosis and Improvement of Control Loop Performance

    CERN Document Server

    Jelali, Mohieddine

    2013-01-01

    Control Performance Management in Industrial Automation provides a coherent and self-contained treatment of a group of methods and applications of burgeoning importance to the detection and solution of problems with control loops that are vital in maintaining product quality, operational safety, and efficiency of material and energy consumption in the process industries. The monograph deals with all aspects of control performance management (CPM), from controller assessment (minimum-variance-control-based and advanced methods), to detection and diagnosis of control loop problems (process non-linearities, oscillations, actuator faults), to the improvement of control performance (maintenance, re-design of loop components, automatic controller re-tuning). It provides a contribution towards the development and application of completely self-contained and automatic methodologies in the field. Moreover, within this work, many CPM tools have been developed that goes far beyond available CPM packages. Control Perform...

  2. Using An Adapter To Perform The Chalfant-Style Containment Vessel Periodic Maintenance Leak Rate Test

    International Nuclear Information System (INIS)

    Loftin, B.; Abramczyk, G.; Trapp, D.

    2011-01-01

    Recently the Packaging Technology and Pressurized Systems (PT and PS) organization at the Savannah River National Laboratory was asked to develop an adapter for performing the leak-rate test of a Chalfant-style containment vessel. The PT and PS organization collaborated with designers at the Department of Energy's Pantex Plant to develop the adapter currently in use for performing the leak-rate testing on the containment vessels. This paper will give the history of leak-rate testing of the Chalfant-style containment vessels, discuss the design concept for the adapter, give an overview of the design, and will present results of the testing done using the adapter.

  3. Putting HLW performance assessment results in perspective

    International Nuclear Information System (INIS)

    Neall, F.; Smith, P.; Sumerling, T.; Umeki, H.

    1995-01-01

    According to performance assessment results for the different disposal concepts investigated, the maximum radiation doses to the population lie well below the limit set in the official Swiss Protection Objective and below the level of present-day natural background radiation. A comparison of different performance assessments has shown that the following key factors determine radionuclide release from a repository: radionuclide inventory, canister material and failure mode, nuclide solubility limits, the permeability of the buffer material, retardation during transport through the near-field, the presence of an excavation disturbed zone in the rock, the distance to the nearest major water-bearing fracture zone, the conceptual model for transport in fractured rock and near-surface dilution and dose factors. (author) 2 figs., 2 tabs

  4. Assessing the performance of dynamical trajectory estimates

    Science.gov (United States)

    Bröcker, Jochen

    2014-06-01

    Estimating trajectories and parameters of dynamical systems from observations is a problem frequently encountered in various branches of science; geophysicists for example refer to this problem as data assimilation. Unlike as in estimation problems with exchangeable observations, in data assimilation the observations cannot easily be divided into separate sets for estimation and validation; this creates serious problems, since simply using the same observations for estimation and validation might result in overly optimistic performance assessments. To circumvent this problem, a result is presented which allows us to estimate this optimism, thus allowing for a more realistic performance assessment in data assimilation. The presented approach becomes particularly simple for data assimilation methods employing a linear error feedback (such as synchronization schemes, nudging, incremental 3DVAR and 4DVar, and various Kalman filter approaches). Numerical examples considering a high gain observer confirm the theory.

  5. Development of assessment methods for transport and storage containers with higher content of metallic recycling material

    International Nuclear Information System (INIS)

    Zencker, U.; Qiao Linan; Droste, B.

    2004-01-01

    The mechanical behaviour of transport and storage containers made of ductile cast iron melted with higher content of metallic recycling material from decommissioning and dismantling of nuclear installations is investigated. With drop tests of cubic container-like models, the influence of different real targets on the stresses in the cask body and the fracture behaviour is examined. A test stand foundation is suggested, which can be manufactured simply and improves the reproducibility of the test results strongly. The test objects are partially equipped with artificial cracklike defects. Dynamic fracture mechanics analyses of these defects were performed by means of finite element calculations to uncover safety margins. Numerous test results show depending on the requirements that containers for final disposal can be built by means of a ductile cast iron with fracture toughness more than half under the lower bound value for the licensed material qualities yet. The application limits of the material are determined also by the opportunities of the safety assessment methods. This project supports the application of brittle fracture safe transport and storage packages for radioactive materials as recommended in App. VI of the Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (IAEA No. TS-G-1.1)

  6. Development of assessment methods for transport and storage containers with higher content of metallic recycling material

    Energy Technology Data Exchange (ETDEWEB)

    Zencker, U.; Qiao Linan; Droste, B. [Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin (Germany)

    2004-07-01

    The mechanical behaviour of transport and storage containers made of ductile cast iron melted with higher content of metallic recycling material from decommissioning and dismantling of nuclear installations is investigated. With drop tests of cubic container-like models, the influence of different real targets on the stresses in the cask body and the fracture behaviour is examined. A test stand foundation is suggested, which can be manufactured simply and improves the reproducibility of the test results strongly. The test objects are partially equipped with artificial cracklike defects. Dynamic fracture mechanics analyses of these defects were performed by means of finite element calculations to uncover safety margins. Numerous test results show depending on the requirements that containers for final disposal can be built by means of a ductile cast iron with fracture toughness more than half under the lower bound value for the licensed material qualities yet. The application limits of the material are determined also by the opportunities of the safety assessment methods. This project supports the application of brittle fracture safe transport and storage packages for radioactive materials as recommended in App. VI of the Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (IAEA No. TS-G-1.1).

  7. Assessment of airborne asbestos exposure during the servicing and handling of automobile asbestos-containing gaskets.

    Science.gov (United States)

    Blake, Charles L; Dotson, G Scott; Harbison, Raymond D

    2006-07-01

    Five test sessions were conducted to assess asbestos exposure during the removal or installation of asbestos-containing gaskets on vehicles. All testing took place within an operative automotive repair facility involving passenger cars and a pickup truck ranging in vintage from late 1960s through 1970s. A professional mechanic performed all shop work including engine disassembly and reassembly, gasket manipulation and parts cleaning. Bulk sample analysis of removed gaskets through polarized light microscopy (PLM) revealed asbestos fiber concentrations ranging between 0 and 75%. Personal and area air samples were collected and analyzed using National Institute of Occupational Safety Health (NIOSH) methods 7400 [phase contrast microscopy (PCM)] and 7402 [transmission electron microscopy (TEM)]. Among all air samples collected, approximately 21% (n = 11) contained chrysotile fibers. The mean PCM and phase contrast microscopy equivalent (PCME) 8-h time weighted average (TWA) concentrations for these samples were 0.0031 fibers/cubic centimeters (f/cc) and 0.0017 f/cc, respectively. Based on these findings, automobile mechanics who worked with asbestos-containing gaskets may have been exposed to concentrations of airborne asbestos concentrations approximately 100 times lower than the current Occupational Safety and Health Administration (OSHA) Permissible Exposure Limit (PEL) of 0.1 f/cc.

  8. Containment design, performance criteria and research needs for advanced reactor designs

    International Nuclear Information System (INIS)

    Bagdi, G.; Ali, S.; Costello, J

    2004-01-01

    This paper points out some important shifts in the basic expectations in the performance requirements for containment structures and discusses the areas where the containment structure design requirements and acceptance criteria can be integrated with ultimate test based insights. Although there has not been any new reactor construction in the United States for over thirty years, several designs of evolutionary and advanced reactors have already been certified. Performance requirements for containment structures under design basis and severe accident conditions and explicit consideration of seismic margins have been used in the design certification process. In the United States, the containment structure design code is the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NE-Class MC for the steel containment and Section III, Division 2 for reinforced and prestressed concrete reactor vessels and containments. This containment design code was based on the early concept of applying design basis internal pressure and associated load combinations that included the operating basis and safe shutdown earthquake ground motion. These early design criteria served the nuclear industry and the regulatory authorities in maintaining public health and safety. However, these early design criteria do not incorporate the performance criteria related to containment function in an integrated fashion. Research in large scale model testing of containment structures to failure from over pressurization and shake table testing using simulated ground motion, have produced insights related to failure modes and material behavior at failure. The results of this research provide the opportunity to integrate these observations into design and acceptance criteria. This integration process would identify 'gaps' in the present knowledge and future research needs. This knowledge base is important for gleaning risk-informed insights into

  9. Uncertainty evaluation methods for waste package performance assessment

    International Nuclear Information System (INIS)

    Wu, Y.T.; Nair, P.K.; Journel, A.G.; Abramson, L.R.

    1991-01-01

    This report identifies and investigates methodologies to deal with uncertainties in assessing high-level nuclear waste package performance. Four uncertainty evaluation methods (probability-distribution approach, bounding approach, expert judgment, and sensitivity analysis) are suggested as the elements of a methodology that, without either diminishing or enhancing the input uncertainties, can evaluate performance uncertainty. Such a methodology can also help identify critical inputs as a guide to reducing uncertainty so as to provide reasonable assurance that the risk objectives are met. This report examines the current qualitative waste containment regulation and shows how, in conjunction with the identified uncertainty evaluation methodology, a framework for a quantitative probability-based rule can be developed that takes account of the uncertainties. Current US Nuclear Regulatory Commission (NRC) regulation requires that the waste packages provide ''substantially complete containment'' (SCC) during the containment period. The term ''SCC'' is ambiguous and subject to interpretation. This report, together with an accompanying report that describes the technical considerations that must be addressed to satisfy high-level waste containment requirements, provides a basis for a third report to develop recommendations for regulatory uncertainty reduction in the ''containment''requirement of 10 CFR Part 60. 25 refs., 3 figs., 2 tabs

  10. Assessment of cavity dispersal correlations for possible implementation in the CONTAIN code

    International Nuclear Information System (INIS)

    Williams, D.C.; Griffith, R.O.

    1996-02-01

    Candidate models and correlations describing entrainment and dispersal of core debris from reactor cavities in direct containment heating (DCH) event, are assessed against a data base of approximately 600 experiments performed previously at Brookhaven National Laboratory and Sandia National Laboratories reactor cavities was studied. Cavity geometries studied are those of the Surry and Zion nuclear power plants and scale factors of 1/42 and 1/10 were studied for both geometries. Other parameters varied in the experiments include gas pressure driving the dispersal, identities of the driving gas and of the simulant fluid, orifice diameter in the pressure vessel, and volume of the gas pressure vessel. Correlations were assessed in terms of their ability to reproduce the observed trends in the fractions dispersed as the experimental parameters were varied. For the fraction of the debris dispersed, the correlations recommended for inclusion in the CONTAIN code are the Tutu-Ginsberg correlations, the integral form of the correlation proposed by Levy and a modified form of the Whalley-Hewitt correlation. For entrainment rates, the recommended correlations are the time-dependent forms of the Levy correlation, a correlation suggested by Tutu, and the modified Whalley-Hewitt correlation

  11. Assessment of severe accident prevention and mitigation features: BWR, Mark II containment design

    International Nuclear Information System (INIS)

    Lehner, J.R.; Hsu, C.J.; Eltawila, F.; Perkins, K.R.; Luckas, W.J.; Fitzpatrick, R.G.; Pratt, W.T.

    1988-07-01

    Plant features and operator actions, which have been found to be important in either preventing or mitigating severe accidents in BWRs with Mark II containments (BWR Mark II's) have been identified. These features and actions were developed from insights derived from reviews of in-depth risk assessments performed specifically for the Limerick and Shoreham plants and from other relevant studies. Accident sequences that dominate the core-damage frequency and those accident sequences that are of potentially high consequence were identified. Vulnerabilities of the BWR Mark II to severe-accident containment loads were also noted. In addition, those features of a BWR Mark II, which are important for preventing core damage and are available for mitigating fission-product release to the environment were also identified. This report is issued to provide focus to an analyst examining an individual plant. This report calls attention to plant features and operator actions and provides a list of deterministic attributes for assessing those features and actions found to be helpful in reducing the overall risk for Mark II plants. Thus, the guidance is offered as a resource in examining the subject plant to determine if the same, or similar, plant features and operator actions will be of value in reducing overall plant risk. This report is intended to serve solely as guidance

  12. ASSESSING STUDENT PERFORMANCE ON INTERPRETING THROUGH PEER-ASSESSMENT

    Directory of Open Access Journals (Sweden)

    Titik Ismailia

    2017-12-01

    Full Text Available As a part of translation interpreting is translating spoken discourse orally. It needs some requirements like ability to speak clearly, clarity, fluency, eye contact, and self-confidence. It also needs linguistic proficiency, analytical skill, listening and recall, interpersonal skills, ethical behaviour, speaking skills, cultural knowledge, and subject knowledge. Evaluating students performance on interpreting can be done through peer assessment. Peer- assessment is one of alternative assessment to grade the peers in group or individuals by commenting on and judging other students work. To do this process there is a join work between listening and speaking, and two students. The first student as a speaker and the second student as an interpreter. Both of them should do the same quality on speak clearly as a speaker and as an interpreter should able to listen and translating the spoken discourse orally. Evaluation can use analytical grade that allows teacher to set clear criteria for correction like fluency, grammar, terminology, general content, and mechanics. Students and teacher can give comment on every criteria based on their own competency. During the process on making criteria, students and teacher can discuss and give reasonable suggestion to make the assessment suitable to the students competency. At the end, a rubric of assessment with the score from 0 to 100 and criteria and also the comment included in the paper of assessment.

  13. Post-assessment of pre-stressed containment structures by evaluation of monitored long term deformation results

    International Nuclear Information System (INIS)

    Wienand, B.

    2015-01-01

    The comparison of monitored long term deformations of containment structures with calculated values achieved by using design material parameters shows occasionally considerable deviations, partly caused by conservative assumptions in the containments design phase. Systematic post-assessment and adaption of the decisive parameters attains better coincidence. In the present investigation measured long-term deformations are first of all compared to pre-calculated values based on the material parameters defined in the design phase. Afterwards, the deformations deviations are minimized by repeating the calculation with assessed material parameters. This method appears to be a suitable method to predict the future containment structure long-term behavior and to achieve a possible life-time extension. The presented investigation was performed as part of NUGENIA ACCEPPT project which researches the ageing of concrete containment structures in nuclear power plants

  14. THAI experimental programme for containment safety assessment under severe accident conditions

    Energy Technology Data Exchange (ETDEWEB)

    Gupta, S.; Freitag, M. [Becker Technologies GmbH, Eschborn (Germany); Poss, G.

    2016-05-15

    The THAI (THAI = Thermal hydraulics, Hydrogen, Aerosols, Iodine) experimental programme aims to address open questions concerning the behavior of hydrogen, iodine and aerosols in the containment of water cooled reactors. Since its construction in 2000, THAI programme is being performed in the frame of various national projects (sponsored by German Federal Ministry for Economic Affairs and Energy, BMWi) and two international joint projects (under auspices of OECD/NEA). THAI experimental data have been widely used for the validation and further development of Lumped Parameter (LP) and Computational Fluid Dynamics (CFD) codes with 3D capabilities. Selected examples of code benchmark exercises performed based on the THAI data include; hydrogen distribution experiment (ISP-47 and OECD/NEA THAI code benchmark), hydrogen combustion behaviour (ISP-49), hydrogen mitigation by PARs (OECD/NEA THAI-2 code benchmark), iodine/surface interactions, iodine mass transfer, and iodine transport and multi-compartment behaviour (EU-SARNET and EU-SARNET2), thermal-hydraulic tests (German CFD-network). In the present paper, a brief overview on the THAI experiments and their role in the containment safety assessment is discussed.

  15. Tailored model abstraction in performance assessments

    International Nuclear Information System (INIS)

    Kessler, J.H.

    1995-01-01

    Total System Performance Assessments (TSPAs) are likely to be one of the most significant parts of making safety cases for the continued development and licensing of geologic repositories for the disposal of spent fuel and HLW. Thus, it is critical that the TSPA model capture the 'essence' of the physical processes relevant to demonstrating the appropriate regulation is met. But how much detail about the physical processes must be modeled and understood before there is enough confidence that the appropriate essence has been captured? In this summary the level of model abstraction that is required is discussed. Approaches for subsystem and total system performance analyses are outlined, and the role of best estimate models is examined. It is concluded that a conservative approach for repository performance, based on limited amount of field and laboratory data, can provide sufficient confidence for a regulatory decision

  16. The effect of severe accident mitigation design on the containment performance for Korean ALWR

    International Nuclear Information System (INIS)

    Na, J. H.; Lee, J. S.; Lim, H. K.; Kim, J. K.

    2001-01-01

    The containment performance analysis for Korean ALWR standard design has been performed to confirm the safety goal and to identify the design features vulnerable to severe accidents for the on-going design. The results in terms of conditional containment failure probability show Korean ALWR design does not have any particular vulnerability given core damage sequences. It shows the conditional containment failure probability for pull power internal event is less than that of design goal. The late containment failure is much less than 4% for given core damages and that of containment bypass is about 2%. New design features of the Korean ALWR such as bydrogen mitigation system (IIMS), cavity flooding system (CFS), and emergency containment spray bakcup system (ECSBS), external reactor vessel cooling (ERVC), etc. are reflected in Korean ALWR design and is reviewed in this paper to give an insight for the design vulnerabilities and input to the development of accident management. These Korean ALWR specific design features showed the containment performance is significantly enhanced compared with the other PWR plants

  17. ASSESSING UNIVERSITY RESEARCH PERFORMANCE WITH MULTIPLE CONSTITUENCIES

    Directory of Open Access Journals (Sweden)

    Kuang-Liang Liu

    2012-12-01

    Full Text Available The research performance of the university is critical to the national competitiveness. Previous research has established that research performance is based on scholarly publishing. Several studies suggested that journal ranking is the important research quality indicator. However, unilateral measurement for the research performance will seriously corrode the development of university research work. Assessing university research performance with multiple constituencies is a better to enhance the university research. Although substantial studies have been performed on the critical factors that affect knowledge exploration in the university, those in knowledge exploitation are still lacking. With the multiple constituencies, a fully understanding of research performance can be gained. In the research model, knowledge exploration represents the academic research and knowledge exploitation represents the university–industry collaboration. Data collected from 124 university data in online database. The study shows that knowledge exploration and exploitation both are significant positive predictors of university competitiveness. University resources play important roles to affect both knowledge exploration and exploitation in the university. The study also shows that higher knowledge exploration will enhance knowledge exploitation. Implications for theory and practice and suggestions for future research are discussed.

  18. Effects of container cavity size and copper coating on field performance of container-grown longleaf pine seedlings

    Science.gov (United States)

    Shi-Jean Susana Sung; James D. Haywood; Mary A. Sword-Sayer; Kristina F. Connor; D. Andrew Scott

    2010-01-01

    Longleaf pine (Pinus palustris Mill.) seedlings were grown for 27 weeks in 3 container cavity sizes [small (S), medium (M), and large (L)], and half the containers were coated with copper (Cu). In November 2004, we planted 144 seedlings from each of 6 container treatments in each of 4 replications in central LA. All plots were burned in February 2006...

  19. Assessment of corrosion and fatigue damage to light water reactor metal containments

    International Nuclear Information System (INIS)

    Sinha, U.P.; Shah, V.N.; Smith, S.K.

    1991-01-01

    This paper presents a generic procedure for estimating aging damage, evaluating structural integrity, and identifying mitigation activities for safe operation of boiling water reactor (BWR) Mark I metal containments and ice-condenser type pressurized water reactor (PWR) cylindrical metal containments. The mechanisms of concern that can cause aging damage to these two types of containments are corrosion and fatigue. Assessment of fatigue damage to bellows is also described. Assessment of corrosion and fatigue damage described in this paper include: containment design features that are relevant to aging assessment, several corrosion and fatigue mechanisms, inspection of corrosion and fatigue damage, and mitigation of damage caused by these mechanisms. In addition, synergistic interaction between corrosion and fatigue is considered. Possible actions for mitigating aging include enhanced inspection methods, maintenance activities based on operating experience, and supplementary surveillance programs. Field experience related to aging of metal containments is reviewed. Finally, conclusions and recommendations are presented

  20. Caffeine-containing energy drink improves sprint performance during an international rugby sevens competition.

    Science.gov (United States)

    Del Coso, Juan; Portillo, Javier; Muñoz, Gloria; Abián-Vicén, Javier; Gonzalez-Millán, Cristina; Muñoz-Guerra, Jesús

    2013-06-01

    The aim of this study was to determine the effects of a caffeine-containing energy drink on physical performance during a rugby sevens competition. A second purpose was to investigate the post-competition urinary caffeine concentration derived from the energy drink intake. On two non-consecutive days of a friendly tournament, 16 women from the Spanish National rugby sevens Team (mean age and body mass = 23 ± 2 years and 66 ± 7 kg) ingested 3 mg of caffeine per kg of body mass in the form of an energy drink (Fure(®), ProEnergetics) or the same drink without caffeine (placebo). After 60 min for caffeine absorption, participants performed a 15-s maximal jump test, a 6 × 30 m sprint test, and then played three rugby sevens games against another national team. Individual running pace and instantaneous speed during the games were assessed using global positioning satellite (GPS) devices. Urine samples were obtained pre and post-competition. In comparison to the placebo, the ingestion of the energy drink increased muscle power output during the jump series (23.5 ± 10.1 vs. 25.6 ± 11.8 kW, P = 0.05), running pace during the games (87.5 ± 8.3 vs. 95.4 ± 12.7 m/min, P caffeine concentration than the placebo (3.3 ± 0.7 vs. 0.2 ± 0.1 μg/mL; P caffeine in the form of a commercially available energy drink considerably enhanced physical performance during a women's rugby sevens competition.

  1. Guidance for performing preliminary assessments under CERCLA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-09-01

    EPA headquarters and a national site assessment workgroup produced this guidance for Regional, State, and contractor staff who manage or perform preliminary assessments (PAs). EPA has focused this guidance on the types of sites and site conditions most commonly encountered. The PA approach described in this guidance is generally applicable to a wide variety of sites. However, because of the variability among sites, the amount of information available, and the level of investigative effort required, it is not possible to provide guidance that is equally applicable to all sites. PA investigators should recognize this and be aware that variation from this guidance may be necessary for some sites, particularly for PAs performed at Federal facilities, PAs conducted under EPA`s Environmental Priorities Initiative (EPI), and PAs at sites that have previously been extensively investigated by EPA or others. The purpose of this guidance is to provide instructions for conducting a PA and reporting results. This guidance discusses the information required to evaluate a site and how to obtain it, how to score a site, and reporting requirements. This document also provides guidelines and instruction on PA evaluation, scoring, and the use of standard PA scoresheets. The overall goal of this guidance is to assist PA investigators in conducting high-quality assessments that result in correct site screening or further action recommendations on a nationally consistent basis.

  2. Hanford immobilized low-activity tank waste performance assessment

    International Nuclear Information System (INIS)

    Mann, F.M.

    1998-01-01

    The Hanford Immobilized Low-Activity Tank Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-level fraction of waste presently contained in Hanford Site tanks. The tank waste is the by-product of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste has been stored in underground single and double-shell tanks. The tank waste is to be retrieved, separated into low and high-activity fractions, and then immobilized by private vendors. The US Department of Energy (DOE) will receive the vitrified waste from private vendors and plans to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at Hanford until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to issue a Disposal Authorization Statement that would allow the modification of the four existing concrete disposal vaults to provide better access for emplacement of the immobilized low-activity waste (ILAW) containers; filling of the modified vaults with the approximately 5,000 ILAW containers and filler material with the intent to dispose of the containers; construction of the first set of next-generation disposal facilities. The performance assessment activity will continue beyond this assessment. The activity will collect additional data on the geotechnical features of the disposal sites, the disposal facility design and construction, and the long-term performance of the waste. Better estimates of long-term performance will be produced and reviewed on a regular basis. Performance assessments supporting closure of filled facilities will be issued seeking approval of those actions necessary to conclude active disposal facility operations. This report also analyzes the long-term performance of the currently planned disposal system as a basis

  3. Hanford immobilized low-activity tank waste performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Mann, F.M.

    1998-03-26

    The Hanford Immobilized Low-Activity Tank Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-level fraction of waste presently contained in Hanford Site tanks. The tank waste is the by-product of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste has been stored in underground single and double-shell tanks. The tank waste is to be retrieved, separated into low and high-activity fractions, and then immobilized by private vendors. The US Department of Energy (DOE) will receive the vitrified waste from private vendors and plans to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at Hanford until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to issue a Disposal Authorization Statement that would allow the modification of the four existing concrete disposal vaults to provide better access for emplacement of the immobilized low-activity waste (ILAW) containers; filling of the modified vaults with the approximately 5,000 ILAW containers and filler material with the intent to dispose of the containers; construction of the first set of next-generation disposal facilities. The performance assessment activity will continue beyond this assessment. The activity will collect additional data on the geotechnical features of the disposal sites, the disposal facility design and construction, and the long-term performance of the waste. Better estimates of long-term performance will be produced and reviewed on a regular basis. Performance assessments supporting closure of filled facilities will be issued seeking approval of those actions necessary to conclude active disposal facility operations. This report also analyzes the long-term performance of the currently planned disposal system as a basis

  4. The impact of Docker containers on the performance of genomic pipelines.

    Science.gov (United States)

    Di Tommaso, Paolo; Palumbo, Emilio; Chatzou, Maria; Prieto, Pablo; Heuer, Michael L; Notredame, Cedric

    2015-01-01

    Genomic pipelines consist of several pieces of third party software and, because of their experimental nature, frequent changes and updates are commonly necessary thus raising serious deployment and reproducibility issues. Docker containers are emerging as a possible solution for many of these problems, as they allow the packaging of pipelines in an isolated and self-contained manner. This makes it easy to distribute and execute pipelines in a portable manner across a wide range of computing platforms. Thus, the question that arises is to what extent the use of Docker containers might affect the performance of these pipelines. Here we address this question and conclude that Docker containers have only a minor impact on the performance of common genomic pipelines, which is negligible when the executed jobs are long in terms of computational time.

  5. The impact of Docker containers on the performance of genomic pipelines

    Directory of Open Access Journals (Sweden)

    Paolo Di Tommaso

    2015-09-01

    Full Text Available Genomic pipelines consist of several pieces of third party software and, because of their experimental nature, frequent changes and updates are commonly necessary thus raising serious deployment and reproducibility issues. Docker containers are emerging as a possible solution for many of these problems, as they allow the packaging of pipelines in an isolated and self-contained manner. This makes it easy to distribute and execute pipelines in a portable manner across a wide range of computing platforms. Thus, the question that arises is to what extent the use of Docker containers might affect the performance of these pipelines. Here we address this question and conclude that Docker containers have only a minor impact on the performance of common genomic pipelines, which is negligible when the executed jobs are long in terms of computational time.

  6. Performance behavior of the passive containment cooling system of a natural circulation BWR during postulated accident condition

    International Nuclear Information System (INIS)

    Kumar, Mukesh; Nayak, A.K.; Jain, Vikas; Vijayan, P.K.; Saha, D.; Sinha, R.K.

    2011-01-01

    Passive systems are playing prominent role in the development of innovative nuclear reactor systems due to their simplicity, enhanced safety, reliability and economy. These systems are being considered for normal operation as well as accidental conditions of reactor following a postulated accident scenario to preclude the scenarios arising out of failure of active systems as well as to minimize the operator intervention. Indian innovative reactor AHWR being designed for thorium utilization employs various passive safety concepts. As containment is the ultimate barrier to the release of radioactivity, passive concepts are being employed in BWRs for minimize peak containment pressure in the containment during a postulated accident condition like LOCA. The concept of passive containment cooling system (PCCS) in the AHWR comprises of inclined tube heat exchangers located underneath an elevated pool that removes the heat from the steam-air atmosphere of containment following a LOCA by natural circulation of water inside the tubes. The steam condenses on the external surface of tubes of PCCS in addition to the wall of the containment which in turn depressurizes the containment. This paper deals with the performance assessment of PCCS of AHWR during a postulated design basis LOCA by using the best estimate code RELAP5/Mod3.2. (author)

  7. Assessing ventilation system performance in isolation rooms

    Energy Technology Data Exchange (ETDEWEB)

    Balocco, Carla [Department of Energy Engineering ' ' Sergio Stecco' ' , via S. Marta 3, Firenze (Italy); Lio, Pietro [Computer Laboratory, University of Cambridge, 15 JJ Thompson Avenue, CB03FD Cambridge (United Kingdom)

    2011-01-15

    In this paper numerical transient simulations were used to investigate the air flow patterns, distribution and velocity, and the particulate dispersion inside an existing typical hospitalization room equipped with an advanced Heating Ventilation Air Conditioning (HVAC), with Variable Air Volume (VAV) primary air system designed for immune-suppressed patients never modelled before. The three-dimensional models of the room consider different, most typical, positions of the patients. Results indicate the best conditions for the high induction air inlet diffuser and the scheme of pressures imposed in the room to provide the effective means of controlling flows containing virus droplets. We believe that our work exemplifies the usefulness of numerical investigations of HVAC performances in real situations and provides important recommendations towards disease control and careful design and optimization of ventilation in hospital settings. (author)

  8. Safety assessment of a dry storage container drop into irradiated fuel bays

    International Nuclear Information System (INIS)

    Parlatan, Y.; Oh, D.; Arguner, D.; Lei, Q.M.; Kulpa, T.; Bayoumi, M.H.

    2004-01-01

    In Pickering nuclear stations, Dry Storage Containers (DSCs) are employed to transfer used (irradiated) fuel from an irradiated fuel bay to a dry storage facility for interim storage. Each DSC is wet-loaded in the bay water with 4 fuel modules containing up to a total of 384 used fuel bundles that have been out of the reactor core for at least 10 years. Once the DSC is fully loaded, the crane in the bay raises the DSC for spray-wash such that the bottom of the DSC is never more than 2 m above the bay water surface. This paper presents a safety assessment of consequences of an unlikely event that a fully loaded DSC is accidentally dropped into an irradiated fuel bay from the highest possible elevation. Experiments and analyses performed elsewhere show that the DSC drop-generated shock waves will not threaten the structural integrity of an irradiated fuel bay. Therefore, this assessment only assesses the potential damage to the spent fuel bundles in the bay due to pressure transients generated by an accidental DSC drop. A bounding estimate approach has been used to calculate the upper limit of the pressure pulse and the resulting static and dynamic stresses on the fuel sheath. The bounding calculations and relevant experimental results demonstrate that an accidental drop of a fully loaded DSC into an irradiated fuel bay will not cause additional failures of the main fuel inventories stored in modules in the bay water, thus no consequential release of fission products into the bay water. (author)

  9. Methodology for assessing performance of waste management systems

    International Nuclear Information System (INIS)

    Meshkov, N.K.; Herzenberg, C.L.; Camasta, S.F.

    1988-01-01

    The newly revised draft DOE Order 5820.2, Chapter 3, requires that DOE low-level waste shall be managed on a systematic basis using the most appropriate combination of waste generation reduction, segregation, treatment, and disposal practices so that the radioactive components are contained and the overall cost effectiveness is minimized. This order expects each site to prepare and maintain an overall waste management systems performance assessment supporting the combination of waste management practices used in generation reduction segregation, treatment, packaging, storage, and disposal. A document prepared by EG and G Idaho, Inc. for the Department of Energy called Guidance for Conduct of Waste Management Systems Performance Assessment is specifically intended to provide the approach necessary to meet the systems performance assessment requirement of DOE Order 5820.2, Chapter 3, and other applicable state regulations dealing with LLW (low-level radioactive wastes). Methods and procedures are needed for assessing the performance of a waste management system. This report addresses this need. The purpose of the methodology provided in this report is to select the optimal way to manage particular sets of waste streams from generation to disposal in a safe and cost-effective manner, and thereby assist the DOE LLW mangers in complying with the DOE Order 5820.2, Chapter 3, and the associated guidance document

  10. Performance assessment modeling of pyrometallurgical process wasteforms

    International Nuclear Information System (INIS)

    Nutt, W.M.; Hill, R.N.; Bullen, D.B.

    1995-01-01

    Performance assessment analyses have been completed to estimate the behavior of high-level nuclear wasteforms generated from the pyrometallurgical processing of liquid metal reactor (LMR) and light water reactor (LWR) spent nuclear fuel. Waste emplaced in the proposed repository at Yucca Mountain is investigated as the basis for the study. The resulting cumulative actinide and fission product releases to the accessible environment within a 100,000 year period from the various pyrometallurgical process wasteforms are compared to those of directly disposed LWR spent fuel using the same total repository system model. The impact of differing radionuclide transport models on the overall release characteristics is investigated

  11. Use of PSA Level 2 analysis for improving containment performance. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1998-03-01

    In order to discuss and exchange experience on different aspects of methods associated with Level 2 PSA and its applications for improving containment performance, the IAEA held a Technical Committee meeting in Vienna in December 1996. The meeting, which was attended by 26 participants from 20 Member States, provided a broad forum for discussion. The meeting addressed the issues related to the actual performance of Level 2 PSA studies as well as the insights gained from applications to improve containment performance. Particular attention was given to studies and applications for WWER type reactors, for which Level 2 work is still in its early stages, and for channel type reactors where modelling of accident progression is complex and significantly different from vessel type light water reactors. This TECDOC contains the papers presented at the meeting and the results of extensive discussions which were held in specific working groups

  12. Building Confidence in LLW Performance Assessments - 13386

    Energy Technology Data Exchange (ETDEWEB)

    Rustick, Joseph H.; Kosson, David S.; Krahn, Steven L.; Clarke, James H. [Vanderbilt University, Department of Civil and Environmental Engineering and Consortium for Risk Evaluation with Stakeholder Participation, Nashville, Tennessee, 37235 (United States)

    2013-07-01

    The performance assessment process and incorporated input assumptions for four active and one planned DOE disposal sites were analyzed using a systems approach. The sites selected were the Savannah River E-Area Slit and Engineered Trenches, Hanford Integrated Disposal Facility, Idaho Radioactive Waste Management Complex, Oak Ridge Environmental Management Waste Management Facility, and Nevada National Security Site Area 5. Each disposal facility evaluation incorporated three overall system components (1) site characteristics (climate, geology, geochemistry, etc.), (2) waste properties (waste form and package), and (3) engineered barrier designs (cover system, liner system). Site conceptual models were also analyzed to identity the main risk drivers and risk insights controlling performance for each disposal facility. (authors)

  13. Building Confidence in LLW Performance Assessments - 13386

    International Nuclear Information System (INIS)

    Rustick, Joseph H.; Kosson, David S.; Krahn, Steven L.; Clarke, James H.

    2013-01-01

    The performance assessment process and incorporated input assumptions for four active and one planned DOE disposal sites were analyzed using a systems approach. The sites selected were the Savannah River E-Area Slit and Engineered Trenches, Hanford Integrated Disposal Facility, Idaho Radioactive Waste Management Complex, Oak Ridge Environmental Management Waste Management Facility, and Nevada National Security Site Area 5. Each disposal facility evaluation incorporated three overall system components (1) site characteristics (climate, geology, geochemistry, etc.), (2) waste properties (waste form and package), and (3) engineered barrier designs (cover system, liner system). Site conceptual models were also analyzed to identity the main risk drivers and risk insights controlling performance for each disposal facility. (authors)

  14. Development and assessment of a fiber reinforced HPC container for radioactive waste

    International Nuclear Information System (INIS)

    Roulet, A.; Pineau, F.; Chanut, S.; Thibaux, Th.

    2007-01-01

    As part of its research into solutions for concrete disposal containers for long-lived radioactive waste, Andra defined requirements for high-performance concretes with enhanced porosity, diffusion, and permeability characteristics. It is the starting point for further research into severe conditions of containment and durability. To meet these objectives, Eiffage TP consequently developed a highly fibered High Performance Concrete (HPC) design mix using CEM V cement and silica fume. Then, mockups were produced to characterize the performance various concepts of containers with this new concrete mix. These mockups helped to identify possible manufacturing problems, and particularly the risk of cracking due to restrained shrinkage. (authors)

  15. Modelling saline intrusion for repository performance assessment

    International Nuclear Information System (INIS)

    Jackson, C.P.

    1989-04-01

    UK Nirex Ltd are currently considering the possibility of disposal of radioactive waste by burial in deep underground repositories. The natural pathway for radionuclides from such a repository to return to Man's immediate environment (the biosphere) is via groundwater. Thus analyses of the groundwater flow in the neighbourhood of a possible repository, and consequent radionuclide transport form an important part of a performance assessment for a repository. Some of the areas in the UK that might be considered as possible locations for a repository are near the coast. If a repository is located in a coastal region seawater may intrude into the groundwater flow system. As seawater is denser than fresh water buoyancy forces acting on the intruding saline water may have significant effects on the groundwater flow system, and consequently on the time for radionuclides to return to the biosphere. Further, the chemistry of the repository near-field may be strongly influenced by the salinity of the groundwater. It is therefore important for Nirex to have a capability for reliably modelling saline intrusion to an appropriate degree of accuracy in order to make performance assessments for a repository in a coastal region. This report describes work undertaken in the Nirex Research programme to provide such a capability. (author)

  16. Performance assessment task team progress report

    International Nuclear Information System (INIS)

    Wood, D.E.; Curl, R.U.; Armstrong, D.R.; Cook, J.R.; Dolenc, M.R.; Kocher, D.C.; Owens, K.W.; Regnier, E.P.; Roles, G.W.; Seitz, R.R.

    1994-05-01

    The U.S. Department of Energy (DOE) Headquarters EM-35, established a Performance Assessment Task Team (referred to as the Team) to integrate the activities of the sites that are preparing performance assessments (PAs) for disposal of new low-level waste, as required by Chapter III of DOE Order 5820.2A, open-quotes Low-Level Waste Managementclose quotes. The intent of the Team is to achieve a degree of consistency among these PAs as the analyses proceed at the disposal sites. The Team's purpose is to recommend policy and guidance to the DOE on issues that impact the PAs, including release scenarios and parameters, so that the approaches are as consistent as possible across the DOE complex. The Team has identified issues requiring attention and developed discussion papers for those issues. Some issues have been completed, and the recommendations are provided in this document. Other issues are still being discussed, and the status summaries are provided in this document. A major initiative was to establish a subteam to develop a set of test scenarios and parameters for benchmarking codes in use at the various sites. The activities of the Team are reported here through December 1993

  17. Consideration of environmental change in performance assessments

    International Nuclear Information System (INIS)

    Pinedo, P.; Thorne, M.; Egan, M.; Calvez, M.; Kautsky, U.

    2005-01-01

    Depending on the particular circumstances in which a post-closure performance assessment of a radioactive waste repository is made, it may be appropriate to follow simple or more complex approaches in characterising the biosphere. Several different Example Reference Biospheres were explored in BIOMASS Theme 1 to address a range of issues that arise. Here, consideration is given to Example Reference Biospheres relevant to representing the implications of changes that may occur within the biosphere system during the period over which releases of radionuclides from a disposal facility might take place. Mechanisms of change considered include those extrinsic and intrinsic to the system of interest. An overall methodology for incorporating environmental change into assessments is proposed. This includes screening of primary mechanisms of change; identification of possible time sequences of change; development of a coherent description of the regional landscape response for each time sequence; integration of source term and geosphere-biosphere interface information; identification and description of one or more time series of assessment biospheres; and evaluation of the advantages and disadvantages of simulating the effects of sequences of biosphere systems and the transitions between them, or of defining a set of biosphere systems to be represented individually in a non-sequential analysis. The usefulness of the methodology is explored in two site-specific examples and one generic example

  18. Designing a database for performance assessment: Lessons learned from WIPP

    International Nuclear Information System (INIS)

    Martell, M.A.; Schenker, A.

    1997-01-01

    The Waste Isolation Pilot Plant (WIPP) Compliance Certification Application (CCA) Performance Assessment (PA) used a relational database that was originally designed only to supply the input parameters required for implementation of the PA codes. Reviewers used the database as a point of entry to audit quality assurance measures for control, traceability, and retrievability of input information used for analysis, and output/work products. During these audits it became apparent that modifications to the architecture and scope of the database would benefit the EPA regulator and other stakeholders when reviewing the recertification application. This paper contains a discussion of the WPP PA CCA database and lessons learned for designing a database

  19. Performance Assessment of a Post-Closure Pyrophoric Event

    International Nuclear Information System (INIS)

    Duguid, J.O.; Senger, R.K.; Leem, J.

    2002-01-01

    This paper describes analyses of a potential post-closure pyrophoric event in a waste package containing uranium metal spent fuel. The analyses include temperature at adjacent waste packages caused by the event and the dose to humans due to the event. The thermal analyses show that the event would not be expected to damage the adjacent waste packages. The dose analyses show that the doses due to the event are small. These analyses provide support to screening arguments used to demonstrate that the pyrophoric event should not be considered in the total system performance assessment model

  20. Performance assessment plans and methods for the Salt Repository Project

    International Nuclear Information System (INIS)

    1984-08-01

    This document presents the preliminary plans and anticipated methods of the Salt Repository Project (SRP) for assessing the postclosure and radiological aspects of preclosure performance of a nuclear waste repository in salt. This plan is intended to be revised on an annual basis. The emphasis in this preliminary effort is on the method of conceptually dividing the system into three subsystems (the very near field, the near field, and the far field) and applying models to analyze the behavior of each subsystem and its individual components. The next revision will contain more detailed plans being developed as part of Site Characterization Plan (SCP) activities. After a brief system description, this plan presents the performance targets which have been established for nuclear waste repositories by regulatory agencies (Chapter 3). The SRP approach to modeling, including sensitivity and uncertainty techniques is then presented (Chapter 4). This is followed by a discussion of scenario analysis (Chapter 5), a presentation of preliminary data needs as anticipated by the SRP (Chapter 6), and a presentation of the SRP approach to postclosure assessment of the very near field, the near field, and the far field (Chapters 7, 8, and 9, respectively). Preclosure radiological assessment is discussed in Chapter 10. Chapter 11 presents the SRP approach to code verification and validation. Finally, the Appendix lists all computer codes anticipated for use in performance assessments. The list of codes will be updated as plans are revised

  1. Performance Analysis on Transfer Platforms in Frame Bridge Based Automated Container Terminals

    Directory of Open Access Journals (Sweden)

    Hongtao Hu

    2013-01-01

    Full Text Available This paper studies a new automated container terminal (ACT system which utilizes multistory frame bridges and rail-mounted trolleys to transport containers between the quay and the yard. Beside typical ACT systems use trucks or automated guided vehicles for transporting containers between quay cranes and yard cranes, the new design uses three types of handling machines, namely, ground trolleys (GTs, transfer platforms (TPs, and frame trolleys (FTs. These three types of handling machines collaborate with one another to transport containers. This study decomposes the system into several subsystems. Each subsystem has one TP and several FTs and GTs dedicated to this TP. Then, a Markov chain model is developed to analyze the throughput of TPs. At last, the performance of the new ACT system is estimated. Sensitivity analyzes the numbers, and the processing rates of trolleys are conducted through the numeric experiments.

  2. Methyllithium-Doped Naphthyl-Containing Conjugated Microporous Polymer with Enhanced Hydrogen Storage Performance.

    Science.gov (United States)

    Xu, Dan; Sun, Lei; Li, Gang; Shang, Jin; Yang, Rui-Xia; Deng, Wei-Qiao

    2016-06-01

    Hydrogen storage is a primary challenge for using hydrogen as a fuel. With ideal hydrogen storage kinetics, the weak binding strength of hydrogen to sorbents is the key barrier to obtain decent hydrogen storage performance. Here, we reported the rational synthesis of a methyllithium-doped naphthyl-containing conjugated microporous polymer with exceptional binding strength of hydrogen to the polymer guided by theoretical simulations. Meanwhile, the experimental results showed that isosteric heat can reach up to 8.4 kJ mol(-1) and the methyllithium-doped naphthyl-containing conjugated microporous polymer exhibited an enhanced hydrogen storage performance with 150 % enhancement compared with its counterpart naphthyl-containing conjugated microporous polymer. These results indicate that this strategy provides a direction for design and synthesis of new materials that meet the US Department of Energy (DOE) hydrogen storage target. © 2016 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  3. The Waste Isolation Pilot Plant Performance Assessment Program

    International Nuclear Information System (INIS)

    Myers, J.; Coons, W.E.; Eastmond, R.; Morse, J.; Chakrabarti, S.; Zurkoff, J.; Colton, I.D.; Banz, I.

    1986-01-01

    The Waste Isolation Pilot Plant (WIPP) Performance Assessment Program involves a comprehensive analysis of the WIPP project with respect to the recently finalized Environmental Protection Agency regulations regarding the long-term geologic isolation of radioactive wastes. The performance assessment brings together the results of site characterization, underground experimental, and environmental studies into a rigorous determination of the performance of WIPP as a disposal system for transuranic radioactive waste. The Program consists of scenario development, geochemical, hydrologic, and thermomechanical support analyses and will address the specific containment and individual protection requirements specified in 40 CFR 191 sub-part B. Calculated releases from these interrelated analyses will be reported as an overall probability distribution of cumulative release resulting from all processes and events occurring over the 10,000 year post-closure period. In addition, results will include any doses to the public resulting from natural processes occurring over the 1,000 year post-closure period. The overall plan for the WIPP Performance Assessment Program is presented along with approaches to issues specific to the WIPP project

  4. Electrochemical Performance of Low-Carbon Steel in Alkaline Model Solutions Containing Hybrid Aggregates

    NARCIS (Netherlands)

    Koleva, D.A.; Hu, J.; De Wit, J.H.W.; Boshkov, N.; Radeva, T.; Milkova, V.; Van Breugel, K.

    2010-01-01

    This work reports on the electrochemical performance of low-carbon steel electrodes in model alkaline solutions in the presence of 4.9.10-4 g/l hybrid aggregates i.e. cement extract, containing PDADMAC (poly (diallyl, dimethyl ammonium chloride) / PAA (Poly (acrylic acid)/ PDADMAC over a CaO core.

  5. The use of repassivation potential in predicting the performance of high-level nuclear waste container materials

    International Nuclear Information System (INIS)

    Sridhar, N.; Dunn, D.; Cragnolino, G.

    1995-01-01

    Localized corrosion in aqueous environments forms an important bounding condition for the performance assessment of high-level waste (HLW) container materials. A predictive methodology using repassivation potential is examined in this paper. It is shown, based on long-term (continuing for over 11 months) testing of alloy 825, that repassivation potential of deep pits or crevices is a conservative and robust parameter for the prediction of localized corrosion. In contrast, initiation potentials measured by short-term tests are non-conservative and highly sensitive to several surface and environmental factors. Corrosion data from various field tests and plant equipment performance are analyzed in terms of the applicability of repassivation potential. The applicability of repassivation potential for predicting the occurrence of stress corrosion cracking (SCC) and intergranular corrosion in chloride containing environments is also examined

  6. Program to develop analytical tools for environmental and safety assessment of nuclear material shipping container systems

    International Nuclear Information System (INIS)

    Butler, T.A.

    1978-11-01

    This paper describes a program for developing analytical techniques to evaluate the response of nuclear material shipping containers to severe accidents. Both lumped-mass and finite element techniques are employed to predict shipping container and shipping container-carrier response to impact. The general impact problem is computationally expensive because of its nonlinear, three-dimensional nature. This expense is minimized by using approximate models to parametrically identify critical cases before more exact analyses are performed. The computer codes developed for solving the problem are being experimentally substantiated with test data from full-scale and scale-model container drop tests. 6 figures, 1 table

  7. Scientific performance assessments through a gender lens

    DEFF Research Database (Denmark)

    Nielsen, Mathias Wullum

    2018-01-01

    The focus on excellence and quality assurance in the academy has spawned a signifi cant increase in the use of bibliometric measures in performance assessments of individual researchers. This article investigates the organizational consequences of this development through a gender lens. Based...... scholars, evaluators using bibliometrics risk disadvantaging candidates diverging from the norm with implications for gender stratifi cation. Despite these potential biases, bibliometric measures come to function as technologies supporting a managerial narrative of the gender-blind organization....... They adhere to the prevailing ethos of the academic meritocracy by standardizing the criteria for organizational advancement and ensuring transparency and accountability in the selection process. While bibliometric tools in this sense may lead to the recruitment of scientists with a strong CV and track record...

  8. Performing Probabilistic Risk Assessment Through RAVEN

    Energy Technology Data Exchange (ETDEWEB)

    A. Alfonsi; C. Rabiti; D. Mandelli; J. Cogliati; R. Kinoshita

    2013-06-01

    The Reactor Analysis and Virtual control ENviroment (RAVEN) code is a software tool that acts as the control logic driver and post-processing engine for the newly developed Thermal-Hydraulic code RELAP-7. RAVEN is now a multi-purpose Probabilistic Risk Assessment (PRA) software framework that allows dispatching different functionalities: Derive and actuate the control logic required to simulate the plant control system and operator actions (guided procedures), allowing on-line monitoring/controlling in the Phase Space Perform both Monte-Carlo sampling of random distributed events and Dynamic Event Tree based analysis Facilitate the input/output handling through a Graphical User Interface (GUI) and a post-processing data mining module

  9. Aging assessment of Westinghouse PWR and General Electric BWR containment isolation functions

    Energy Technology Data Exchange (ETDEWEB)

    Lee, B.S.; Travis, R.; Grove, E.; DiBiasio, A.

    1996-03-01

    A study was performed to assess the effects of aging on the Containment Isolation (CI) functions of Westinghouse Pressurized Water Reactors and General Electric Boiling Water Reactors. This study is part of the Nuclear Plant Aging Research (NPAR) program, sponsored by the U.S. Nuclear Regulatory Commission. The objectives of this program are to provide an understanding of the aging process and how it affects plant safety so that it can be properly managed. This is one of a number of studies performed under the NPAR program which provide a technical basis for the identification and evaluation of degradation caused by age. Failure data from two national databases, Nuclear Plant Reliability Data System (NPRDS) and Licensee Event Reports (LERs), as well as plant specific data were reviewed and analyzed to understand the effects of aging on the CI functions. This study provided information on the effects of aging on component failure frequency, failure modes, and failure causes. Current inspection, surveillance, and monitoring practices were also reviewed.

  10. Aging assessment of Westinghouse PWR and General Electric BWR containment isolation functions

    International Nuclear Information System (INIS)

    Lee, B.S.; Travis, R.; Grove, E.; DiBiasio, A.

    1996-03-01

    A study was performed to assess the effects of aging on the Containment Isolation (CI) functions of Westinghouse Pressurized Water Reactors and General Electric Boiling Water Reactors. This study is part of the Nuclear Plant Aging Research (NPAR) program, sponsored by the U.S. Nuclear Regulatory Commission. The objectives of this program are to provide an understanding of the aging process and how it affects plant safety so that it can be properly managed. This is one of a number of studies performed under the NPAR program which provide a technical basis for the identification and evaluation of degradation caused by age. Failure data from two national databases, Nuclear Plant Reliability Data System (NPRDS) and Licensee Event Reports (LERs), as well as plant specific data were reviewed and analyzed to understand the effects of aging on the CI functions. This study provided information on the effects of aging on component failure frequency, failure modes, and failure causes. Current inspection, surveillance, and monitoring practices were also reviewed

  11. Probabilistic Radiological Performance Assessment Modeling and Uncertainty

    Science.gov (United States)

    Tauxe, J.

    2004-12-01

    A generic probabilistic radiological Performance Assessment (PA) model is presented. The model, built using the GoldSim systems simulation software platform, concerns contaminant transport and dose estimation in support of decision making with uncertainty. Both the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Department of Energy (DOE) require assessments of potential future risk to human receptors of disposal of LLW. Commercially operated LLW disposal facilities are licensed by the NRC (or agreement states), and the DOE operates such facilities for disposal of DOE-generated LLW. The type of PA model presented is probabilistic in nature, and hence reflects the current state of knowledge about the site by using probability distributions to capture what is expected (central tendency or average) and the uncertainty (e.g., standard deviation) associated with input parameters, and propagating through the model to arrive at output distributions that reflect expected performance and the overall uncertainty in the system. Estimates of contaminant release rates, concentrations in environmental media, and resulting doses to human receptors well into the future are made by running the model in Monte Carlo fashion, with each realization representing a possible combination of input parameter values. Statistical summaries of the results can be compared to regulatory performance objectives, and decision makers are better informed of the inherently uncertain aspects of the model which supports their decision-making. While this information may make some regulators uncomfortable, they must realize that uncertainties which were hidden in a deterministic analysis are revealed in a probabilistic analysis, and the chance of making a correct decision is now known rather than hoped for. The model includes many typical features and processes that would be part of a PA, but is entirely fictitious. This does not represent any particular site and is meant to be a generic example. A

  12. Effect of long-lived containers on the postclosure performance of a reference disposal system

    International Nuclear Information System (INIS)

    Goodwin, B.W.; Hajas, W.C.; LeNeveu, D.M.

    1996-05-01

    The concept for disposal of Canada's nuclear fuel waste involves isolating the waste in corrosion-resistant containers emplaced in a scaled vault at a depth of 500 to 1000 m in plutonic rock of the Canadian Shield. The concept permits a choice of methods, materials, site locations, and designs. The technical feasibility of this concept and its impact on the environment and human health are summarized in an Environmental Impact Statement (AECL 1994a,b), supported by nine detailed reference documents (Davis et al. 1993; Davison et al. 1994a,b; Goodwin et al. 1994; Greber et al. 1994; Grondin et al. 1994; Johnson et al. 1994a,b; Simmons and Baumgartner 1994). In the assessment of the reference disposal system, we assumed the containers encapsulating the nuclear fuel waste were constructed from Grade-2 titanium. In this report, we investigate the effect of a different choice, and assume the use of long-lived containers constructed from materials such as high-purity copper or Grades-12 or -16 titanium alloys. These alternative materials would provide much longer periods of protection, based on the expectation that the only container failure mechanism, for times up to 10 5 a, involves initial fabrication defects. We explore the effects of long-lived containers for the same vault layout and orientation that were assumed for the reference disposal vault. We also explore effects for two less favourable situations, in which the vault is closer to a nearby fracture zone and in which the vault is extended to have emplacement rooms on both sides of the fracture zone. Our analyses use the probabilistic assessment computer code, SYVAC3-CC3, an acronym for SYstems Variability Analysis Code, generation 3. with a system model describing the Canadian Concept, generation 3, for the disposal of nuclear fuel waste. The input data for the code have been adjusted to approximate the expected protection characteristics of alternative container materials. (author). 31 refs., 1 tab., 16 figs

  13. Structural capacity assessment of a generic pre-stressed concrete containment structure under aircraft impact

    International Nuclear Information System (INIS)

    Iliev, Alexander

    2013-01-01

    The studied containment expressed adequate capacity to resist impact loads in the upper range of the studied diapason. The aircraft impact capacity of the containment for impact in the upper part of the cylindrical shell is about 25‐30% higher than the capacity for impact in the middle part of the cylindrical shell. The obtained fragility curves reefed to MoA can be then used for various additional calculations in the safety assessment of nuclear facilities under aircraft impact

  14. E-Area Performance Assessment Interim Measures Assessment FY2005

    Energy Technology Data Exchange (ETDEWEB)

    Stallings, M

    2006-01-31

    After major changes to the limits for various disposal units of the E-Area Low Level Waste Facility (ELLWF) last year, no major changes have been made during FY2005. A Special Analysis was completed which removes the air pathway {sup 14}C limit from the Intermediate Level Vault (ILV). This analysis will allow the disposal of reactor moderator deionizers which previously had no pathway to disposal. Several studies have also been completed providing groundwater transport input for future special analyses. During the past year, since Slit Trenches No.1 and No.2 were nearing volumetric capacity, they were operationally closed under a preliminary closure analysis. This analysis was performed using as-disposed conditions and data and showed that concrete rubble from the demolition of 232-F was acceptable for disposal in the STs even though the latest special analysis for the STs had reduced the tritium limits so that the inventory in the rubble exceeded limits. A number of special studies are planned during the next years; perhaps the largest of these will be revision of the Performance Assessment (PA) for the ELLWF. The revision will be accomplished by incorporating special analyses performed since the last PA revision as well as revising analyses to include new data. Projected impacts on disposal limits of more recent studies have been estimated. No interim measures will be applied during this year. However, it is being recommended that tritium disposals to the Components-in-Grout (CIG) Trenches be suspended until a limited Special Analysis (SA) currently in progress is completed. This SA will give recommendations for optimum placement of tritiated D-Area tower waste. Further recommendations for tritiated waste placement in the CIG Trenches will be given in the upcoming PA revision.

  15. Structural capacity assessment of WWER-1000 MW reactor containment. Progress report

    International Nuclear Information System (INIS)

    Jordanov, M.

    1999-01-01

    The objective of the project is to provide assessment of the structural behaviour and safety capacity of the WWER-1000 MW Reactor Building Containment at Kozloduy NPP under critical combination of loads according to the current international requirements. The analysis is focused on a realistic assessment of the Containment taking into account the non-linear shell behaviour of the pre-stressed reinforced concrete structure. Previous assessments of the status of pre stressing cables pointed out that the efficiency of the Containment as a final defence barrier for internal and external events depends on their reliability. Due to this, the experimental data obtained from embedded sensors (gauges) at pre-stressed shell structure is to be compared with the results from analytical investigations. The reliability of the WWER-1000 MW accident prevention system is under evaluation in the project. The Soviet standard design WWER-1000 MW type units installed in Kozloduy NPP were originally designed for a Safe Shutdown Earthquake (SSE) with a peak ground acceleration (PGA) of 0.1g. The new site seismicity studies revealed that the seismic hazard for the site significantly exceeds the originally estimated and a Review Level Earthquake (RLE) anchored to PGA=0.20g was proposed for re-assessment of the structures and equipment at Kozloduy NPP. The scope of the study is a re-assessment of the Containment structure under critical combination of loads according to the current safety and reliability requirements, including comparison between the Russian design requirements and the international regulations. Additionally, an investigation of the pre-stressing technology and the annual control of the cables' pre-stressing of the Containment is to be made. The crane influence on the dynamic behaviour of the Containment will be done as well as a study of the integrity of the Containment as a final defence barrier

  16. Containment response analysis for the PSA (Probabilistic Safety Assessment) of the CAREM-25 nuclear power plant

    International Nuclear Information System (INIS)

    Baron, J.H.

    1997-01-01

    This work is part of the probabilistic safety assessment actually under development for the CAREM-25 nuclear power station, and departs from the accident sequences already obtained and quantified by the Event Trees/Fault Trees techniques. At first, the potential containment failure modes for nuclear stations are listed, based on the experience. Then, the CAREM-25 design peculiarities are analyzed, on their possible influence on the containment behavior during severe accidents. Then plan damage states are defined. Furthermore, containment damage states are also defined, and containment event trees are built for each plant damage state. Those sequences considered representative from the annual probability (those which exceed or probability of IE-09 per year, are used to quantify the combinations of plant damage states/containment damage states, based on the estimation of a vulnerability matrix. (author) [es

  17. The IPE Database: providing information on plant design, core damage frequency and containment performance

    International Nuclear Information System (INIS)

    Lehner, J.R.; Lin, C.C.; Pratt, W.T.; Su, T.; Danziger, L.

    1996-01-01

    A database, called the IPE Database has been developed that stores data obtained from the Individual Plant Examinations (IPEs) which licensees of nuclear power plants have conducted in response to the Nuclear Regulatory Commission's (NRC) Generic Letter GL88-20. The IPE Database is a collection of linked files which store information about plant design, core damage frequency (CDF), and containment performance in a uniform, structured way. The information contained in the various files is based on data contained in the IPE submittals. The information extracted from the submittals and entered into the IPE Database can be manipulated so that queries regarding individual or groups of plants can be answered using the IPE Database

  18. Cucumber cultivars for container gardening and the value of field trials for predicting Cucumber performance in containers

    Science.gov (United States)

    Cucumber (Cucumis sativus L.) is one of the most popular vegetable crops grown in U.S. home and urban gardens. The objectives of this study were to identify cultivars and planting densities for high yield of container-grown cucumbers. Additional objectives were to determine the value of field trials...

  19. Development of internal dose assessment procedure for workers in industries using raw materials containing naturally occurring radioactive materials

    International Nuclear Information System (INIS)

    Choi, Cheol Kyu; KIm, Yong Geon; Ji, Seung Woo; Kim, Kwang Pyo; Koo, Bon Cheol; Chang, Byung Uck

    2016-01-01

    It is necessary to assess radiation dose to workers due to inhalation of airborne particulates containing naturally occurring radioactive materials (NORM) to ensure radiological safety required by the Natural Radiation Safety Management Act. The objective of this study is to develop an internal dose assessment procedure for workers at industries using raw materials containing natural radionuclides. The dose assessment procedure was developed based on harmonization, accuracy, and proportionality. The procedure includes determination of dose assessment necessity, preliminary dose estimation, airborne particulate sampling and characterization, and detailed assessment of radiation dose. The developed dose assessment procedure is as follows. Radioactivity concentration criteria to determine dose assessment necessity are 10 Bq·g-1 for 40K and 1 Bq·g-1 for the other natural radionuclides. The preliminary dose estimation is performed using annual limit on intake (ALI). The estimated doses are classified into 3 groups (<0.1 mSv, 0.1-0.3 mSv, and >0.3 mSv). Air sampling methods are determined based on the dose estimates. Detailed dose assessment is performed using air sampling and particulate characterization. The final dose results are classified into 4 different levels (<0.1 mSv, 0.1-0.3 mSv, 0.3-1 mSv, and >1 mSv). Proper radiation protection measures are suggested according to the dose level. The developed dose assessment procedure was applied for NORM industries in Korea, including coal combustion, phosphate processing, and monazite handing facilities. The developed procedure provides consistent dose assessment results and contributes to the establishment of optimization of radiological protection in NORM industries

  20. Development of internal dose assessment procedure for workers in industries using raw materials containing naturally occurring radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Cheol Kyu; KIm, Yong Geon; Ji, Seung Woo; Kim, Kwang Pyo [College of Engineering, Kyung Hee University, Yongin (Korea, Republic of); Koo, Bon Cheol; Chang, Byung Uck [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2016-09-15

    It is necessary to assess radiation dose to workers due to inhalation of airborne particulates containing naturally occurring radioactive materials (NORM) to ensure radiological safety required by the Natural Radiation Safety Management Act. The objective of this study is to develop an internal dose assessment procedure for workers at industries using raw materials containing natural radionuclides. The dose assessment procedure was developed based on harmonization, accuracy, and proportionality. The procedure includes determination of dose assessment necessity, preliminary dose estimation, airborne particulate sampling and characterization, and detailed assessment of radiation dose. The developed dose assessment procedure is as follows. Radioactivity concentration criteria to determine dose assessment necessity are 10 Bq·g-1 for 40K and 1 Bq·g-1 for the other natural radionuclides. The preliminary dose estimation is performed using annual limit on intake (ALI). The estimated doses are classified into 3 groups (<0.1 mSv, 0.1-0.3 mSv, and >0.3 mSv). Air sampling methods are determined based on the dose estimates. Detailed dose assessment is performed using air sampling and particulate characterization. The final dose results are classified into 4 different levels (<0.1 mSv, 0.1-0.3 mSv, 0.3-1 mSv, and >1 mSv). Proper radiation protection measures are suggested according to the dose level. The developed dose assessment procedure was applied for NORM industries in Korea, including coal combustion, phosphate processing, and monazite handing facilities. The developed procedure provides consistent dose assessment results and contributes to the establishment of optimization of radiological protection in NORM industries.

  1. Acute effects of caffeine-containing energy drinks on physical performance: a systematic review and meta-analysis.

    Science.gov (United States)

    Souza, Diego B; Del Coso, Juan; Casonatto, Juliano; Polito, Marcos D

    2017-02-01

    Caffeine-containing energy drinks (EDs) are currently used as ergogenic aids to improve physical performance in a wide variety of sport disciplines. However, the outcomes of previous investigations on this topic are inconclusive due to methodological differences, especially, in the dosage of the active ingredients and the test used to assess performance. We performed a systematic review and meta-analysis of published studies to evaluate the effects of acute ED intake on physical performance. The search for references was conducted in the databases PubMed, ISI Web of Knowledge and SPORTDiscus until December 2015. Thirty-four studies published between 1998 and 2015 were included in the analysis. Using a random-effects model, effect sizes (ES) were calculated as the standardized mean difference. Overall, ED ingestion improved physical performance in muscle strength and endurance (ES = 0.49; p performance (slope = 0.0001; p = 0.04), but not between caffeine dosage (mg) and performance (slope = 0.0009; p = 0.21). ED ingestion improved performance in muscle strength and endurance, endurance exercise tests, jumping and sport-specific actions. However, the improvement in performance was associated with taurine dosage.

  2. Containment performance of transportable storage casks at 9m drop test

    Energy Technology Data Exchange (ETDEWEB)

    Tobita, H. [Hitachi Zosen Corp., Osaka (Japan); Araki, K. [Hitachi Zosen Diesel and Engineering Co., Ltd., Tokyo (Japan)

    2004-07-01

    Spent fuel transportable storage casks usually have a double lid closure system, which consists of primary and secondary lids, and gaskets, to keep the containment function during transportation and storage, and to monitor a leakage or containment function during storage. Metal gasket is planning to be used not only during storage but transportation of both before and after storage. As metal gasket will degrade its containment function by creep during storage period of 50 years, relative displacement such as opening and slide displacement between the flange of the containment vessel and the lid should be restricted to a small range. To maintain the containment performance, we provisionally adopted the maximum opening limit of 0.1mm and the maximum slide displacement limit of 3.0mm in the full-scale cask design based on the report of the fundamental experiment on the metal gasket which examines the relation between leakage rate and sealing gap. The purpose of this study is to analyse the behaviour of the sealed parts (lid and vessel body) under 9m-drop impact test conditions and to establish some analytical method to evaluate this behaviour. In this study, the drop test of 1/3scale model of Hitz-B69 cask with the double lids closure system was carried out, the behaviours of the seal part were measured by displacement sensors, and they were compared with the result of the numerical analysis carried out separateley.

  3. Effect of air condition on AP-1000 containment cooling performance in station black out accident

    International Nuclear Information System (INIS)

    Hendro Tjahjono

    2015-01-01

    AP1000 reactor is a nuclear power plant generation III+ 1000 MWe which apply passive cooling concept to anticipate accidents triggered by the extinction of the entire supply of electrical power or Station Black Out (SBO). In the AP1000 reactor, decay heat disposal mechanism conducted passively through the PRHR-IRWST and subsequently forwarded to the reactor containment. Containment externally cooled through natural convection in the air gap and through evaporation cooling water poured on the outer surface of the containment wall. The mechanism of evaporation of water into the air outside is strongly influenced by the conditions of humidity and air temperature. The purpose of this study was to determine the extent of the influence of the air condition on cooling capabilities of the AP1000 containment. The method used is to perform simulations using Matlab-based analytical calculation model capable of estimating the power of heat transferred. The simulation results showed a decrease in power up to 5% for relative humidity rose from 10% to 95%, while the variation of air temperature of 10°C to 40°C, the power will decrease up to 15%. It can be concluded that the effect of air temperature increase is much more significant in lowering the containment cooling ability compared with the increase of humidity. (author)

  4. Comparative Assessment of Health Workers Performance and The ...

    African Journals Online (AJOL)

    Comparative Assessment of Health Workers Performance and The Performance ... had very high significant effect on performance of health workers which was independent of ... Keywords: Health Worker Performance Factors Hospitals Nigeria ...

  5. Passive containment cooling system performance in the simplified boiling water reactor

    International Nuclear Information System (INIS)

    Shiralkar, B.S.; Gamble, R.E.; Yadigaroglu, G.

    1997-01-01

    The Simplified Boiling Water Reactor (SBWR) incorporates a passive system for decay heat removal from the containment in the event of a postulated Loss-of-Coolant Accident (LOCA). Decay heat is removed by condensation of the steam discharged from the reactor pressure vessel (RPV) in three condensers which comprise the Passive Containment Cooling System (PCCS). These condensers are designed to carry the heat load while transporting a mixture of steam and noncondensible gas (primarily nitrogen) from the drywell to the suppression chamber. This paper describes the expected LOCA response of the SBWR with respect to the PCCS performance, based on analysis and test results. The results confirm that the PCCS has excess capacity for decay heat removal and that overall system performance is very robust. 12 refs., 8 figs

  6. Assessing Ecosystem Model Performance in Semiarid Systems

    Science.gov (United States)

    Thomas, A.; Dietze, M.; Scott, R. L.; Biederman, J. A.

    2017-12-01

    In ecosystem process modelling, comparing outputs to benchmark datasets observed in the field is an important way to validate models, allowing the modelling community to track model performance over time and compare models at specific sites. Multi-model comparison projects as well as models themselves have largely been focused on temperate forests and similar biomes. Semiarid regions, on the other hand, are underrepresented in land surface and ecosystem modelling efforts, and yet will be disproportionately impacted by disturbances such as climate change due to their sensitivity to changes in the water balance. Benchmarking models at semiarid sites is an important step in assessing and improving models' suitability for predicting the impact of disturbance on semiarid ecosystems. In this study, several ecosystem models were compared at a semiarid grassland in southwestern Arizona using PEcAn, or the Predictive Ecosystem Analyzer, an open-source eco-informatics toolbox ideal for creating the repeatable model workflows necessary for benchmarking. Models included SIPNET, DALEC, JULES, ED2, GDAY, LPJ-GUESS, MAESPA, CLM, CABLE, and FATES. Comparison between model output and benchmarks such as net ecosystem exchange (NEE) tended to produce high root mean square error and low correlation coefficients, reflecting poor simulation of seasonality and the tendency for models to create much higher carbon sources than observed. These results indicate that ecosystem models do not currently adequately represent semiarid ecosystem processes.

  7. Thermodynamics, data estimation and performance assessment

    International Nuclear Information System (INIS)

    Grenthe, I.

    2002-01-01

    Performance assessment provides a narrative of a system and its development. One may use a literary metaphor; the procedure is like writing a novel where the 'chapters' are the various sub-systems and where both the 'plot' and the 'grammar' are based on scientific and other information, some hard facts and other more or less reliable guesses. I will begin with some general remarks on models, which may provide a useful starting point for what follows. - Models never provide complete descriptions of real systems; they are used to highlight certain aspects of them and to answer 'what-if' questions; - Modelling is an iterative process that provides guidance as to what are important phenomena and what is less relevant for the description of the system and its function; - It is necessary to distinguish between model uncertainties and parameter uncertainties; - It is often better to estimate a quantity for which no data are available than to exclude the particular process where it is needed. Thermodynamics provide not only numerical values for different chemical processes, but more important a theory framework that can be used for the estimation of data. I will not discuss activity coefficient corrections of thermodynamic data, an important area that has already been addressed by Professor Fanghaenel. In the following overview I will be using examples of estimations of different kinds to illustrate what can be accomplished using thermodynamics in combination with chemical theories. (author)

  8. Assessing reservoir performance risk in CO2 storage projects

    International Nuclear Information System (INIS)

    Bowden, A.R.; Rigg, A.

    2005-01-01

    One of the main issues for researchers involved with geological storage of carbon dioxide (CO 2 ) has been the development of a proper methodology to assess and compare alternative CO 2 injection projects on the basis of risk. Consideration needs to be given to technical aspects, such as the risk of leakage and the effectiveness of the intended reservoir, as well as less tangible aspects such as the value and safety of geological storage of CO 2 , and potential impacts on the community and environment. The Geological Disposal of Carbon Dioxide (GEODISC), was a research program of the Australian Petroleum Cooperative Research Centre which identified 56 potential environmentally sustainable sites for CO 2 injection (ESSCIs) within Australia. Several studies were carried out, involving detailed evaluation of the suitability of 4 selected sites, including Dongara, Petrel, Gippsland and Carnarvon. The GEODISC program included a risk assessment research module which required a complete and quantified risk assessment of CO 2 injection as a storage option. Primary goals were to assess the risk of leakage, to assess the effectiveness of the intended reservoir, and to assess negative consequences to facilitate comparison of alternative sites. This paper discussed the background and risk assessment model. Key performance indicators (KPIs) were also developed to address the purpose of risk assessment. It was concluded that the RISQUE method is an appropriate approach and that potential injection projects can be measured against six KPIs including containment; effectiveness; self-funding potential; wider community benefits; community safety and community amenity. 6 refs., 3 tabs., 3 figs

  9. Assessment of Effective Prestressed Force of Nuclear Containment Building using SI Technique

    Energy Technology Data Exchange (ETDEWEB)

    Lee, H. P.; Jang, J. B.; Hwang, K. M.; Song, Y. C. [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

    2010-10-15

    Bonded tendons have been used in reactor buildings of heavy water reactors and the light water reactors of some nuclear power plants operating in Korea. The assessment of prestressed forces on those bonded tendons is becoming an important issue in assuring their continuous operation beyond their design life. In order to assess the effective prestressed force on the bonded tendon, indirect assessment techniques have been applying to the test beams which were manufactured on construction time. Therefore, this research mainly forced to establish the assessment methodology to measure directly the effective prestressed force on the bonded tendon of containment buildings using System Identification (SI) technique. To accomplish this purpose, simple SI method was proposed and adapted three dimensional finite element analysis of the 1:4 scale prestressed concrete containment vessel (PCCV) tested by Sandia National Laboratory in 2000

  10. Study of the performances of acoustic emission testing for glass fibre reinforced plastic pipes containing defects

    International Nuclear Information System (INIS)

    Villard, D.; Vidal, M.C.

    1995-08-01

    Glass fibre reinforced plastic pipes are more and more often used, in nuclear power plants, for building or replacement of water pipings classified 'nuclear safety'. Tests have been performed to evaluate the performances of acoustic emission testing for in service inspection of these components. The tests were focused on glass fibre reinforced polyester and vinyl-ester pipes, in as received conditions or containing impacts, and intentionally introduced defects. They have been carried out by CETIM, following the ASTM Standard E 1118 (code CARP), to a maximum pressure lever of 25 Bar The results show that the CARP procedure can be used for detection of defects and evaluation of their noxiousness towards internal pressure: most of the tubes containing low energy impacts could not be distinguished from tubes without defect; on the other hand the important noxiousness of lacks of impregnation of roving layer appeared clearly. Complementary tests have been performed on some tubes at a more important pressure lever, for which the damage of the tubes in enough to deteriorate there elastic properties. The results showed that CARP procedure give valuable informations on damage level. It would be interesting to evaluate acoustic emission on tubes containing realistic in-service degradations. (author). 11 refs., 15 figs., 6 tabs., 2 appends

  11. The assessment of containment codes by experiments simulating severe accident scenarios

    International Nuclear Information System (INIS)

    Karwat, H.

    1992-01-01

    Hitherto, a generally applicable validation matrix for codes simulating the containment behaviour under severe accident conditions did not exist. Past code applications have shown that most problems may be traced back to inaccurate thermalhydraulic parameters governing gas- or aerosol-distribution events. A provisional code-validation matrix is proposed, based on a careful selection of containment experiments performed during recent years in relevant test facilities under various operating conditions. The matrix focuses on the thermalhydraulic aspects of the containment behaviour after severe accidents as a first important step. It may be supplemented in the future by additional suitable tests

  12. Development of assessment technology for hydrogen burn and fission product behavior in containment

    International Nuclear Information System (INIS)

    Kim, S. B.; Kim, J. T.; Ha, K. S.; Hong, S. W.; Song, Y. M.; Park, J. H.; Cho, Y. R.; Kang, H. S.

    2012-04-01

    Analysis tools for hydrogen burn was established to resolve the hydrogen issues in containment. To validate CFX commercial CFD(computational fluid dynamics) code, the hydrogen combustion experiments such as FLAME and ENACEFF for reactor containment were analyzed. And OpenFOAM hydrogen combustion code was developed and validated. Experiments for the flame propagation characteristics in IRWST and the run-up-distance for DDT(Deflagration to detonation transition) were performed and analytical model was evaluated to evaluation of the performance of hydrogen mitigation system, that is, PAR(Passive auto-catalistic re-combiner) To improvement of the fission product modelling in containment, separate analysis module for Iodine behavior and its application tool of K-IODIP (Korea IODIne Package) were developed. PHEBUS FPT-3 analysis was performed to validate MELCOR code. And also the characteristics of fission product behaviors in Future Reactors(GEN-IV) were compared

  13. Fatigue Strength Assessment of Welded Mild Steel Joints Containing Bulk Imperfections

    Directory of Open Access Journals (Sweden)

    Martin Leitner

    2018-04-01

    Full Text Available This work investigates the effect of gas pores, as bulk imperfections, on the fatigue strength of welded mild steel joints. Two test series containing different butt joint geometries and weld process parameters are included in order to achieve two variable types of pore sizes. Based on the √area-parameter by Murakami, the test series can be grouped into imperfections exhibiting √area < 1000 µm and √area > 1000 µm. Fatigue tests at a load stress ratio of R = 0.1 are performed, which act as comparison for the subsequent fatigue estimation. To assess the fatigue resistance, the approaches by Murakami, De Kazinczy, and Mitchell are utilized, which highlight certain differences in the applicability depending on the imperfection size. It is found that, on one hand, Murakami’s approach is well suitable for both small and large gas pores depending on the applied model parameters. On the other hand, the fatigue concepts by De Kazinczy and Mitchell are preferably practicable for large defects with √area > 1000 µm. In addition, the method by Mitchell incorporates the stress concentration factor of the imperfection, which can be numerically computed considering the size, shape, and location of the gas pore, as presented in this paper.

  14. Thermal performance prediction of UO2 pellet partly containing 9%w tungsten network

    International Nuclear Information System (INIS)

    Suwardi

    2008-01-01

    Sintered UO 2 exhibits very stable in reactor core compared to UC, UN, U metal and its alloys. However, its thermal conductivity is very low (2.about.5 W/m K), that limits its performance. UO 2 pellet containing Tungsten network invented by Song improves considerably its conductivity. The paper reports an analysis of thermal performance for UO 2 pellet that contains partly or wholly with 9% b. of Tungsten. The tungsten network having a high melting point and excellent thermal conductivity is continuously formed around UO 2 grains. Since the presence of network decreases the amount of fissile material and the burn up of fissile material is higher in the near surface zone of pellet but high temperature zone that releases low conductivity fission gas to the gap located in inner part of pellet, the analysis has been done for different outer radial-portion of tungsten-free pellet. The analysis takes into account the correction factor for pellet conductivity related to both pore and temperature distribution and high burn up effect. The gap conductance has been considered invariable since decrease caused by wider gap size related to lower pellet expansion is compensated by increase caused by fewer of refractory fission gas released. The results (47 kw/m, 40% burnup) show temperature decrease in all of pellet position containing W network. Pellet containing 9%b. tungsten network lower consecutively its center line temperature from 1578 to 1406, 1292, 1231, 1192, 1111, and 1038 deg C for 0, 50, 67, 75, 80, 90, and 100 % portion of network. An 80 to 90 % portion of inner pellet containing tungsten network can be considered a best fuel design. This preliminary analysis is prospective and more realistic one is recommended. (author)

  15. Policy and Validity Prospects for Performance-Based Assessment.

    Science.gov (United States)

    Baker, Eva L.; And Others

    1994-01-01

    This article describes performance-based assessment as expounded by its proponents, comments on these conceptions, reviews evidence regarding the technical quality of performance-based assessment, and considers its validity under various policy options. (JDD)

  16. 25 CFR 20.404 - What information is contained in a social services assessment?

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false What information is contained in a social services assessment? 20.404 Section 20.404 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR HUMAN SERVICES FINANCIAL ASSISTANCE AND SOCIAL SERVICES PROGRAMS Services to Children, Elderly, and Families § 20.404 What...

  17. Human performance assessment: methods and measures

    International Nuclear Information System (INIS)

    Andresen, Gisle; Droeivoldsmo, Asgeir

    2000-10-01

    The Human Error Analysis Project (HEAP) was initiated in 1994. The aim of the project was to acquire insights on how and why cognitive errors occur when operators are engaged in problem solving in advanced integrated control rooms. Since human error had not been studied in the HAlden Man-Machine LABoratory (HAMMLAB) before, it was also necessary to carry out research in methodology. In retrospect, it is clear that much of the methodological work is relevant to human-machine research in general, and not only to research on human error. The purpose of this report is, therefore, to give practitioners and researchers an overview of the methodological parts of HEAP. The scope of the report is limited to methods used throughout the data acquisition process, i.e., data-collection methods, data-refinement methods, and measurement methods. The data-collection methods include various types of verbal protocols, simulator logs, questionnaires, and interviews. Data-refinement methods involve different applications of the Eyecon system, a flexible data-refinement tool, and small computer programs used for rearranging, reformatting, and aggregating raw-data. Measurement methods involve assessment of diagnostic behaviour, erroneous actions, complexity, task/system performance, situation awareness, and workload. The report concludes that the data-collection methods are generally both reliable and efficient. The data-refinement methods, however, should be easier to use in order to facilitate explorative analyses. Although the series of experiments provided an opportunity for measurement validation, there are still uncertainties connected to several measures, due to their reliability still being unknown. (Author). 58 refs.,7 tabs

  18. Performance Comparison of Containment PT analysis between CAP and CONTEMPT Code

    Energy Technology Data Exchange (ETDEWEB)

    Choo, Yeon Jun; Hong, Soon Joon; Hwang, Su Hyun; Kim, Min Ki; Lee, Byung Chul [FNC Tech., Seoul (Korea, Republic of); Ha, Sang Jun; Choi, Hoon [KHNP-CENTERAL RESEARCH INSTITUTE, Daejeon (Korea, Republic of)

    2013-10-15

    CAP, in the form that is linked with SPACE, computed the containment back-pressure during LOCA accident. In previous SAR (safety analysis report) report of Shin-Kori Units 3 and 4, the CONTEMPT series of codes(hereby referred to as just 'CONTEMPT') is used to evaluate the containment safety during the postulated loss-of-coolant accident (LOCA). In more detail, CONTEMPT-LT/028 was used to calculate the containment maximum PT, while CONTEMPT4/MOD5 to calculate the minimum PT. Actually, in minimum PT analysis, CONTEMPT4/MOD5, which provide back pressure condition of containment, was linked with RELAP5/MOD3.3 which calculate the amount of blowdown into containment. In this analysis, CONTEMPT4/MOD5 was modified based on KREM. CONTEMPT code was developed to predict the long term behavior of water-cooled nuclear reactor containment systems subjected to LOCA conditions. It calculates the time variation of compartment pressures, temperatures, mass and energy inventories, heat structure temperature distributions, and energy exchange with adjacent compartments, leakage on containment response. Models are provided for fan cooler and cooling spray as engineered safety systems. Any compartment may have both a liquid pool region and an air-vapor atmosphere region above the pool. Each region is assumed to have a uniform temperature, but the temperatures of the two regions may be different. As mentioned above, CONTEMP has the similar code features and it therefore is expected to show the similar analysis performance with CAP. In this study, the differences between CAP and two CONTEMPT code versions (CONTEMPT-LT/028 for maximum PT and CONTEMPT4/MOD5 for minimum PT) are, in detail, identified and the code performances were compared for the same problem. Code by code comparison was carried out to identify the difference of LOCA analysis between a series of COMTEMPT and CAP code. With regard to important factors that affect the transient behavior of compartment thermodynamic

  19. Performance Comparison of Containment PT analysis between CAP and CONTEMPT Code

    International Nuclear Information System (INIS)

    Choo, Yeon Jun; Hong, Soon Joon; Hwang, Su Hyun; Kim, Min Ki; Lee, Byung Chul; Ha, Sang Jun; Choi, Hoon

    2013-01-01

    CAP, in the form that is linked with SPACE, computed the containment back-pressure during LOCA accident. In previous SAR (safety analysis report) report of Shin-Kori Units 3 and 4, the CONTEMPT series of codes(hereby referred to as just 'CONTEMPT') is used to evaluate the containment safety during the postulated loss-of-coolant accident (LOCA). In more detail, CONTEMPT-LT/028 was used to calculate the containment maximum PT, while CONTEMPT4/MOD5 to calculate the minimum PT. Actually, in minimum PT analysis, CONTEMPT4/MOD5, which provide back pressure condition of containment, was linked with RELAP5/MOD3.3 which calculate the amount of blowdown into containment. In this analysis, CONTEMPT4/MOD5 was modified based on KREM. CONTEMPT code was developed to predict the long term behavior of water-cooled nuclear reactor containment systems subjected to LOCA conditions. It calculates the time variation of compartment pressures, temperatures, mass and energy inventories, heat structure temperature distributions, and energy exchange with adjacent compartments, leakage on containment response. Models are provided for fan cooler and cooling spray as engineered safety systems. Any compartment may have both a liquid pool region and an air-vapor atmosphere region above the pool. Each region is assumed to have a uniform temperature, but the temperatures of the two regions may be different. As mentioned above, CONTEMP has the similar code features and it therefore is expected to show the similar analysis performance with CAP. In this study, the differences between CAP and two CONTEMPT code versions (CONTEMPT-LT/028 for maximum PT and CONTEMPT4/MOD5 for minimum PT) are, in detail, identified and the code performances were compared for the same problem. Code by code comparison was carried out to identify the difference of LOCA analysis between a series of COMTEMPT and CAP code. With regard to important factors that affect the transient behavior of compartment thermodynamic state in

  20. Radiological performance assessment for the E-Area Vaults Disposal Facility. Appendices A through M

    Energy Technology Data Exchange (ETDEWEB)

    Cook, J.R.

    1994-04-15

    These document contains appendices A-M for the performance assessment. They are A: details of models and assumptions, B: computer codes, C: data tabulation, D: geochemical interactions, E: hydrogeology of the Savannah River Site, F: software QA plans, G: completeness review guide, H: performance assessment peer review panel recommendations, I: suspect soil performance analysis, J: sensitivity/uncertainty analysis, K: vault degradation study, L: description of naval reactor waste disposal, M: porflow input file. (GHH)

  1. Radiological performance assessment for the E-Area Vaults Disposal Facility

    International Nuclear Information System (INIS)

    Cook, J.R.

    1994-01-01

    These document contains appendices A-M for the performance assessment. They are A: details of models and assumptions, B: computer codes, C: data tabulation, D: geochemical interactions, E: hydrogeology of the Savannah River Site, F: software QA plans, G: completeness review guide, H: performance assessment peer review panel recommendations, I: suspect soil performance analysis, J: sensitivity/uncertainty analysis, K: vault degradation study, L: description of naval reactor waste disposal, M: porflow input file

  2. Assessment of aggregates- cement paste border in concretes containing silica fume and fly ash

    Directory of Open Access Journals (Sweden)

    Ali Sademomtazi

    2017-12-01

    Full Text Available The bond between aggregate and cement paste, called the interfacial transition zone (ITZ is an important parameter that effect on the mechanical properties and durability of concrete. Transition zone microstructure and porosity (pores of cement paste or concrete are affected by the type and properties of materials used which evaluated in this research. On the other hand, the use of efficient, low-cost and reliable method is particularly important for evaluating of concrete performance against the chloride ion penetration and its relationships with transition zone as a suitable index to assess the durability. So far, various methods to approach the electrical Indices are presented. In this research, the effect of pozzolanic materials fly ash (10%, 20% and 30% and silica fume (5% and 10% as substitute of cement by weight in binary and ternary mixtures on the fresh and hardened concrete properties were investigated. To determine mechanical properties, the compressive strength, splitting tensile strength and modulus of elasticity tests were performed. Also, water penetration depth, porosity, water sorptivity, specific electrical resistivity, rapid chloride penetration test (RCPT and rapid chloride migration test (RCMT tests were applied to evaluate concrete durability. To examine the border of aggregate and cement paste morphology of concrete specimens, scanning electron microscope images (SEM was used. The fresh concrete results showed that the presence of silica fume in binary and ternary mixtures reduced workability and air content but fly ash increased them. Adding silica fume to mixtures of containing flay ash while increasing mechanical strength reduced the porosity and pores to 18%. The presence of pozzolanic materials in addition to increasing bond quality and uniformity of aggregate-cement matrix border a considerably positive effect on the transport properties of concrete.

  3. Influence of the distribution of non-condensables on passive containment condenser performance in PANDA

    International Nuclear Information System (INIS)

    Bandurski, Th.; Huggenberger, M.; Dreier, J.; Aubert, C.; Putz, F.; Gamble, R.E.; Yadigaroglu, G.

    2001-01-01

    Recently passive cooling systems have been designed for the long-term decay heat removal from the containment of Advanced Light Water Reactors. In particular, the long-term LOCA response of the Passive Containment Cooling System (PCCS) for the General Electric European Simplified Boiling Water Reactor (ESBWR) has been tested in the large-scale PANDA facility. The PANDA tests achieved the dual objectives of improving confidence in the performance of the passive heat removal mechanisms underlying the design of the system, and extending the database available for containment analysis code qualification. The tests conducted subject the PCCS to a variety of conditions representing design-basis and beyond-design-basis accident conditions. These include operation in the presence of both heavier and lighter than steam non-condensable gases, as well as a variety of asymmetric and challenging start-up conditions. The present paper addresses the transient distribution of non-condensables in PANDA, and their effect on (passive) condenser performance. (author)

  4. Influence of the distribution of noncondensibles on passive containment condenser performance in PANDA

    International Nuclear Information System (INIS)

    Bandurski, T.; Huggenberger, M.; Dreier, J.; Aubert, C.; Putz, F.; Gamble, R.E.; Yadigaroglu, G.

    2001-01-01

    Recently, passive cooling systems have been designed for the long-term decay heat removal from the containment of Advanced Light Water Reactors. In particular, the long-term LOCA response of the Passive Containment Cooling System (PCCS) for the General Electric European Simplified Boiling Water Reactor (ESBWR) has been tested in the large scale PANDA facility. The PANDA tests achieved the dual objective of improving confidence in the performance of the passive heat removal mechanisms underlying the design of the tested systems and extending the data base available for containment analysis code qualification. The tests conducted subject the PCCS to a variety of conditions representing design-basis and beyond-design-basis accident conditions. These include operation in the presence of both heavier and lighter than steam noncondensible gases as well as a variety of asymmetric conditions and challenging start-up conditions. The present paper addresses the transient distribution of noncondensibles and their effect on the passive condenser performance in PANDA

  5. Influence of the distribution of non-condensables on passive containment condenser performance in PANDA

    Energy Technology Data Exchange (ETDEWEB)

    Bandurski, Th.; Huggenberger, M.; Dreier, J.; Aubert, C.; Putz, F.; Gamble, R.E.; Yadigaroglu, G

    2001-03-01

    Recently passive cooling systems have been designed for the long-term decay heat removal from the containment of Advanced Light Water Reactors. In particular, the long-term LOCA response of the Passive Containment Cooling System (PCCS) for the General Electric European Simplified Boiling Water Reactor (ESBWR) has been tested in the large-scale PANDA facility. The PANDA tests achieved the dual objectives of improving confidence in the performance of the passive heat removal mechanisms underlying the design of the system, and extending the database available for containment analysis code qualification. The tests conducted subject the PCCS to a variety of conditions representing design-basis and beyond-design-basis accident conditions. These include operation in the presence of both heavier and lighter than steam non-condensable gases, as well as a variety of asymmetric and challenging start-up conditions. The present paper addresses the transient distribution of non-condensables in PANDA, and their effect on (passive) condenser performance. (author)

  6. Influence of the distribution of noncondensibles on passive containment condenser performance in PANDA

    Energy Technology Data Exchange (ETDEWEB)

    Bandurski, T. E-mail: thomas.bandurski@psi.ch; Huggenberger, M.; Dreier, J.; Aubert, C.; Putz, F.; Gamble, R.E. E-mail: robert.gamble@gene.ge.com; Yadigaroglu, G. E-mail: yadigaroglu@iet.mavt.ethz.ch

    2001-02-01

    Recently, passive cooling systems have been designed for the long-term decay heat removal from the containment of Advanced Light Water Reactors. In particular, the long-term LOCA response of the Passive Containment Cooling System (PCCS) for the General Electric European Simplified Boiling Water Reactor (ESBWR) has been tested in the large scale PANDA facility. The PANDA tests achieved the dual objective of improving confidence in the performance of the passive heat removal mechanisms underlying the design of the tested systems and extending the data base available for containment analysis code qualification. The tests conducted subject the PCCS to a variety of conditions representing design-basis and beyond-design-basis accident conditions. These include operation in the presence of both heavier and lighter than steam noncondensible gases as well as a variety of asymmetric conditions and challenging start-up conditions. The present paper addresses the transient distribution of noncondensibles and their effect on the passive condenser performance in PANDA.

  7. Total cross-sections assessment of neutron reaction with stainless steel SUS-310 contained in various nuclear data files

    International Nuclear Information System (INIS)

    Suwoto

    2002-01-01

    The integral testing of neutron cross-sections for Stainless Steel SUS-310 contained in various nuclear data files have been performed. The shielding benchmark calculations for Stainless Steel SUS-310 has been analysed through ORNL-Broomstick Experiment calculation which performed by MAERKER, R.E. at ORNL - USA ( 1) . Assessment with JENDL-3.1, JENDL-3.2, ENDF/B-IV, ENDF/B-VI nuclear data files and data from GEEL have also been carried out. The overall calculation results SUS-310 show in a good agreement with the experimental data, although, underestimate results appear below 3 MeV for all nuclear data files. These underestimation tendencies clearly caused by presented of iron nuclide which more than half in Stainless Steel compound. The total neutron cross-sections of iron nuclide contained in various nuclear data files relatively lower on that energy ranges

  8. Teachers' Views on Performance-Based Assessments.

    Science.gov (United States)

    King, Bruce

    1991-01-01

    Provides personal perspectives from teachers about the prospects and problems illuminated by Stanford University's Teacher Assessment Project. Teacher remarks address the portfolio development process, assessment centers, implications for national board certification for teachers, personal thoughts and perspectives on teaching, and the future of…

  9. Energy performance assessment in urban planning competitions

    International Nuclear Information System (INIS)

    Eicker, Ursula; Monien, Dirk; Duminil, Éric; Nouvel, Romain

    2015-01-01

    Highlights: • Quantification of energy efficiency in urban planning. • Analysis based on 3D (city) model. • Impact evaluation of urban form on energy demand, supply and building costs. • Primary energy balance with and without inclusion of shadowing effects. - Abstract: Many cities today are committed to increase the energy efficiency of buildings and the fraction of renewables especially in new urban developments. However, quantitative data on building energy performance as a function of urban density, building compactness and orientation, building use and supply options are rarely available during the design of new cities or early scenario analysis for existing city quarters, making it difficult for cities to effectively evaluate which concepts work today and in the future. The paper proposes a methodology to assess the energy demand and supply options as a function of the availability of geometry, building standard and use data. An automated procedure was implemented to identify each building’s geometry and volume and transfer the information to a simulation tool, which then calculates heating demand and solar energy generation on roofs and facades. The simulation includes shading calculations for each segment of the façades and roofs and thus allows a very detailed quantification of the building energy demand. By applying the methodology to a case study city quarter designed in an urban competition in Munich, it could be shown how the urban design influences the energy demand of the quarter and which fractions of renewable energy can be integrated into the roofs. While the building insulation standard and use are the is most important criteria for building energy efficiency (with an impact of more than a factor 2), the exact geometrical form, compactness and urban shading effects influences the energy demand by 10–20%. On the other hand, the detailed roof geometry and orientation influences the possible solar coverage of electricity or thermal

  10. High nitrogen-containing cotton derived 3D porous carbon frameworks for high-performance supercapacitors

    Science.gov (United States)

    Fan, Li-Zhen; Chen, Tian-Tian; Song, Wei-Li; Li, Xiaogang; Zhang, Shichao

    2015-10-01

    Supercapacitors fabricated by 3D porous carbon frameworks, such as graphene- and carbon nanotube (CNT)-based aerogels, have been highly attractive due to their various advantages. However, their high cost along with insufficient yield has inhibited their large-scale applications. Here we have demonstrated a facile and easily scalable approach for large-scale preparing novel 3D nitrogen-containing porous carbon frameworks using ultralow-cost commercial cotton. Electrochemical performance suggests that the optimal nitrogen-containing cotton-derived carbon frameworks with a high nitrogen content (12.1 mol%) along with low surface area 285 m2 g-1 present high specific capacities of the 308 and 200 F g-1 in KOH electrolyte at current densities of 0.1 and 10 A g-1, respectively, with very limited capacitance loss upon 10,000 cycles in both aqueous and gel electrolytes. Moreover, the electrode exhibits the highest capacitance up to 220 F g-1 at 0.1 A g-1 and excellent flexibility (with negligible capacitance loss under different bending angles) in the polyvinyl alcohol/KOH gel electrolyte. The observed excellent performance competes well with that found in the electrodes of similar 3D frameworks formed by graphene or CNTs. Therefore, the ultralow-cost and simply strategy here demonstrates great potential for scalable producing high-performance carbon-based supercapacitors in the industry.

  11. High nitrogen-containing cotton derived 3D porous carbon frameworks for high-performance supercapacitors

    Science.gov (United States)

    Fan, Li-Zhen; Chen, Tian-Tian; Song, Wei-Li; Li, Xiaogang; Zhang, Shichao

    2015-01-01

    Supercapacitors fabricated by 3D porous carbon frameworks, such as graphene- and carbon nanotube (CNT)-based aerogels, have been highly attractive due to their various advantages. However, their high cost along with insufficient yield has inhibited their large-scale applications. Here we have demonstrated a facile and easily scalable approach for large-scale preparing novel 3D nitrogen-containing porous carbon frameworks using ultralow-cost commercial cotton. Electrochemical performance suggests that the optimal nitrogen-containing cotton-derived carbon frameworks with a high nitrogen content (12.1 mol%) along with low surface area 285 m2 g−1 present high specific capacities of the 308 and 200 F g−1 in KOH electrolyte at current densities of 0.1 and 10 A g−1, respectively, with very limited capacitance loss upon 10,000 cycles in both aqueous and gel electrolytes. Moreover, the electrode exhibits the highest capacitance up to 220 F g−1 at 0.1 A g−1 and excellent flexibility (with negligible capacitance loss under different bending angles) in the polyvinyl alcohol/KOH gel electrolyte. The observed excellent performance competes well with that found in the electrodes of similar 3D frameworks formed by graphene or CNTs. Therefore, the ultralow-cost and simply strategy here demonstrates great potential for scalable producing high-performance carbon-based supercapacitors in the industry. PMID:26472144

  12. Beginning science teachers' performances: Assessment in times of reform

    Science.gov (United States)

    Budzinsky, Fie K.

    2000-10-01

    The current reform in science education and the research on effective teaching and student learning have reinforced the importance of teacher competency. To better measure performances in the teaching of science, performance assessment has been added to Connecticut's licensure process for beginning science teachers. Teaching portfolios are used to document teaching and learning over time. Portfolios, however, are not without problems. One of the major concerns with the portfolio assessment process is its subjectivity. Assessors may not have opportunities to ask clarifying or follow-up questions to enhance the interpretation of a teacher's performance. In addition, portfolios often contain components based on self-documentation, which are subjective. Furthermore, the use of portfolios raises test equity issues. These concerns present challenges for persons in charge of establishing the validity of a portfolio-based licensure process. In high-stakes decision processes, such as teaching licensure, the validity of the assessment instruments must be studied. The primary purpose of this study was to explore the criterion-related validity of the Connecticut State Department of Education's Beginning Science Teaching Portfolio by comparing the interpretations of performances from science teaching portfolios to those derived from another assessment method, the Expert Science Teaching Educational and Evaluation Model, (ESTEEM). The analysis of correlations between the Beginning Science Teaching Portfolio and ESTEEM instrument scores was the primary method for establishing support for validity. The results indicated moderate correlations between all Beginning Science Teaching Portfolio and ESTEEM category and total variables. Multiple regression was used to examine whether differences existed in beginning science teachers' performances based on gender, poverty group, school level, and science discipline taught. None of these variables significantly contributed to the

  13. Sorption data base for performance assessment of radwaste repository

    International Nuclear Information System (INIS)

    Cho, Y.H.; Jung, J.; Lee, J.K.; Hahn, P.S.

    2001-01-01

    Sorption data base (SDB) provides readily available data for the performance assessment of radwaste repository when site-specific data are not available and/or more reference data are needed. The software developed in the Korea Atomic Energy Research Institute (KAERI), SDB-21C, is a graphic user interface (GUI) program that provides efficient and user friendly tools for evaluating the large amount of sorption data. The data base of distribution coefficients compiled in the program contains about 11,000 Nuclear Energy Agency (NEA) data and 2,000 KAERI data up to now while the addition of new data is under progress. Furthermore, the parametric model and its compiled data sets are also included in SDB-21C. (author)

  14. Problems of heat transfer within the containing vessel of high performance LMFBR spent fuel shipping casks

    International Nuclear Information System (INIS)

    Pope, R.B.; Gartling, D.K.; Schimmel, W.P. Jr.; Larson, D.W.

    1976-01-01

    A preliminary assessment of heat transfer problems internal to a LMFBR spent fuel shipping cask is reported. The assessment is based upon previous results obtained in full-scale, electrically heated mockups of an LMFBR assembly located in a containing pipe, and also upon analytical and empirical studies presented in this paper. It is shown that a liquid coolant will be required to adequately distribute the decay heat of short-cooled assemblies from the fuel region to the containing cask structure. Liquid sodium apparently provides the best heat transfer, and sufficient data are available to adequately model the heat transfer processes involved. Dowtherm A is the most efficient organic evaluated to date and presented in the open literature. Since the organic materials have high Prandtl and usually high Rayleigh numbers, natural convection is the predominant mode of heat transfer. It is shown that a more comprehensive understanding of the convective processes will be required before heat transfer with an organic coolant can be adequately modeled. However, in view of systems considerations, Dowtherm A should be further considered as an alternative to sodium for use as a LMFBR spent fuel shipping cask coolant

  15. Market Assessment and Product Evaluation of Probiotic Containing Dietary Supplements Available in Bangladesh Market

    Directory of Open Access Journals (Sweden)

    Anjuman Ara Begum

    2015-01-01

    Full Text Available Probiotics containing food supplements available in Bangladesh market were identified and collected for assessment. To assess their label claim, they were resuspended into sterile distilled water. Then, series dilutions of each sample solution were prepared and immediately plated out, in duplicate, into De Man Rogosa Sharpe (MRS agar. These plates were then incubated at 37°C for 48 hours and colonies were counted. Viable cell numbers stated on the labels were compared with actual viable cell numbers. To assess the viability of the probiotics included in the products, probiotic strains were isolated from each of the four products and screened for inhibitory activity against six indicator strains. It was surprisingly found that although the viable cell numbers of all supplements were three to four log cycles lower than label claim of the products, however, this problem did not affect the inhibitory activity of the probiotic strains against indicator strains according to in vitro assessment. Legislation and regulation regarding prebiotic-probiotic containing products should be built up in Bangladesh to ensure quality products supply to the consumers. Moreover, manufacturers of probiotic containing products should take the responsibility for providing the consumer with scientifically and legally correct information.

  16. Effects of Consuming a Low Dose of Alcohol with Mixers Containing Carbohydrate or Artificial Sweetener on Simulated Driving Performance

    Directory of Open Access Journals (Sweden)

    Bryce Brickley

    2018-03-01

    Full Text Available The Australian National Drug and Alcohol Research Centre (NDARC devised gender-based drinking recommendations to ensure blood or equivalized breath alcohol concentrations (BrAC remain <0.050%. However, these may be inappropriate for individuals consuming alcohol without carbohydrate (CHO, which results in higher BrACs. This study investigated the effects of ingesting alcohol with and without CHO on BrACs and simulated driving performance. Thirty-two participants (16 males; age: 23 ± 6 years completed two randomized single-blinded trials. Participants performed a baseline drive (Drive 1, then an experimental drive (Drive 2, following alcohol consumption (males: 20 g; females: 10 g. Alcoholic beverages contained either 25 g sucrose or aspartame (AS. Driving performance was assessed using lateral control (standard deviation of lane position [SDLP] and number of lane departures and risk-taking (number of overtaking maneuvers and maximum overtaking speed. BrAC and subjective ratings (e.g., intoxication were also assessed. BrAC was significantly lower as Drive 2 commenced with CHO compared to AS (0.022 ± 0.008% vs. 0.030 ± 0.011%. Two males provided BrACs >0.050% with AS. Neither beverage influenced changes to simulated driving performance. Ingesting alcohol in quantities advised by the NDARC results in no detectable simulated driving impairment. However, the likelihood of exceeding the legal drink-driving BrAC is increased when alcohol is consumed with artificially-sweetened mixers.

  17. Performance of japanese quails fed feeds containing different corn and limestone particle sizes

    OpenAIRE

    Berto,DA; Garcia,EA; Móri,C; Faitarone,ABG; Pelícia,K; Molino,AB

    2007-01-01

    This study aimed at evaluating performance and egg quality of Japanese quails fed feeds containing different corn and limestone particle sizes. A total number of 648 birds in the peak of production was distributed in a random complete block experimental design, using a 2x3 factorial arrangement (2 corn particle sizes and 3 limestone particle sizes). Birds were designated to one of two blocks, with six replicates of 18 birds each. Mean geometric diameter (MGD) values used were 0.617mm and 0.72...

  18. High-performance electrically conductive silver paste prepared by silver-containing precursor

    Energy Technology Data Exchange (ETDEWEB)

    Liu, Jianguo; Cao, Yu; Li, Xiangyou; Wang, Xiaoye; Zeng, Xiaoyan [Huazhong University of Science and Technology, Wuhan National Laboratory for Optoelectronics, College of Optoelectronics Science and Engineering, Wuhan (China)

    2010-09-15

    A high-performance electrically conductive silver paste with no solid particles before drying and/or sintering is developed, in which silver-containing precursor is employed as conductive functional phase. Thermogravimetry analysis, volume electrical resistivity tests and sintering experiments show that the paste with about 14 wt.% silver pristine content is able to achieve the volume electrical resistivity of (2-3) x 10{sup -5} {omega} cm after it is sintered at 220 C. A micro-pen direct-writing process indicates that it is very suitable for the fabrication of high-resolution (25 {mu}m) and high-integration devices and apparatus. (orig.)

  19. Development and Performance Assessment of the High-Performance Shrinkage Reducing Agent for Concrete

    Directory of Open Access Journals (Sweden)

    Hyung Sub Han

    2016-01-01

    Full Text Available To develop a high-performance shrinkage reducing agent, this study investigated several shrinkage reducing materials and supplements for those materials. Fluidity and air content were satisfactory for the various shrinkage reducing materials. The decrease in viscosity was the lowest for glycol-based materials. The decrease in drying shrinkage was most prominent for mixtures containing glycol-based materials. In particular, mixtures containing G2 achieved a 40% decrease in the amount of drying shrinkage. Most shrinkage reducing materials had weaker level of compressive strength than that of the plain mixture. When 3% triethanolamine was used for early strength improvement, the strength was enhanced by 158% compared to that of the plain mixture on day 1; enhancement values were 135% on day 7 and 113% on day 28. To assess the performance of the developed high-performance shrinkage reducing agent and to determine the optimal amount, 2.0% shrinkage reducing agent was set as 40% of the value of the plain mixture. While the effect was more prominent at higher amounts, to prevent deterioration of the compressive strength and the other physical properties, the recommended amount is less than 2.0%.

  20. Performance Assessment Strategy Plan for the Geologic Repository Program

    International Nuclear Information System (INIS)

    1990-01-01

    Performance assessment is a major constituent of the program being conducted by the US Department of Energy (DOE) to develop a geologic repository. Performance assessment is the set of activities needed for quantitative evaluations to assess compliance with the performance requirements in the regulations for a geologic repository and to support the development of the repository. The strategy for these evaluations has been documented in the Performance Assessment Strategy Plan (DOE, 1989). The implementation of the performance assessment strategy is defined in this document. This paper discusses the scope and objectives of the implementation plan, the relationship of the plan to other program plans, summarizes the performance assessment areas and the integrated strategy of the performance assessment program. 1 fig., 3 tabs

  1. Assessment of the Internal Pressure Fragility of the Hanul NPP Units 3 and 4 Containment Building Using a Nonlinear Finite Element Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyung Kui; Hahm, Dea Gi; Choi, In Kil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    The sensitivity of the concrete strength is relatively higher compared to that of the steel strength. According to changes in the structure of the material, about 6-10% ultimate internal pressure differences occurred. Thirty sets of an FE model considering the material uncertainty of concrete and steel were composed for the internal pressure fragility assessment. From the internal pressure fragility assessment of the target containment building, the median capacity of liner leakage is estimated to be 116 psi. As can be seen from the Fukushima nuclear power plant accident, the containment building is the final protecting shield to prevent radiation leakage. Thus, a structural soundness evaluation for the containment pressure loads owing to a severe accident is very important. Recently, a probabilistic safety assessment has been commonly used to take into account the possible factors of uncertainty in a structural system. An assessment of the internal pressure fragility of the CANDU type containment buildings considering the correlation of structural material variables, and an assessment of the internal pressure fragility of the CANDU type containment buildings using a nonlinear finite element analysis, were also performed. However, for PWR type containment buildings, a fragility assessment has not been performed yet using a nonlinear finite element model (FEM) analysis. In this study, for the Hanul NPP units 3 and 4 containment building, the internal pressure fragility assessment was established using an FEM analysis. To do this, a three-dimensional finite element model, material property values, and a sensitive analysis were developed. A nonlinear finite element analysis of the Hanul NPP units 3 and 4 containment building was performed for a material sensitivity analysis and internal pressure fragility assessment.

  2. Assessment of the Internal Pressure Fragility of the Hanul NPP Units 3 and 4 Containment Building Using a Nonlinear Finite Element Analysis

    International Nuclear Information System (INIS)

    Park, Hyung Kui; Hahm, Dea Gi; Choi, In Kil

    2013-01-01

    The sensitivity of the concrete strength is relatively higher compared to that of the steel strength. According to changes in the structure of the material, about 6-10% ultimate internal pressure differences occurred. Thirty sets of an FE model considering the material uncertainty of concrete and steel were composed for the internal pressure fragility assessment. From the internal pressure fragility assessment of the target containment building, the median capacity of liner leakage is estimated to be 116 psi. As can be seen from the Fukushima nuclear power plant accident, the containment building is the final protecting shield to prevent radiation leakage. Thus, a structural soundness evaluation for the containment pressure loads owing to a severe accident is very important. Recently, a probabilistic safety assessment has been commonly used to take into account the possible factors of uncertainty in a structural system. An assessment of the internal pressure fragility of the CANDU type containment buildings considering the correlation of structural material variables, and an assessment of the internal pressure fragility of the CANDU type containment buildings using a nonlinear finite element analysis, were also performed. However, for PWR type containment buildings, a fragility assessment has not been performed yet using a nonlinear finite element model (FEM) analysis. In this study, for the Hanul NPP units 3 and 4 containment building, the internal pressure fragility assessment was established using an FEM analysis. To do this, a three-dimensional finite element model, material property values, and a sensitive analysis were developed. A nonlinear finite element analysis of the Hanul NPP units 3 and 4 containment building was performed for a material sensitivity analysis and internal pressure fragility assessment

  3. Identification of long-term containment/stabilization technology performance issues

    International Nuclear Information System (INIS)

    Matthern, G.E.; Nickelson, D.F.

    1997-01-01

    U.S. Department of Energy (DOE) faces a somewhat unique challenge when addressing in situ remedial alternatives that leave long-lived radionuclides and hazardous contaminants onsite. These contaminants will remain a potential hazard for thousands of years. However, the risks, costs, and uncertainties associated with removal and offsite disposal are leading many sites to select in situ disposal alternatives. Improvements in containment, stabilization, and monitoring technologies will enhance the viability of such alternatives for implementation. DOE's Office of Science and Technology sponsored a two day workshop designed to investigate issues associated with the long-term in situ stabilization and containment of buried, long-lived hazardous and radioactive contaminants. The workshop facilitated communication among end users representing most sites within the DOE, regulators, and technologists to define long-term performance issues for in situ stabilization and containment alternatives. Participants were divided into groups to identify issues and a strategy to address priority issues. This paper presents the results of the working groups and summarizes the conclusions. A common issue identified by the work groups is communication. Effective communication between technologists, risk assessors, end users, regulators, and other stakeholders would contribute greatly to resolution of both technical and programmatic issues

  4. Effect of Ce on performance and physicochemical properties of Pt-containing automotive emission control catalysts

    International Nuclear Information System (INIS)

    Nunan, J.G.; Silver, R.G.; Bradley, S.A.

    1992-01-01

    Present-day automotive emission control catalysts contain noble metals such as Pt, Pd and Rh all on an alumina support with a variety of promoters. Ce is one of the most important promoters. In this paper, the interaction between Pt and Ce is studied using TPR and STEM on a variety of catalysts. The degree of Pt/Ce interaction is increased by decreasing CeO 2 crystallite size, and to a lesser extent by increasing CeO 2 loading. Direct Pt/Ce interaction leads to a synergistic reduction of both Pt and surface Ce. This reduction qualitatively correlates with catalyst performance after activation in a reducing gas. It is proposed that this synergistic reduction of Pt and Ce is associated with observed improvements in catalyst performance using a non-oscillating exhaust gas

  5. Structure, conduct and performance paradigm in assessing travel agency performances

    Directory of Open Access Journals (Sweden)

    Stănciulescu Gabriela Cecilia

    2017-07-01

    Full Text Available The purpose of this paper is to present and exemplify traditional and neoclassical approaches to market structure and tourism firm performance analysis. The paper tackles some of the industrial economic thinking trends which were meant to fill the gaps left by the traditional approaches. Two approaches stand out from among the industrial economic trends: SCP paradigm and game theory. The results show that the strategy tourism operators prefer is to practise high prices; however there is no certainty that the competitors would adhere to such an idea at the beginning or during the season.

  6. Risk assessment of genotoxic and carcinogenic alkenylbenzenes in botanical containing products present on the Chinese market.

    Science.gov (United States)

    Ning, Jia; Cui, XinYue; Kong, XiangNan; Tang, YiFei; Wulandari, Riana; Chen, Lu; Wesseling, Sebas; Rietjens, Ivonne M C M

    2018-03-15

    In the present study, a risk assessment of plant food supplements (PFS), traditional Chinese medicines (TCM) and herbal teas containing alkenylbenzenes was performed using the Margin of Exposure (MOE) approach. The levels of alkenylbenzenes in botanical preparations collected on the Chinese market were quantified and the combined estimated daily intake (EDI) was determined using dose additivity. The combined EDI values obtained assuming equal potency of all alkenylbenzenes detected in the PFS, TCM and herbal teas were 0.3 to 14.3, 0.05 to 539.4 and 0.04 to 42.5 μg/kg bw/day, respectively. Calculating combined EDI values taking into account the toxic equivalency (TEQ) approach, the values for PFS, TCM and herbal teas were 0.3 to 7.7, 0.05 to 278.0 and 0.02 to 16.5 μg estragole equivalents/kg bw/day, respectively. The MOE values resulting from consumption of these PFS, TCM and one cup of herbal tea per day during life-time were generally lower than 10 000, suggesting a potential priority for risk management. For short-term exposure such as two weeks consumption, applying Haber's rule, only one TCM 6 () still had an MOE value below 10 000. It is concluded that selected consumption of Chinese botanical preparations raise a concern because of exposure to alkenylbenzenes, especially when exposure is for longer periods of time. Copyright © 2018 The Authors. Published by Elsevier Ltd.. All rights reserved.

  7. Thermal Performance and Operation Limit of Heat Pipe Containing Neutron Absorber

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyung Mo; Jeong, Yeong Shin; Kim, In Guk; Bang, In Choel [UNIST, Ulsan (Korea, Republic of)

    2015-05-15

    Recently, passive safety systems are under development to ensure the core cooling in accidents involving impossible depressurization such as station blackout (SBO). Hydraulic control rod drive mechanisms, passive auxiliary feedwater system (PAFS), Passive autocatalystic recombiner (PAR), and so on are types of passive safety systems to enhance the safety of nuclear power plants. Heat pipe is used in various engineering fields due to its advantages in terms of easy fabrication, high heat transfer rate, and passive heat transfer. Also, the various concepts associated with safety system and heat transfer using the heat pipe were developed in nuclear engineering field.. Thus, our group suggested the hybrid control rod which combines the functions of existing control rod and heat pipe. If there is significant temperature difference between active core and condenser, the hybrid control rod can shutdown the nuclear fission reaction and remove the decay heat from the core to ultimate heat sink. The unique characteristic of the hybrid control rod is the presence of neutron absorber inside the heat pipe. Many previous researchers studied the effect of parameters on the thermal performance of heat pipe. However, the effect of neutron absorber on the thermal performance of heat pipe has not been investigated. Thus, the annular heat pipe which contains B{sub 4}C pellet in the normal heat pipe was prepared and the thermal performance of the annular heat pipe was studied in this study. Hybrid control rod concept was developed as a passive safety system of nuclear power plant to ensure the safety of the reactor at accident condition. The hybrid control rod must contain the neutron absorber for the function as a control rod. So, the effect of neutron absorber on the thermal performance of heat pipe was experimentally investigated in this study. Temperature distributions at evaporator section of annular heat pipe were lower than normal heat pipe due to the larger volume occupied by

  8. In Situ Remediation Integrated Program, Evaluation and assessment of containment technology

    International Nuclear Information System (INIS)

    Gerber, M.A.; Fayer, M.J.

    1994-04-01

    The In Situ Remediation Integrated Program (ISRIP) was established by the US Department of Energy (DOE) to advance the state-of-the art of innovative in situ remediation technologies to the point of demonstration and to broaden the applicability of these technologies to the widely varying site remediation requirements throughout the DOE complex. This program complements similar ongoing integrated demonstration programs being conducted at several DOE sites. The ISRIP has been conducting baseline assessments on in situ technologies to support program planning. Pacific Northwest Laboratory conducted an assessment and evaluation of subsurface containment barrier technology in support of ISRIP's Containment Technology Subprogram. This report summarizes the results of that activity and provides a recommendation for priortizing areas in which additional research and development is needed to advance the technology to the point of demonstration in support of DOE's site restoration activities

  9. Mixed Waste Integrated Program: A technology assessment for mercury-containing mixed wastes

    International Nuclear Information System (INIS)

    Perona, J.J.; Brown, C.H.

    1993-03-01

    The treatment of mixed wastes must meet US Environmental Protection Agency (EPA) standards for chemically hazardous species and also must provide adequate control of the radioactive species. The US Department of Energy (DOE) Office of Technology Development established the Mixed Waste Integrated Program (MWIP) to develop mixed-waste treatment technology in support of the Mixed Low-Level Waste Program. Many DOE mixed-waste streams contain mercury. This report is an assessment of current state-of-the-art technologies for mercury separations from solids, liquids, and gases. A total of 19 technologies were assessed. This project is funded through the Chemical-Physical Technology Support Group of the MWIP

  10. Comparative Effect of Diets Containing Cooked and Roasted Soybeans on Growth Performances of Growing Finishing Pigs

    Directory of Open Access Journals (Sweden)

    F. Meffeja

    2003-01-01

    Full Text Available heat of soybeans on the performances of grower-finisher pigs. Twenty hybrid male piglets, averaging 15.4 ± 0.8 kg initial body weights were allotted to four experimental diets (five replicates per treatment based on soybean meal, cotton seed cake, cooked or roasted soybeans over a 98-day period. The rations containing the commonly used soybean meal and cotton seed cake were used as control diets. Results showed that the weight gain and feed conversion ratio obtained with diets containing roasted and cooked soybeans were significantly (P 0.05 compared to the soybean meal diet. Comparison of the two methods of heat treatment showed no significant difference on animal performances. Feed costs to produce one kilogram live weight, calculated as mean costs for both growth phases, although not significant between treatments, showed a slightly lower value in roasted soybean diets. These results show that the roasting method can be used with the same advantages as the cooking method.

  11. Seismic reliability assessment methodology for CANDU concrete containment structures-phase 11

    International Nuclear Information System (INIS)

    Hong, H.P.

    1996-07-01

    This study was undertaken to verify a set of load factors for reliability-based seismic evaluation of CANDU containment structures in Eastern Canada. Here, the new, site-specific, results of probabilistic seismic hazard assessment (response spectral velocity) were applied. It was found that the previously recommended load factors are relatively insensitive to the new seismic hazard information, and are adequate for a reliability-based seismic evaluation process. (author). 4 refs., 5 tabs., 9 figs

  12. Performance assessment strategy for low-level waste disposal sites

    International Nuclear Information System (INIS)

    Starmer, R.J.; Deering, L.G.; Weber, M.F.

    1988-01-01

    This paper describes US Nuclear Regulatory Commission (NRC) staff views on predicting the performance of low-level radioactive waste disposal facilities. Under the Atomic Energy Act, as amended, and the Low Level Radioactive Waste Policy Act, as amended, the NRC and Agreement States license land disposal of low-level radioactive waste (LLW) using the requirements in 10 CFR Part 61 or comparable state requirements. The purpose of this paper is to briefly describe regulatory requirements for performance assessment in low-level waste licensing, a strategy for performance assessments to support license applications, and NRC staff licensing evaluation of performance assessments. NRC's current activities in developing a performance assessment methodology will provide an overall systems modeling approach for assessing the performance of LLW disposal facilities. NRC staff will use the methodology to evaluate performance assessments conducted by applicants for LLW disposal facilities. The methodology will be made available to states and other interested parties

  13. Technical Basis for Assessing Uranium Bioremediation Performance

    International Nuclear Information System (INIS)

    PE Long; SB Yabusaki; PD Meyer; CJ Murray; AL N'Guessan

    2008-01-01

    In situ bioremediation of uranium holds significant promise for effective stabilization of U(VI) from groundwater at reduced cost compared to conventional pump and treat. This promise is unlikely to be realized unless researchers and practitioners successfully predict and demonstrate the long-term effectiveness of uranium bioremediation protocols. Field research to date has focused on both proof of principle and a mechanistic level of understanding. Current practice typically involves an engineering approach using proprietary amendments that focuses mainly on monitoring U(VI) concentration for a limited time period. Given the complexity of uranium biogeochemistry and uranium secondary minerals, and the lack of documented case studies, a systematic monitoring approach using multiple performance indicators is needed. This document provides an overview of uranium bioremediation, summarizes design considerations, and identifies and prioritizes field performance indicators for the application of uranium bioremediation. The performance indicators provided as part of this document are based on current biogeochemical understanding of uranium and will enable practitioners to monitor the performance of their system and make a strong case to clients, regulators, and the public that the future performance of the system can be assured and changes in performance addressed as needed. The performance indicators established by this document and the information gained by using these indicators do add to the cost of uranium bioremediation. However, they are vital to the long-term success of the application of uranium bioremediation and provide a significant assurance that regulatory goals will be met. The document also emphasizes the need for systematic development of key information from bench scale tests and pilot scales tests prior to full-scale implementation

  14. Technical Basis for Assessing Uranium Bioremediation Performance

    Energy Technology Data Exchange (ETDEWEB)

    PE Long; SB Yabusaki; PD Meyer; CJ Murray; AL N’Guessan

    2008-04-01

    In situ bioremediation of uranium holds significant promise for effective stabilization of U(VI) from groundwater at reduced cost compared to conventional pump and treat. This promise is unlikely to be realized unless researchers and practitioners successfully predict and demonstrate the long-term effectiveness of uranium bioremediation protocols. Field research to date has focused on both proof of principle and a mechanistic level of understanding. Current practice typically involves an engineering approach using proprietary amendments that focuses mainly on monitoring U(VI) concentration for a limited time period. Given the complexity of uranium biogeochemistry and uranium secondary minerals, and the lack of documented case studies, a systematic monitoring approach using multiple performance indicators is needed. This document provides an overview of uranium bioremediation, summarizes design considerations, and identifies and prioritizes field performance indicators for the application of uranium bioremediation. The performance indicators provided as part of this document are based on current biogeochemical understanding of uranium and will enable practitioners to monitor the performance of their system and make a strong case to clients, regulators, and the public that the future performance of the system can be assured and changes in performance addressed as needed. The performance indicators established by this document and the information gained by using these indicators do add to the cost of uranium bioremediation. However, they are vital to the long-term success of the application of uranium bioremediation and provide a significant assurance that regulatory goals will be met. The document also emphasizes the need for systematic development of key information from bench scale tests and pilot scales tests prior to full-scale implementation.

  15. Performance assessment for the class L-II disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    This draft radiological performance assessment (PA) for the proposed Class L-II Disposal Facility (CIIDF) on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the requirements of the US Department of Energy Order 5820.2A. This PA considers the disposal of low-level radioactive wastes (LLW) over the operating life of the facility and the long-term performance of the facility in providing protection to public health and the environment. The performance objectives contained in the order require that the facility be managed to accomplish the following: (1) Protect public health and safety in accordance with standards specified in environmental health orders and other DOE orders. (2) Ensure that external exposure to the waste and concentrations of radioactive material that may be released into surface water, groundwater, soil, plants, and animals results in an effective dose equivalent (EDE) that does not exceed 25 mrem/year to a member of the public. Releases to the atmosphere shall meet the requirements of 40 CFR Pt. 61. Reasonable effort should be made to maintain releases of radioactivity in effluents to the general environment as low as reasonably achievable. (1) Ensure that the committed EDEs received by individual who inadvertently may intrude into the facility after the loss of active institutional control (100 years) will not exceed 100 mrem/year for continuous exposure of 500 mrem for a single acute exposure. (4) Protect groundwater resources, consistent with federal, state, and local requirements.

  16. Monitoring the Long-Term Performance of Engineered Containment Systems: Role of Ecological Processes

    International Nuclear Information System (INIS)

    Traynham, B.; Clarke, J.H.; Burger, J.; Waugh, J.

    2009-01-01

    Engineered covers have been widely used to minimize water infiltration into landfills used by U. S. Department of Energy (DOE) for the disposal of radioactive and hazardous chemical waste. The degradation of engineered covers over time is a complex process that is influenced by site specific characteristics, the structure and dynamics of the indigenous plant community, and the interplay of physical and biological factors at contaminated sites. It is necessary to develop a rigorous method to evaluate long-term performance of covers and other engineered barriers with quantification of risk and uncertainty. Because many of the contaminants of concern are long-lived, this methodology must consider changes in the environmental setting (e.g., precipitation, temperature) and cover components for long time periods (>100 years). Current monitoring approaches focus solely on hydrologic properties of the cover system. Additionally, cover design guidelines, such as those from RCRA, are not performance based and do not consider long-term site-specific influences such as climate, vegetation, and soils. Fundamental ecological processes such as succession are not even factored into current models, yet they directly affect the integrity of landfill covers through biointrusion, erosion, and water balance. Therefore, it is useful to identify ecological parameters and processes most important to performance for prioritization of site characterization and long-term monitoring activities. This investigation into the role of ecological monitoring of isolation containment systems utilizes the software platform GoldSim to identify important parameters and processes for performance verification and monitoring. (authors)

  17. Caffeine-containing energy drink improves physical performance in female soccer players.

    Science.gov (United States)

    Lara, Beatriz; Gonzalez-Millán, Cristina; Salinero, Juan Jose; Abian-Vicen, Javier; Areces, Francisco; Barbero-Alvarez, Jose Carlos; Muñoz, Víctor; Portillo, Luis Javier; Gonzalez-Rave, Jose Maria; Del Coso, Juan

    2014-05-01

    There is little information about the effects of caffeine intake on female team-sport performance. The aim of this study was to investigate the effectiveness of a caffeine-containing energy drink to improve physical performance in female soccer players during a simulated game. A double-blind, placebo controlled and randomized experimental design was used in this investigation. In two different sessions, 18 women soccer players ingested 3 mg of caffeine/kg in the form of an energy drink or an identical drink with no caffeine content (placebo). After 60 min, they performed a countermovement jump (CMJ) and a 7 × 30 m sprint test followed by a simulated soccer match (2 × 40 min). Individual running distance and speed were measured using GPS devices. In comparison to the placebo drink, the ingestion of the caffeinated energy drink increased the CMJ height (26.6 ± 4.0 vs 27.4 ± 3.8 cm; P 18 km/h (161 ± 99 vs 216 ± 103 m; P caffeine/kg might be an effective ergogenic aid to improve physical performance in female soccer players.

  18. Performance assessment of Point Lepreau Generating Station

    Energy Technology Data Exchange (ETDEWEB)

    Alikhan, S [Point Lepreau Generating Station, Lepreau, NB (Canada)

    1991-04-01

    The Point Lepreau Generating Station, a 680 MWe CANDU unit, is located about 40 km southwest of the city of Saint John, New Brunswick, Canada. It was declared in-service on 1 February, 1983 and, since then, has demonstrated an average cross capacity factor of over 93% up to the end of 1990. This paper compared the performance of the station with other sister CANDU units and the Light Water Reactors world-wide using the following ten performance indicators, as applicable: - gross capacity factor; - fuel burn-up; - heavy water upkeep; - unplanned reactor trips while critical; - forced outage rate; - fuel handling performance; - derived emission of radioactive effluents to environment; - personnel radiation dose; - industrial safety; - low-level solid radioactive wastes. The paper examines various areas of station activities including management and organization, operations and maintenance, technical support, fuel handling and health physics in order to highlight some of the 'good practices' which are believed to have made a significant contribution towards achieving the demonstrated performance of Point Lepreau G.S. In addition, several areas of potential improvement are discussed in order to maintain and enhance, where practicable, the safety, reliability and economic performance of the station. In this context, a careful review of the operating experiences, both in-house and at other stations, and a judicious application of lessons learned plays a significant role. (author)

  19. Performance assessment of Point Lepreau Generating Station

    International Nuclear Information System (INIS)

    Alikhan, S.

    1991-01-01

    The Point Lepreau Generating Station, a 680 MWe CANDU unit, is located about 40 km southwest of the city of Saint John, New Brunswick, Canada. It was declared in-service on 1 February, 1983 and, since then, has demonstrated an average cross capacity factor of over 93% up to the end of 1990. This paper compared the performance of the station with other sister CANDU units and the Light Water Reactors world-wide using the following ten performance indicators, as applicable: - gross capacity factor; - fuel burn-up; - heavy water upkeep; - unplanned reactor trips while critical; - forced outage rate; - fuel handling performance; - derived emission of radioactive effluents to environment; - personnel radiation dose; - industrial safety; - low-level solid radioactive wastes. The paper examines various areas of station activities including management and organization, operations and maintenance, technical support, fuel handling and health physics in order to highlight some of the 'good practices' which are believed to have made a significant contribution towards achieving the demonstrated performance of Point Lepreau G.S. In addition, several areas of potential improvement are discussed in order to maintain and enhance, where practicable, the safety, reliability and economic performance of the station. In this context, a careful review of the operating experiences, both in-house and at other stations, and a judicious application of lessons learned plays a significant role. (author)

  20. PERFORMANCE ASSESSMENT IN OPERATING DRY PORTS

    Directory of Open Access Journals (Sweden)

    Ciortescu Cezar-Gabriel

    2010-12-01

    Full Text Available In this paper, an approach for recognizing and defining correct and operable performance will be presented with the purpose of evaluating the effectiveness and efficiency of processes in dry ports (inland intermodal hubs. The challenge in evaluating the possible improvements of the underlying processes lies in the special nature and the complex structure of dry ports. It is important to consider that all the processes are highly interconnected and that changes in parameters in one process also have an impact on parameters in other processes. Furthermore, the performance of dry ports, seen as the backbone of the system, has a significant impact on the overall performance of the whole transportation network.

  1. Effects of Time-Release Caffeine Containing Supplement on Metabolic Rate, Glycerol Concentration and Performance

    Directory of Open Access Journals (Sweden)

    Adam M. Gonzalez, Jay R. Hoffman, Adam J. Wells, Gerald T. Mangine, Jeremy R. Townsend, Adam R. Jajtner, Ran Wang, Amelia A. Miramonti, Gabriel J. Pruna, Michael B. LaMonica, Jonathan D. Bohner, Mattan W. Hoffman, Leonardo P. Oliveira, David H. Fukuda, Maren S. Fragala, Jeffrey R. Stout

    2015-06-01

    Full Text Available This study compared caffeine pharmacokinetics, glycerol concentrations, metabolic rate, and performance measures following ingestion of a time-release caffeine containing supplement (TR-CAF versus a regular caffeine capsule (CAF and a placebo (PL. Following a double-blind, placebo-controlled, randomized, cross-over design, ten males (25.9 ± 3.2 y who regularly consume caffeine ingested capsules containing either TR-CAF, CAF, or PL. Blood draws and performance measures occurred at every hour over an 8-hour period. Plasma caffeine concentrations were significantly greater (p < 0.05 in CAF compared to TR-CAF during hours 2-5 and significantly greater (p = 0.042 in TR-CAF compared to CAF at hour 8. There were no significant differences between trials in glycerol concentrations (p = 0.86 or metabolic measures (p = 0.17-0.91. Physical reaction time was significantly improved for CAF at hour 5 (p=0.01 compared to PL. Average upper body reaction time was significantly improved for CAF and TR-CAF during hours 1-4 (p = 0.04 and p = 0.01, respectively and over the 8-hour period (p = 0.04 and p = 0.001, respectively compared to PL. Average upper body reaction time was also significantly improved for TR-CAF compared to PL during hours 5-8 (p = 0.004. TR-CAF and CAF showed distinct pharmacokinetics yielding modest effects on reaction time, yet did not alter glycerol concentration, metabolic measures, or other performance measures.

  2. Irrigation performance assessment in Crimea, Ukraine

    NARCIS (Netherlands)

    Pavlov, S.S.; Roerink, G.J.; Hellegers, P.J.G.J.; Popovych, V.F.

    2006-01-01

    After the collapse of the Soviet Union the performance of irrigated agriculture decreased drastically in Ukraine, due to problems related to the transition from a centrally planned economy to a market economy. Before formulating recommendations on required actions to modify this problematic

  3. Using urbanization profiles to assess screening performance

    NARCIS (Netherlands)

    Boon, ME; Kok, LP

    The large Dutch data sets acquired as a result of population-based cervical smear screening programs can be further exploited to obtain an urbanization-weighted score to gain insight into the quality of the performance of the individual cytology laboratories. Based on the first four digits of the

  4. Assessing heat exchanger performance data using temperature ...

    African Journals Online (AJOL)

    In addition, any calculated performance acceptance criteria must also consider uncertainty and error in the experimental measurements of temperature and flow. However, most statistical methods are complex and not easily applied to heat exchangers such as those that serve the power plant industry where data are difficult ...

  5. Postulated accident conditions for air cleaning systems and radiological dose assessments for containment options

    International Nuclear Information System (INIS)

    Hilliard, R.K.; Postma, A.K.

    1975-01-01

    Ambient conditions and performance requirements for emergency air cleaning systems applicable to commercial LMFBR plants were studied. The focus of this study centered on aerosol removal under hypothetical core disruptive accident conditions. Effort completed includes a review of air cleaning systems related to LMFBR plants, selection of three reference containment system designs, postulation of the EACS design basis accident (EACS-DBA), analysis of thermal conditions resulting from the DBA, analysis of aerosol transport behavior following the DBA, and an estimate of bone dose at the site boundary for each of the reference plant designs. Reference plant concepts were a single containment system (e.g., FFTF), a double containment system (e.g., CRBRP with closed head compartment), and a containment-confinement design in which an inerted, sealed primary volume was located within a ventilated building whose exhaust was filtered. The reference design basis accident selected here involved release to the inner containment system of 1 percent of non-volatile solids and plutonium, 25 percent of core halogens, 25 percent of core volatile solids, 100 percent of core noble gases, 68 lbs of sodium vapor and 5000 lbs of liquid sodium. 13 references. (U.S.)

  6. Tajikistan - Public Expenditure and Financial Accountability Assessment : Performance Report

    OpenAIRE

    World Bank

    2007-01-01

    This assessment is based on work undertaken between October 2006 and May 2007. The summary assessment covers the following three areas: an integrated assessment of PFM performance based on the 28+3 PEFA indicators, an assessment of the impact of PFM weaknesses, and the prospects for reform planning and implementation. The main report consists of four sections: an introduction, the country ...

  7. In vitro antibacterial and cytotoxicity assessments of an orthodontic bonding agent containing benzalkonium chloride.

    Science.gov (United States)

    Saito, Kayo; Hayakawa, Tohru; Kawabata, Rihito; Meguro, Daijiro; Kasai, Kazutaka

    2009-03-01

    To assess the antibacterial activity and cytotoxicity of an orthodontic bonding material containing an antibacterial agent. Superbond C&B (4-methacryloxyethyl trimellitate anhydride/methyl methacrylate-tri-n-butyl borane [4-META/MMA-TBB]) resin was mixed with benzalkonium chloride (BAC) to obtain final BAC concentrations of 0.25%, 0.75%, 1.25%, 1.75%, 2.5%, and 5.0% (wt/ wt). Antibacterial activity against Streptococcus mutans and Streptococcus sobrinus was evaluated by soaking the BAC-resin in distilled water at 37 degrees C for periods of 30, 90, and 180 days. Antibacterial activity of the BAC-resin was measured by the disk diffusion method, and the inhibition zone around each sample was measured and recorded. For evaluation of cytotoxicity, BAC-resin samples were put into cell culture inserts placed above human gingival cells and were incubated at 37 degrees C for 1, 3, and 6 days. Cytotoxicity was assessed with a tetrazolium bromide reduction assay. The antibacterial activity of BAC-incorporated resin samples decreased significantly after immersion in water for 180 days, regardless of BAC concentration. The antibacterial activity of nonimmersed resin containing 0.25% or 1.75% BAC was comparable with that of 5.0% BAC-resin immersed for 180 days. In cytotoxicity tests, most cells died when exposed to resins containing 1.75%, 2.5%, and 5% BAC. No difference was observed between resins containing 0.25% and 0.75% BAC at 1, 3, and 6 days of culture. The addition of BAC to 4-META/MMA-TBB resin confers an antibacterial effect even after immersion in water, and 4-META/MMA-TBB resin containing 0.25% to 0.75% BAC has no significant cytotoxic effect.

  8. WIPP performance assessment: impacts of human intrusion

    International Nuclear Information System (INIS)

    Anderson, D.R.; Hunter, R.L.; Bertram-Howery, S.G.; Lappin, A.R.

    1989-01-01

    The Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico is a research and development facility that may become the USA's first and only mined geologic repository for transuranic waste. Human intrusion into the WIPP repository after closure has been shown by preliminary sensitivity analyses and calculations of consequences to be an important, and perhaps the most important, factor in long-term repository performance

  9. Cost performance assessment of in situ vitrification

    International Nuclear Information System (INIS)

    Showalter, W.E.; Letellier, B.C.; Booth, S.R.; Barnes-Smith, P.

    1992-01-01

    In situ vitrification (ISV) is a thermal treatment technology with promise for the destruction or immobilization of hazardous materials in contaminated soils. It has developed over the past decade to a level of maturity where meaningful cost effectiveness studies may be performed. The ISV process melts 4 to 25 m 2 of undisturbed soil to a maximum depth of 6 m into an obsidian-like glass waste form by applying electric current (3750 kill) between symmetrically spaced electrodes. Temperatures of approximately 2000 degree C drive off and destroy complex organics which are captured in an off-gas treatment system, while radio-nuclides are incorporated into the homogeneous glass monolith. A comparative life-cycle cost evaluation between mobile rotary kiln incineration and ISV was performed to quantitatively identify appropriate performance regimes and components of cost which are sensitive to the implementation of each technology. Predictions of melt times and power consumption were obtained from an ISV performance model over ranges of several parameters including electrode spacing, soil moisture, melt depth, electrical resistivity, and soil density. These data were coupled with manpower requirements, capitalization costs, and a melt placement optimization routine to allow interpolation over a wide variety of site characteristics. For the purpose of this study, a single site scenario representative of a mixed waste evaporation pond was constructed. Preliminary comparisons between ISV and incineration show that while operating costs are comparable, ISV avoids secondary treatment and monitored storage of radioactive waste that would be required following conventional incineration. It is the long term storage of incinerated material that is the most expensive component

  10. A Probabilistic Methodology for Assessing the Effectiveness of the Containment Filtered Venting Systems

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-10-15

    After the Chernobyl nuclear accident, mainly in Sweden, Germany, France, Switzerland, the Netherlands and other European countries have installed CFVS. In the US, some Boiling Water Reactor type only the voluntary installation of CFVS was required. But until now it has not been installed for pressurized water reactors. In Korea, CFVS is currently installed on Wolseong Unit 1 and preferentially applied to Heavy Water Reactor. Later it plans to apply for the Light Water Reactor. In this study, a safety improvement of installing the CFVS was assessed by the tool of Probabilistic Safety Assessment (PSA) for a reference plant. The CFVS is under installment in CANDU reactor for preventing the containment failure during severe accidents. But it has been evaluated that the effectiveness is negligible because of adverse effects of radioactive nuclides releases. Now the CFVS has not been installed yet in the LWR. The results can vary greatly depending on the detailed assessment.

  11. Performance of juvenile mojarra supplied with feed containing varying levels of crude protein

    Directory of Open Access Journals (Sweden)

    Ricardo Henrique Bastos de Souza

    2016-04-01

    Full Text Available ABSTRACT The growth of the Brazilian aquaculture has stimulated the development of the productive chain of native species, including marine environment. The objective of this study was to evaluate the growth performance of juvenile mojarra fish (Diapterus rhombeus fed diets containing different concentrations of crude protein (32, 36, 40 and 44 g 100 g-1. The 80 juvenile mojarra (7.2±1.5 g were kept in 16 circular tanks (150 L. The study design used was completely randomized with four treatments and four repetitions. The fish were fed four times a day. At the end of the experiment (60 days the final weight, feed intake, weight gain (WG, feed:gain ratio (FGR, protein efficiency rate (PER, energy efficiency rate, specific growth, survival rate and, body composition were evaluated. It was verified significant effect of protein level on the WG, with the best value at the level of 38.20 g 100 g-1 of crude protein. For FGR, the best estimated value occurred with 38.06 g 100 g-1 of crude protein, similar to that reported for the PER (38.91 g 100 g-1. The other performance parameters and body composition were not influenced by crude protein levels. Diet crude protein concentrations between 38.06 and 38.91 g 100 g-1 provide the best performance indices for juvenile mojarra.

  12. Enhancing physical performance in male volleyball players with a caffeine-containing energy drink.

    Science.gov (United States)

    Del Coso, Juan; Pérez-López, Alberto; Abian-Vicen, Javier; Salinero, Juan Jose; Lara, Beatriz; Valadés, David

    2014-11-01

    There are no scientific data about the effects of caffeine intake on volleyball performance. The aim of this study was to investigate the effect of a caffeine-containing energy drink to enhance physical performance in male volleyball players. A double-blind, placebo-controlled, randomized experimental design was used. In 2 different sessions separated by 1 wk, 15 college volleyball players ingested 3 mg of caffeine per kg of body mass in the form of an energy drink or the same drink without caffeine (placebo). After 60 min, participants performed volleyball-specific tests: standing spike test, maximal squat jump (SJ), maximal countermovement jump (CMJ), 15-s rebound jump test (15RJ), and agility T-test. Later, a simulated volleyball match was played and recorded. In comparison with the placebo drink, the ingestion of the caffeinated energy drink increased ball velocity in the spike test (73 ± 9 vs 75 ± 10 km/h, P volleyball actions more frequently (24.6% ± 14.3% vs 34.3% ± 16.5%, P volleyball players.

  13. Some viewpoints on reference biospheres in Finnish performance assessments

    International Nuclear Information System (INIS)

    Rasilainen, K.; Kattilakoski, E.; Suolanen, V.; Vieno, T.; Vuori, S.

    2002-01-01

    Viewpoints are presented concerning biosphere studies in performance assessments of nuclear waste disposal. The points are based on experiences from several Finnish performance assessments. The latest performance assessment for spent fuel disposal, TILA-99, was considered in the Decision in Principle process for the site selection of the repository. The points given are also based on experiences from participation in international projects dealing with biosphere modelling, for instance BIOMOVS and BIOMASS. (author)

  14. Performance objectives for the Hanford Immobilized Low-Activity Waste (ILAW) performance assessment

    International Nuclear Information System (INIS)

    MANN, F.M.

    1999-01-01

    Performance objectives for the disposal of low activity waste from Hanford Waste Tanks have been developed. These objectives have been based on DOE requirements, programmatic requirements, and public involvement. The DOE requirements include regulations that direct the performance assessment and are cited within the Radioactive Waste Management Order (DOE Order 435.1). Performance objectives for other DOE complex performance assessments have been included

  15. IPE Data Base: Plant design, core damage frequency and containment performance information

    International Nuclear Information System (INIS)

    Lehner, J.; Lin, C.C.; Pratt, W.T.; Su, T.; Danziger, L.

    1995-01-01

    This data base stores data obtained from the Individual Plant Examinations (IPEs) which licensees of nuclear power plants have conducted in response to NRC's Generic Letter GL88-20. The IPE Data Base is a collection of linked files which store information about plant design, core damage frequency, and containment performance in a uniform, structured way. The information contined in the various files is based on data contained in the IPE submittals. The information extracted from the submittals and entered into the IPE Data Base can be maniulated so that queries regarding individual or groups of plants can be answered using the IPE Data Base. The IPE Data Base supports detailed inquiries into the characteristics of individual plants or classes of plants. Progress has been made on the IPE Data Base and it is largely complete. Recent focus has been the development of a user friendly version which is menu driven and allows the user to ask queries of varying complexity easily, without the need to become familiar with particular data base formats or conventions such as those of DBase IV or Microsoft Access. The user can obtain the information he desired by quickly moving through a series of on-screen menus and ''clicking'' on appropriate choices. In this way even a first time user can benefit from the large amount of information stored in the IPE Data Base without the need of a learning period

  16. Influence of Steel Fibers on the Structural Performance of a Prestressed Concrete Containment Building

    International Nuclear Information System (INIS)

    Choun, Youngsun; Hahm, Daegi; Park, Junhee

    2013-01-01

    A large number of previous experimental investigations indicate that the use of steel fibers in conventional reinforced concrete (RC) can enhance the structural and functional performance of prestressed concrete containment buildings (PCCBs) in nuclear power plants. A prevention of through-wall cracks and an increase of the post-cracking ductility will improve the ultimate internal pressure capacity, and a high shear resistance under cyclic loadings will increase the seismic resisting capacity. In this study, the effects of steel fiber reinforced concrete (SFRC) on the ultimate pressure and seismic capacities of a PCCB are investigated. The effects of steel fibers on the ultimate pressure and shear resisting capacities of a PCCB are investigated. It is revealed that both of the ultimate pressure capacity and the shear resisting capacity of a PCCB can be greatly enhanced by introducing steel fibers in a conventional RC. Estimation results indicate that the ultimate pressure capacity and maximum lateral displacement of a PCCB can be improved by 16% and 64%, respectively, if a conventional RC contains hooked steel fibers in a volume fraction of 1.0%

  17. Feeding Diets Containing Different Forms of Duckweed on Productive Performance and Egg Quality of Ducks

    Directory of Open Access Journals (Sweden)

    B. Indarsih

    2012-08-01

    Full Text Available The present experiment was undertaken to study the feeding effect of diets containing different forms of duckweed for local ducks on their productive performance and egg quality or egg yolk pigmentation. A total of 90 birds of 24 wk old ducks were randomly divided into 18 experimental units of 2.0 x 1.0 m2 of cages. The experiment was assigned in a completely randomized design (3 treatments with 6 replicates, 5 birds each. There were 3 dietary treatments, namely P1= ducks fed a complete diet containing 20 % of dried duckweed and given in the form of dry-mash; P2= a complete diet in P1 but it was offered in wet form (slurry; and P3= ducks were offered basal diet in the form of dry-mash and fresh duckweed was offered separately ad libitum. Diets were formulated to have similar nutritional contents. Feed consumption, feed conversion ratio (FCR, and egg yolk pigmentation were measured. The result of the study showed that these three parameters were affected by the feeding different forms of duckweed. Feeding diet with fresh duckweed brought about the best pigmentation than did the dry one. Fresh duckweed offers a promise as a potential feedstuff for ducks and has a good implication in reducing feed processing cost.

  18. Influence of Steel Fibers on the Structural Performance of a Prestressed Concrete Containment Building

    Energy Technology Data Exchange (ETDEWEB)

    Choun, Youngsun; Hahm, Daegi; Park, Junhee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    A large number of previous experimental investigations indicate that the use of steel fibers in conventional reinforced concrete (RC) can enhance the structural and functional performance of prestressed concrete containment buildings (PCCBs) in nuclear power plants. A prevention of through-wall cracks and an increase of the post-cracking ductility will improve the ultimate internal pressure capacity, and a high shear resistance under cyclic loadings will increase the seismic resisting capacity. In this study, the effects of steel fiber reinforced concrete (SFRC) on the ultimate pressure and seismic capacities of a PCCB are investigated. The effects of steel fibers on the ultimate pressure and shear resisting capacities of a PCCB are investigated. It is revealed that both of the ultimate pressure capacity and the shear resisting capacity of a PCCB can be greatly enhanced by introducing steel fibers in a conventional RC. Estimation results indicate that the ultimate pressure capacity and maximum lateral displacement of a PCCB can be improved by 16% and 64%, respectively, if a conventional RC contains hooked steel fibers in a volume fraction of 1.0%.

  19. The role of performance assessment in radioactive waste disposal

    International Nuclear Information System (INIS)

    Stenhouse, M.J.

    1998-01-01

    Performance assessment has many applications in the field of radioactive waste management, none more important than demonstrating the suitability of a particular repository system for waste disposal. The role of performance assessment in radioactive waste disposal is discussed with reference to assessments performed in civilian waste management programmes. The process is, however, relevant, and may be applied directly to the disposal of defence-related wastes. When used in an open and transparent manner, performance assessment is a powerful methodology not only for convincing the authorities of the safety of a disposal concept, but also for gaining the wider acceptance of the general public for repository siting. 26 refs

  20. The performance of polymer containers used for the storage of radioactive waste

    International Nuclear Information System (INIS)

    Brown, L.; Bonin, H.W.; Bui, V.T.

    2005-01-01

    An evaluation of the performance of polymeric materials after exposure to radiation and acidic aqueous solutions provides a basis for the evaluation of failure mechanisms affecting these materials. The work evaluated the importance of the combined effects of aqueous solution diffusion, radiation exposure, and temperature on the mechanical performance, diffusion profile and molecular structure of polymeric materials. This work demonstrated that the dose rate is an extremely important factor since low dose rates have been shown to result in an increase in stress at yield (15 - 20%) over the times studied, whereas higher dose rates reduced stress at yield as discussed above. Irradiation of both Nylon 6,6 and Semi-Aromatic Nylon 6,6 at dose rates of 37 and 56 kGy/hr resulted in an initial decrease in the stress at yield and subsequent recovery. Irradiation at 20 kGy/hr resulted in an initial increase in stress at yield and a continued increase throughout the aging time. It is suggested that polyamide 6,6 may be considered an acceptable material for the fabrication of storage containers for Low Level Radioactive Waste. Similarly, semi-aromatic polyamide 6,6, with its greater resistance to the combined effects of solution diffusion and radiation exposure, may be considered an acceptable material for the fabrication of containers for the storage of Intermediate Level Radioactive Waste. Finally, these results provide further explanation of the results obtained for materials such as polycarbonate, which has been previously determined to be viable candidates for the storage of High Level Radioactive Waste. (author)

  1. The performance of polymer containers used for the storage of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Brown, L.; Bonin, H.W.; Bui, V.T. [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)]. E-mail: bonin-h@rmc.ca

    2005-07-01

    An evaluation of the performance of polymeric materials after exposure to radiation and acidic aqueous solutions provides a basis for the evaluation of failure mechanisms affecting these materials. The work evaluated the importance of the combined effects of aqueous solution diffusion, radiation exposure, and temperature on the mechanical performance, diffusion profile and molecular structure of polymeric materials. This work demonstrated that the dose rate is an extremely important factor since low dose rates have been shown to result in an increase in stress at yield (15 - 20%) over the times studied, whereas higher dose rates reduced stress at yield as discussed above. Irradiation of both Nylon 6,6 and Semi-Aromatic Nylon 6,6 at dose rates of 37 and 56 kGy/hr resulted in an initial decrease in the stress at yield and subsequent recovery. Irradiation at 20 kGy/hr resulted in an initial increase in stress at yield and a continued increase throughout the aging time. It is suggested that polyamide 6,6 may be considered an acceptable material for the fabrication of storage containers for Low Level Radioactive Waste. Similarly, semi-aromatic polyamide 6,6, with its greater resistance to the combined effects of solution diffusion and radiation exposure, may be considered an acceptable material for the fabrication of containers for the storage of Intermediate Level Radioactive Waste. Finally, these results provide further explanation of the results obtained for materials such as polycarbonate, which has been previously determined to be viable candidates for the storage of High Level Radioactive Waste. (author)

  2. An assessment of Class-9 (core-melt) accidents for PWR dry-containment systems

    International Nuclear Information System (INIS)

    Theofanous, T.G.; Saito, M.

    1981-01-01

    The phenomenology of core-melt accidents in dry containments was examined for the purpose of identifying the margins of safety in such Class-9 situations. The scale (geometry) effects appear to crucially limit the extent (severity) of steam explosions. This together with the established reduced explosivity of the corium-A/water system, and the inherently high capability of dry containments (redinforced concrete, and shields in some cases, seismic design etc.) lead to the conclusion that failure due to steam explosions may be considered essentially incredible. These premixture scaling considerations also impact ultimate debris disposition and coolability and need additional development. A water-flooded reactor cavity would have beneficial effects in limiting (but not necessarily eliminating) melt-concrete interactions. Independently of the initial degree of quenching and/or scale of fragmentation, mechanisms exist that drive the system towards ultimate stability (coolability). Additional studies, with intermediate-scale prototypic materials are recommended to better explore these mechanisms. Containment heat removal systems must provide the crucial capability of mitigating such accidents. Passive systems should be explored and assessed against currently available and/or improved active systems taking into account the rather loose time constraints required for activation. It appears that containment margins for accommodating the hydrogen problem are limited. This problem appears to stand out not only in terms of potential consequences but also in terms of lack of any readily available and clear cut solutions at this time. (orig.)

  3. Development and application of a tool to assess laboratory hygiene in contained-use facilities.

    Science.gov (United States)

    Rutjes, S A; Lodder-Verschoor, F; Tijssen, J P; de Roda Husman, A M

    2011-02-01

    To gain information on laboratory hygiene in contained-use laboratories, a method was developed to study the presence of microorganisms on laboratory equipment. Focusing detection on genetically modified organisms (GMOs) containing the universal M13 primer binding sites enabled the detection of a broad range of GMOs using a single PCR. Swabbing surfaces in three different contained-use laboratories led to detection of M13-containing PCR products in 26 out of 34 swabs. Most sequences (up to five per sample) were detected in swabs from the centrifuge and sink, followed by swabs taken from the bin and incubator (up to four sequences per sample). The obtained sequences varied in length from 171 nucleotides (nt) to 878 nt. In most cases, sequences were only partially similar to sequences published in GenBank. The lengths of the regions with high similarity varied from 94 nt to 795 nt, and these similarities ranged from 81% to 100%. Similarities with more than one sequence were commonly found, complicating the identification of detected sequences. Nonetheless, 84% of the detected sequences were actually handled in the laboratory at the time of sampling. This demonstrates that the method may be used as a quality control tool to assess the efficacy of decontamination and cleaning of commonly used surfaces, such as laboratory benches, freezer doors, and centrifuge rotors, without prior knowledge of the identity or characteristics of the GMOs.

  4. Development and Application of a Tool To Assess Laboratory Hygiene in Contained-Use Facilities▿

    Science.gov (United States)

    Rutjes, S. A.; Lodder-Verschoor, F.; Tijssen, J. P.; de Roda Husman, A. M.

    2011-01-01

    To gain information on laboratory hygiene in contained-use laboratories, a method was developed to study the presence of microorganisms on laboratory equipment. Focusing detection on genetically modified organisms (GMOs) containing the universal M13 primer binding sites enabled the detection of a broad range of GMOs using a single PCR. Swabbing surfaces in three different contained-use laboratories led to detection of M13-containing PCR products in 26 out of 34 swabs. Most sequences (up to five per sample) were detected in swabs from the centrifuge and sink, followed by swabs taken from the bin and incubator (up to four sequences per sample). The obtained sequences varied in length from 171 nucleotides (nt) to 878 nt. In most cases, sequences were only partially similar to sequences published in GenBank. The lengths of the regions with high similarity varied from 94 nt to 795 nt, and these similarities ranged from 81% to 100%. Similarities with more than one sequence were commonly found, complicating the identification of detected sequences. Nonetheless, 84% of the detected sequences were actually handled in the laboratory at the time of sampling. This demonstrates that the method may be used as a quality control tool to assess the efficacy of decontamination and cleaning of commonly used surfaces, such as laboratory benches, freezer doors, and centrifuge rotors, without prior knowledge of the identity or characteristics of the GMOs. PMID:21183638

  5. Tools for Performance Assessment of OLSR Protocol

    Directory of Open Access Journals (Sweden)

    Makoto Ikeda

    2009-01-01

    Full Text Available In this paper, we evaluate the performance of Optimized Link State Routing (OLSR protocol by experimental and simulation results. The experiments are carried out by using our implemented testbed and the simulations by using ns-2 simulator. We also designed and implemented a new interface for the ad-hoc network testbed in order to make more easier the experiments. The comparison between experimental and simulation results shows that for the same parameters set, in the simulation we did not notice any packet loss. On the other hand, in the experiments we experienced packet loss because of the environment effects and traffic interference.

  6. Thorium fuel performance assessment in HTRs

    Energy Technology Data Exchange (ETDEWEB)

    Allelein, H.-J. [Forschungszentrum Jülich, D-52425 Jülich (Germany); RWTH Aachen, D-52072 Aachen (Germany); Kania, M.J.; Nabielek, H. [Forschungszentrum Jülich, D-52425 Jülich (Germany); Verfondern, K., E-mail: k.verfondern@fz-juelich.de [Forschungszentrum Jülich, D-52425 Jülich (Germany)

    2014-05-01

    Thorium as a nuclear fuel is receiving renewed interest, because of its widespread availability and the good irradiation performance of Th and mixed (Th,U) oxide compounds as fuels in nuclear power systems. Early HTR development employed thorium together with high-enriched uranium. After 1980, most HTR fuel systems switched to low-enriched uranium. After completing fuel development for AVR and THTR with BISO coated particles, the German program expanded efforts on a new program utilizing thorium and high-enriched uranium TRISO coated particles for advanced HTR concepts for process heat applications (PNP) and direct-cycle electricity production (HHT). The combination of LTI inner and outer pyrocarbon layers surrounding a strong, stable SiC layer greatly improved manufacturing conditions and the subsequent contamination and defective particle fractions in production fuel elements. In addition, this combination provided improved mechanical strength and a higher degree of solid fission product retention, not known previously with HTI-BISO coatings. The improved performance of the HEU (Th,U)O{sub 2} TRISO fuel system was successfully demonstrated in three primary areas of development: manufacturing, irradiation testing under normal operating conditions, and accident simulation testing. In terms of demonstrating performance for advanced HTR applications, the experimental failure statistic from manufacture and irradiation testing are significantly below the coated particle requirements specified for PNP and HHT designs at the time. Covering a range to 1300 °C in normal operations and 1600 °C in accidents, with burnups up to 13% FIMA and fast fluences to 8 × 10{sup 25} m{sup −2} (E > 16 fJ), the results exceed the design limits on manufacturing and operational requirements for the German HTR Modul concept, which were: <6.5 × 10{sup −5} for manufacturing; <2 × 10{sup −4} for normal operating conditions; and <5 × 10{sup −4} for accident conditions. These

  7. Performance Assessment as a Diagnostic Tool for Science Teachers

    Science.gov (United States)

    Kruit, Patricia; Oostdam, Ron; van den Berg, Ed; Schuitema, Jaap

    2018-04-01

    Information on students' development of science skills is essential for teachers to evaluate and improve their own education, as well as to provide adequate support and feedback to the learning process of individual students. The present study explores and discusses the use of performance assessments as a diagnostic tool for formative assessment to inform teachers and guide instruction of science skills in primary education. Three performance assessments were administered to more than 400 students in grades 5 and 6 of primary education. Students performed small experiments using real materials while following the different steps of the empirical cycle. The mutual relationship between the three performance assessments is examined to provide evidence for the value of performance assessments as useful tools for formative evaluation. Differences in response patterns are discussed, and the diagnostic value of performance assessments is illustrated with examples of individual student performances. Findings show that the performance assessments were difficult for grades 5 and 6 students but that much individual variation exists regarding the different steps of the empirical cycle. Evaluation of scores as well as a more substantive analysis of students' responses provided insight into typical errors that students make. It is concluded that performance assessments can be used as a diagnostic tool for monitoring students' skill performance as well as to support teachers in evaluating and improving their science lessons.

  8. Performance Assessment of Intelligence, Surveillance, and Reconnaissance (ISR) Enterprise Workflows

    National Research Council Canada - National Science Library

    Hurley, M. B; Jones, P. B

    2007-01-01

    ... on how to assess the performance of these systems. The framework delineates how measurements from laboratory tests, operational experiments, and field deployments can be analyzed to produce accurate, quantitative descriptions of system performance...

  9. Practical session assessments in human anatomy: Weightings and performance.

    Science.gov (United States)

    McDonald, Aaron C; Chan, Siew-Pang; Schuijers, Johannes A

    2016-07-08

    Assessment weighting within a given module can be a motivating factor for students when deciding on their commitment level and time given to study a specific topic. In this study, an analysis of assessment performances of second year anatomy students was performed over four years to determine if (1) students performed better when a higher weighting was given to a set of practical session assessments and (2) whether an improved performance in the practical session assessments had a carry-over effect on other assessment tasks within that anatomy module and/or other anatomy modules that follow. Results showed that increasing the weighting of practical session assessments improved the average mark in that assessment and also improved the percentage of students passing that assessment. Further, it significantly improved performance in the written end-semester examination within the same module and had a carry-over effect on the anatomy module taught in the next teaching period, as students performed better in subsequent practical session assessments as well as subsequent end-semester examinations. It was concluded that the weighting of assessments had significant influences on a student's performance in that, and subsequent, assessments. It is postulated that practical session assessments, designed to develop deep learning skills in anatomy, improved efficacy in student performance in assessments undertaken in that and subsequent anatomy modules when the weighting of these assessments was greater. These deep learning skills were also transferable to other methods of assessing anatomy. Anat Sci Educ 9: 330-336. © 2015 American Association of Anatomists. © 2015 American Association of Anatomists.

  10. Assessing The Performance of Hydrological Models

    Science.gov (United States)

    van der Knijff, Johan

    The performance of hydrological models is often characterized using the coefficient of efficiency, E. The sensitivity of E to extreme streamflow values, and the difficulty of deciding what value of E should be used as a threshold to identify 'good' models or model parameterizations, have proven to be serious shortcomings of this index. This paper reviews some alternative performance indices that have appeared in the litera- ture. Legates and McCabe (1999) suggested a more generalized form of E, E'(j,B). Here, j is a parameter that controls how much emphasis is put on extreme streamflow values, and B defines a benchmark or 'null hypothesis' against which the results of the model are tested. E'(j,B) was used to evaluate a large number of parameterizations of a conceptual rainfall-runoff model, using 6 different combinations of j and B. First, the effect of j and B is explained. Second, it is demonstrated how the index can be used to explicitly test hypotheses about the model and the data. This approach appears to be particularly attractive if the index is used as a likelihood measure within a GLUE-type analysis.

  11. Assessment of risks for employees of France Telecom regarding overvoltage arresters containing radio-elements

    International Nuclear Information System (INIS)

    Thomassin, A.; Metz, C.; Rannou, A.

    2010-01-01

    As a great number of overvoltage arresters used by France Telecom to protect its telecommunication network against disturbing voltages (notably lightning) contain radio-elements, this report aims at assessing dose levels and associated risks for employees exposed to radioactive overvoltage arrester when setting them up, exploiting installations containing such arresters, or when removing them. After a presentation of these devices, a modelling of activities and geometries is proposed, as well as computation tools. Different scenarios and exposure situations are considered. As far as risks are concerned, after a recall on cancers and ionizing radiation, and on the exposure of France Telecom employees, the report comments the knowledge on radio-induced cancers; notably breast cancer, skin cancer, and mouth and pharynx cancers

  12. MELCOR 1.8.2 Assessment: IET direct containment heating tests

    Energy Technology Data Exchange (ETDEWEB)

    Kmetyk, L.N.

    1993-10-01

    MELCOR is a fully integrated, engineering-level computer code, being developed at Sandia National Laboratories for the USNRC, that models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRS. As part of an ongoing assessment program, the MELCOR computer code has been used to analyze several of the IET direct containment heating experiments done at 1:10 linear scale in the Surtsey test facility at Sandia and at 1:40 linear scale in the corium-water thermal interactions (CWTI) COREXIT test facility at Argonne National Laboratory. These MELCOR calculations were done as an open post-test study, with both the experimental data and CONTAIN results available to guide the selection of code input. Basecase MELCOR results are compared to test data in order to evaluate the new HPME DCH model recently added in MELCOR version 1.8.2. The effect of various user-input parameters in the HPME model, which define both the initial debris source and the subsequent debris interaction, were investigated in sensitivity studies. In addition, several other non-default input modelling changes involving other MELCOR code packages were required in our IET assessment analyses in order to reproduce the observed experiment behavior. Several calculations were done to identify whether any numeric effects exist in our DCH IET assessment analyses.

  13. Assessing Bus Performance Rating in Kajang, Selangor

    Science.gov (United States)

    Norhisham, S.; Ismail, A.; Sidek, L. M.; Borhan, M. N.; Zaini, N.; Yen, A. T. G.

    2018-04-01

    The Transit Capacity and Quality of Service Manual (TCQSM) was chosen based on the review with four manuals and guidelines for the method will be applied. Six (6) attributes, namely Hours of Service, Passenger Load, Transit Auto Travel Time, Service Frequency, Punctuality Performance and Service Coverage were chosen for evaluation.[6][7][8]. A total of three (3) operators with seven (7) routes were identified in Kajang. Based on the final results, the Quality of Service (QOS) findings was rated as D, which was regarded as minimum or satisfactory. Most stakeholders’ recommendations were: for the operators to provide information on bus scheduling and have accurate information for the passengers. It was suggested that in future this study can be extended to all routes and could be repeated after the opening of the Mass Rapid Transit (MRT) stations in Kajang, so as to provide a comparison and better evaluation of the public buses in Kajang.

  14. Synchronous and Cogged Fan Belt Performance Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Cutler, Dylan [National Renewable Energy Lab. (NREL), Golden, CO (United States); Dean, Jesse [National Renewable Energy Lab. (NREL), Golden, CO (United States); Acosta, Jason [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2014-02-01

    The GSA Regional GPG Team commissioned the National Renewable Energy Laboratory (NREL) to perform monitoring of cogged V-belts and synchronous belts on both a constant volume and a variable air volume fan at the Byron G. Rodgers Federal Building and U.S. Courthouse in Denver, Colorado. These motor/fan combinations were tested with their original, standard V-belts (appropriately tensioned by an operation and maintenance professional) to obtain a baseline for standard operation. They were then switched to the cogged V-belts, and finally to synchronous belts. The power consumption by the motor was normalized for both fan speed and air density changes. This was necessary to ensure that the power readings were not influenced by a change in rotational fan speed or by the power required to push denser air. Finally, energy savings and operation and maintenance savings were compiled into an economic life-cycle cost analysis of the different belt options.

  15. Integrity assessment of grouted posttensioning cables and reinforced concrete of a nuclear containment building

    Science.gov (United States)

    Philipose, K.; Shenton, B.

    2011-04-01

    The Containment Buildings of CANDU Nuclear Generating Stations were designed to house nuclear reactors and process equipment and also to provide confinement of releases from a potential nuclear accident such as a Loss Of Coolant Accident (LOCA). To meet this design requirement, a post-tensioning system was designed to induce compressive stresses in the structure to counteract the internal design pressure. The CANDU reactor building at Gentilly-1 (G-1), Quebec, Canada (250 MWe) was built in the early 1970s and is currently in a decommissioned state. The structure at present is under surveillance and monitoring. In the year 2000, a field investigation was conducted as part of a condition assessment and corrosion was detected in some of the grouted post-tension cable strands. However, no further work was done at that time to determine the cause, nature, impact and extent of the corrosion. An investigation of the Gentilly-1 containment building is currently underway to assess the condition of grouted post-tensioning cables and reinforced concrete. At two selected locations, concrete and steel reinforcements were removed from the containment building wall to expose horizontal cables. Individual cable strands and reinforcement bars were instrumented and measurements were taken in-situ before removing them for forensic examination and destructive testing to determine the impact of ageing and corrosion. Concrete samples were also removed and tested in a laboratory. The purpose of the field investigation and laboratory testing, using this structure as a test bed, was also to collect material ageing data and to develop potential Nondestructive Examination (NDE) methods to monitor Containment Building Integrity. The paper describes the field work conducted and the test results obtained for concrete, reinforcement and post-tensioning cables.

  16. Integrity assessment of grouted posttensioning cables and reinforced concrete of a nuclear containment building

    Directory of Open Access Journals (Sweden)

    Shenton B.

    2011-04-01

    Full Text Available The Containment Buildings of CANDU Nuclear Generating Stations were designed to house nuclear reactors and process equipment and also to provide confinement of releases from a potential nuclear accident such as a Loss Of Coolant Accident (LOCA. To meet this design requirement, a post-tensioning system was designed to induce compressive stresses in the structure to counteract the internal design pressure. The CANDU reactor building at Gentilly-1 (G-1, Quebec, Canada (250 MWe was built in the early 1970s and is currently in a decommissioned state. The structure at present is under surveillance and monitoring. In the year 2000, a field investigation was conducted as part of a condition assessment and corrosion was detected in some of the grouted post-tension cable strands. However, no further work was done at that time to determine the cause, nature, impact and extent of the corrosion. An investigation of the Gentilly-1 containment building is currently underway to assess the condition of grouted post-tensioning cables and reinforced concrete. At two selected locations, concrete and steel reinforcements were removed from the containment building wall to expose horizontal cables. Individual cable strands and reinforcement bars were instrumented and measurements were taken in-situ before removing them for forensic examination and destructive testing to determine the impact of ageing and corrosion. Concrete samples were also removed and tested in a laboratory. The purpose of the field investigation and laboratory testing, using this structure as a test bed, was also to collect material ageing data and to develop potential Nondestructive Examination (NDE methods to monitor Containment Building Integrity. The paper describes the field work conducted and the test results obtained for concrete, reinforcement and post-tensioning cables.

  17. An Empirical Study of a Solo Performance Assessment Model

    Science.gov (United States)

    Russell, Brian E.

    2015-01-01

    The purpose of this study was to test a hypothesized model of solo music performance assessment. Specifically, this study investigates the influence of technique and musical expression on perceptions of overall performance quality. The Aural Musical Performance Quality (AMPQ) measure was created to measure overall performance quality, technique,…

  18. Risk assessment of combined exposure to alkenylbenzenes through consumption of plant food supplements containing parsley and dill.

    Science.gov (United States)

    Alajlouni, Abdalmajeed M; Al-Malahmeh, Amer J; Wesseling, Sebastiaan; Kalli, Marina; Vervoort, Jacques; Rietjens, Ivonne M C M

    2017-12-01

    A risk assessment was performed of parsley- and dill-based plant food supplements (PFS) containing apiol and related alkenylbenzenes. First, the levels of the alkenylbenzenes in the PFS and the resulting estimated daily intake (EDI) resulting from use of the PFS were quantified. Since most PFS appeared to contain more than one alkenylbenzene, a combined risk assessment was performed based on equal potency or using a so-called toxic equivalency (TEQ) approach based on toxic equivalency factors (TEFs) for the different alkenylbenzenes. The EDIs resulting from daily PFS consumption amount to 0.74-125 µg kg -1 bw for the individual alkenylbenzenes, 0.74-160 µg kg -1 bw for the sum of the alkenylbenzenes, and 0.47-64 µg kg -1 bw for the sum of alkenylbenzenes when expressed in safrole equivalents. The margins of exposure (MOEs) obtained were generally below 10,000, indicating a priority for risk management if the PFS were to be consumed on a daily basis. Considering short-term use of the PFS, MOEs would increase above 10,000, indicating low priority for risk management. It is concluded that alkenylbenzene intake through consumption of parsley- and dill-based PFS is only of concern when these PFS are used for long periods of time.

  19. Digestibility and performance of lambs fed diets containing old man saltbush hay

    Directory of Open Access Journals (Sweden)

    Greicy Mitzi Bezerra Moreno

    2017-03-01

    Full Text Available The aim of this study was to evaluate feed intake, digestibility, nitrogen balance, water balance, and performance of lambs fed diets containing old man saltbush hay associated with a concentrate. Thirty-two castrated feedlot Santa Inês lambs at approximately eight months of age, with 22 ± 1.97 kg body weight, were distributed into a completely randomized experimental design. Acid detergent fiber intake increased (P < 0.05, whereas non-fibrous carbohydrates intake decreased (P < 0.01. Inclusion of old man saltbush in the diet reduced (P < 0.01 the digestibility of dry and organic matter, neutral and acid detergent fiber, and non-fibrous carbohydrates. The intakes of digestible dry and organic matter, ether extract, total carbohydrates, and digestible non-fibrous carbohydrates also decreased (P < 0.01. Inclusion of old man saltbush did not influence water consumption from the trough by the sheep, averaging 4,327.20 mL/day?1. Body weight at slaughter and daily weight gain decreased linearly (P < 0.05 and feed conversion worsened as old man saltbush hay was added to the diet. Inclusion of old man saltbush at up to 40% replacing the concentrate in feedlot lamb diets does not compromise the performance of these animals.

  20. Performance and economic analysis of broilers fed diets containing acerola meal in replacement of corn

    Directory of Open Access Journals (Sweden)

    Leonardo Henrique Zanetti

    2014-12-01

    Full Text Available It was aimed with this research to evaluate the performance of broiler chickens fed diets containing increasing levels of acerola meal in replacement of corn and analyze the economic viability of that production system. A total of 980 day-old male Cobb chicks were used, allotted in a completely randomized design, with four treatments - inclusion levels (0%, 5%, 10% and 15% of acerola meal in replacement of corn – and seven replications with 35 birds per experimental unit. The birds were weighed at 21 and 42 days of age to measure the performance data. In the period between 1 and 21 days of age, differences were observed in the feed intake and feed:gain only, in which the inclusion of acerola meal linearly decreased feed intake and improved feed:gain up to a level of 10.25%. For the total rearing period, the control treatment showed higher body weight. The feed:gain showed linear effect, worsening the results with increasing amounts of acerola meal in the diets. In the same period, there was no significant difference in feed intake and productive efficiency index. With regard to the economic analysis, it was found that the lowest final cost per broiler was observed in diets with 10% of acerola meal inclusion in replacement of corn.

  1. Performance of broilers fed on diets containing different amounts of chaya (Cnidoscolus aconitifolius) leaf meal.

    Science.gov (United States)

    Sarmiento-Franco, L; McNab, J M; Pearson, R A; Belmar-Casso, R

    2002-05-01

    The performance and gut measurements of broilers fed on diets containing different amounts of chaya (Cnidoscolus aconitifolius) leaf meal (CLM) were examined in two experiments. In the first experiment, 60 Hubbard chickens (30 males and 30 females; 2 weeks old) were fed on five maize diets; these were formulated using 0, 150 (CLM150), 250 (CLM250) or 350 (CLM350) g CLM/kg, and the fifth diet contained soyabean. In the second experiment, 148 Ross male chicks, 1 day old, were fed on three isonitrogenous and isoenergetic maize-soyabean-based diets, which included 0 (control), 150 (C150) or 250 (C250) g CLM/kg. The diets were offered ad libitum for 2 or 3 weeks in the first and second experiments, respectively. Food intake, weight gain and the food:weight gain ratio were recorded. The weight of the gizzard and intestine and the weight and length of the caeca were also determined in the second experiment. In experiment 1, the birds fed on the maize-soyabean diet had a higher (p < 0.05) weight gain and final weight than birds fed on maize only or on the CLM150 diets. There were no differences for any of the variables studied between the birds fed on the maize-soyabean diet and those fed on the CLM250, nor between males and females. In the second experiment, weight gain, food intake and the food:weight gain ratio for birds fed on C250 were lower (p < 0.05) than those in birds fed on either the control or C150 diets. The weights of the gizzard and intestine were the lowest and the highest, respectively, in birds fed on C250 (p < 0.05). The length and weight of the caecum from birds fed on the control diet were lower (p < 0.05) than those of birds fed on either the C150 or C250 diets. The results from this study suggest that CLM may be included up to 150 g/kg in commercial diets without having an adverse effect on poultry performance, and may also be mixed with maize up to 250 g/kg to improve the performance of chickens fed on low-protein diets.

  2. Performance Assessments of Generic Nuclear Waste Repositories in Shale

    Science.gov (United States)

    Stein, E. R.; Sevougian, S. D.; Mariner, P. E.; Hammond, G. E.; Frederick, J.

    2017-12-01

    Simulations of deep geologic disposal of nuclear waste in a generic shale formation showcase Geologic Disposal Safety Assessment (GDSA) Framework, a toolkit for repository performance assessment (PA) whose capabilities include domain discretization (Cubit), multiphysics simulations (PFLOTRAN), uncertainty and sensitivity analysis (Dakota), and visualization (Paraview). GDSA Framework is used to conduct PAs of two generic repositories in shale. The first considers the disposal of 22,000 metric tons heavy metal of commercial spent nuclear fuel. The second considers disposal of defense-related spent nuclear fuel and high level waste. Each PA accounts for the thermal load and radionuclide inventory of applicable waste types, components of the engineered barrier system, and components of the natural barrier system including the host rock shale and underlying and overlying stratigraphic units. Model domains are half-symmetry, gridded with Cubit, and contain between 7 and 22 million grid cells. Grid refinement captures the detail of individual waste packages, emplacement drifts, access drifts, and shafts. Simulations are run in a high performance computing environment on as many as 2048 processes. Equations describing coupled heat and fluid flow and reactive transport are solved with PFLOTRAN, an open-source, massively parallel multiphase flow and reactive transport code. Additional simulated processes include waste package degradation, waste form dissolution, radioactive decay and ingrowth, sorption, solubility, advection, dispersion, and diffusion. Simulations are run to 106 y, and radionuclide concentrations are observed within aquifers at a point approximately 5 km downgradient of the repository. Dakota is used to sample likely ranges of input parameters including waste form and waste package degradation rates and properties of engineered and natural materials to quantify uncertainty in predicted concentrations and sensitivity to input parameters. Sandia National

  3. Performance and dilemmas of urban containment strategies in the transformation context of Beijing

    NARCIS (Netherlands)

    Zhao, Pengjun; Lue, Bin; de Roo, Gert

    2010-01-01

    The implementation of urban containment policies is increasingly attracting attention in environment management. Rapid urban growth and the coexistence of decentralisation and marketisation challenge containment strategies that are implemented to control urban sprawl. This challenge is likely to be

  4. Peer mentoring in doctor performance assessment: strategies, obstacles and benefits.

    NARCIS (Netherlands)

    Overeem, K.; Driessen, E.W.; Arah, O.A.; Lombarts, K.M.; Wollersheim, H.C.H.; Grol, R.P.T.M.

    2010-01-01

    CONTEXT: Mentors are increasingly involved in doctor performance assessments. Mentoring seems to be a key determinant in achieving the ultimate goal of those assessments, namely, improving doctor performance. Little is known, however, about how mentors perceive and fulfil this role. OBJECTIVE: The

  5. Peer mentoring in doctor performance assessment: strategies, obstacles and benefits

    NARCIS (Netherlands)

    Overeem, Karlijn; Driessen, Erik W.; Arah, Onyebuchi A.; Lombarts, Kiki M. J. M. H.; Wollersheim, Hub C.; Grol, Richard P. T. M.

    2010-01-01

    CONTEXT: Mentors are increasingly involved in doctor performance assessments. Mentoring seems to be a key determinant in achieving the ultimate goal of those assessments, namely, improving doctor performance. Little is known, however, about how mentors perceive and fulfil this role. OBJECTIVE: The

  6. Performance of Nile tilapia juvenile fed diet containing different dosages ofrecombinant common carpgrowth hormone

    Directory of Open Access Journals (Sweden)

    Dian Hardiantho

    2013-11-01

    Full Text Available The studywas conductedtodetermine thedose of recombinant common carp growth hormone (rCcGH supplemented in the commercial diet that generates the best performanceonbodyweight, biomass, andfeed conversion rate of juvenile tilapia.The dose of rCcGH administered was10, 20, and30mg/kg of commercial feed, andnorGH supplementation as control. Eachtreatment was designed in triplicates. Juveniles at average bodylengthof about2cm(average body weight of 0.7 g were reared in a density of25fish/m2, for three weeks in hapa net at a size of 2×2×1 m3. Fish were fed diet containing rCcGH twicea week with an interval ofthreedays. The juvenile were fed with the rCcGH supplemented diet three times daily at satiation. The results showedthat average body weight andbiomass of fish treated by rCcGH with the doses of 20 and 30 mg/kg feed was higher (p<0.05 than that of 10 mg/kg and control. In addition, feed conversionrate of 20 and 30 mg/kg feed treatments was lower (p<0.05 than that of 10 mg/kg and control. RT-PCR analysisshowedthat expression level of IGF-1 gene in juvenile liver was increased in parallel with the increasing of rCcGH dosages supplemented in diet.This suggestedthatIGF-1 plays an important rolein the induction ofgrowth,andfeed conversionefficiencyof tilapiafed diet containing rCcGH. The bestperformance of juvenile can be obtainedby feeding with diet containingrCcGH20‒30mg/kgof feed. Keywords: rCcGH, IGF-I, recombinant growthhormone,performance, Nile tilapia.

  7. High performance all-carbon composite transparent electrodes containing uniform carbon nanotube networks

    Energy Technology Data Exchange (ETDEWEB)

    Yun, Hyung Duk; Kwak, Jinsung; Kim, Se-Yang [School of Materials Science and Engineering & Low-Dimensional Carbon Materials Center, Ulsan National Institute of Science and Technology (UNIST), Ulsan, 44919 (Korea, Republic of); Seo, Han; Bang, In Cheol; Kim, Sung Youb [School of Mechanical and Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST), Ulsan, 44919 (Korea, Republic of); Kang, Seoktae [Department of Civil and Environmental Engineering, Korea Advanced Institute of Science and Technology (KAIST), Daejeon, 34141 (Korea, Republic of); Kwon, Soon-Yong, E-mail: sykwon@unist.ac.kr [School of Materials Science and Engineering & Low-Dimensional Carbon Materials Center, Ulsan National Institute of Science and Technology (UNIST), Ulsan, 44919 (Korea, Republic of); School of Mechanical and Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST), Ulsan, 44919 (Korea, Republic of)

    2016-08-05

    Indium tin oxide-free, flexible transparent electrodes (TEs) are crucial for the future commercialization of flexible and wearable electronics. While carbon-based TEs containing carbon nanotube (CNT) networks show promise, they usually exhibit poor dispersion properties, limiting their performance and practicality. In this study, we report a highly efficient and bending durable all-carbon composite TE (ac-TE) that employs uniform CNT networks on a monolayer graphene/polyethylene terephthalate (PET) substrate via a simple air spray deposition method. The air-sprayed CNT/graphene assembly was free-standing on solution, making a polymer-free transfer of carbon composites to target substrates possible. The excellent performance of the ac-TEs was attributed to the uniformly networked CNTs on the polycrystalline graphene with a well-controlled density, effectively bridging the line defects and filling the tears/voids or folds necessarily existing in the as-processed graphene. The sheet resistance of the ac-TEs was increased only 6% from its original value at a bending radius of 2.7 mm, while that of the pristine graphene/PET assembly increased 237%. Mechanical bending of the ac-TEs worsened the electrical performance by only ∼1.7% after 2000 bending cycles at a bending radius of 2.5 mm. Degradation of the performance by the bending was the result of line defects formation in the graphene, demonstrating the potential of the uniform CNT networks to achieve more efficient and flexible carbon-based TEs. Furthermore, the chemically-doped ac-TEs showed commercially suitable electronic and optical properties with much enhanced thermal stability, closer to practical TEs in flexible devices. - Highlights: • Highly efficient and bending durable all-carbon composite transparent electrodes (TEs) are designed. • The performance was strongly dependent on morphology of CNT networks on graphene. • The mechanism relies on the defect reductions in graphene by uniform CNT coating

  8. High performance all-carbon composite transparent electrodes containing uniform carbon nanotube networks

    International Nuclear Information System (INIS)

    Yun, Hyung Duk; Kwak, Jinsung; Kim, Se-Yang; Seo, Han; Bang, In Cheol; Kim, Sung Youb; Kang, Seoktae; Kwon, Soon-Yong

    2016-01-01

    Indium tin oxide-free, flexible transparent electrodes (TEs) are crucial for the future commercialization of flexible and wearable electronics. While carbon-based TEs containing carbon nanotube (CNT) networks show promise, they usually exhibit poor dispersion properties, limiting their performance and practicality. In this study, we report a highly efficient and bending durable all-carbon composite TE (ac-TE) that employs uniform CNT networks on a monolayer graphene/polyethylene terephthalate (PET) substrate via a simple air spray deposition method. The air-sprayed CNT/graphene assembly was free-standing on solution, making a polymer-free transfer of carbon composites to target substrates possible. The excellent performance of the ac-TEs was attributed to the uniformly networked CNTs on the polycrystalline graphene with a well-controlled density, effectively bridging the line defects and filling the tears/voids or folds necessarily existing in the as-processed graphene. The sheet resistance of the ac-TEs was increased only 6% from its original value at a bending radius of 2.7 mm, while that of the pristine graphene/PET assembly increased 237%. Mechanical bending of the ac-TEs worsened the electrical performance by only ∼1.7% after 2000 bending cycles at a bending radius of 2.5 mm. Degradation of the performance by the bending was the result of line defects formation in the graphene, demonstrating the potential of the uniform CNT networks to achieve more efficient and flexible carbon-based TEs. Furthermore, the chemically-doped ac-TEs showed commercially suitable electronic and optical properties with much enhanced thermal stability, closer to practical TEs in flexible devices. - Highlights: • Highly efficient and bending durable all-carbon composite transparent electrodes (TEs) are designed. • The performance was strongly dependent on morphology of CNT networks on graphene. • The mechanism relies on the defect reductions in graphene by uniform CNT coating

  9. Performance Assessment Framework for Private Finance Initiative Projects in Malaysia

    Directory of Open Access Journals (Sweden)

    Lop Nor Suzila

    2016-01-01

    Full Text Available Private Finance Initiative (PFI is viewed as restructuring the previous privatisation concept in delivering value for money for the Malaysian public infrastructure. Among the restructuring efforts in the privatisation is specifying the standard assessment of private concessionaires’ performance through the execution of key performance indicators (KPIs where the private concessionaires’ performance is benchmarked against the government’s standard. KPIs have served as useful tools in assessing performance of PFI projects. However, there is still lacking on determination methods performed to define and measure this KPIs and the absence of guidelines or a framework is also an issue in the implementation of the PFI procurement in Malaysia. Therefore, the objectives of this paper is to investigate the notion of performance assessment model approaches globally (i.e. UK, China, Australia, Serbia and Malaysia and to identify direction for PFI performance assessment tools (KPIs to be practiced in Malaysia. Based on the consideration of these models, this research paper propose an initial framework of performance assessment for PFI projects in Malaysia. The framework is deliberate to cover the performance of PFI at the operation and maintenance phase. The outcomes of this paper can serve as a theoretical base for the development of comprehensive and effective performance assessment for PFI projects in Malaysia.

  10. Model error assessment of burst capacity models for energy pipelines containing surface cracks

    International Nuclear Information System (INIS)

    Yan, Zijian; Zhang, Shenwei; Zhou, Wenxing

    2014-01-01

    This paper develops the probabilistic characteristics of the model errors associated with five well-known burst capacity models/methodologies for pipelines containing longitudinally-oriented external surface cracks, namely the Battelle and CorLAS™ models as well as the failure assessment diagram (FAD) methodologies recommended in the BS 7910 (2005), API RP579 (2007) and R6 (Rev 4, Amendment 10). A total of 112 full-scale burst test data for cracked pipes subjected internal pressure only were collected from the literature. The model error for a given burst capacity model is evaluated based on the ratios of the test to predicted burst pressures for the collected data. Analysis results suggest that the CorLAS™ model is the most accurate model among the five models considered and the Battelle, BS 7910, API RP579 and R6 models are in general conservative; furthermore, the API RP579 and R6 models are markedly more accurate than the Battelle and BS 7910 models. The results will facilitate the development of reliability-based structural integrity management of pipelines. - Highlights: • Model errors for five burst capacity models for pipelines containing surface cracks are characterized. • Basic statistics of the model errors are obtained based on test-to-predicted ratios. • Results will facilitate reliability-based design and assessment of energy pipelines

  11. Determination of Safety Performance Grade of NPP Using Integrated Safety Performance Assessment (ISPA) Program

    International Nuclear Information System (INIS)

    Chung, Dae Wook

    2011-01-01

    Since the beginning of 2000, the safety regulation of nuclear power plant (NPP) has been challenged to be conducted more reasonable, effective and efficient way using risk and performance information. In the United States, USNRC established Reactor Oversight Process (ROP) in 2000 for improving the effectiveness of safety regulation of operating NPPs. The main idea of ROP is to classify the NPPs into 5 categories based on the results of safety performance assessment and to conduct graded regulatory programs according to categorization, which might be interpreted as 'Graded Regulation'. However, the classification of safety performance categories is highly comprehensive and sensitive process so that safety performance assessment program should be prepared in integrated, objective and quantitative manner. Furthermore, the results of assessment should characterize and categorize the actual level of safety performance of specific NPP, integrating all the substantial elements for assessing the safety performance. In consideration of particular regulatory environment in Korea, the integrated safety performance assessment (ISPA) program is being under development for the use in the determination of safety performance grade (SPG) of a NPP. The ISPA program consists of 6 individual assessment programs (4 quantitative and 2 qualitative) which cover the overall safety performance of NPP. Some of the assessment programs which are already implemented are used directly or modified for incorporating risk aspects. The others which are not existing regulatory programs are newly developed. Eventually, all the assessment results from individual assessment programs are produced and integrated to determine the safety performance grade of a specific NPP

  12. Field performance of Quercus bicolor established as repeatedly air-root-pruned container and bareroot planting stock

    Science.gov (United States)

    J.W." Jerry" Van Sambeek; Larry D. Godsey; William D. Walter; Harold E. Garrett; John P. Dwyer

    2016-01-01

    Benefits of repeated air-root-pruning of seedlings when stepping up to progressively larger containers include excellent lateral root distribution immediately below the root collar and an exceptionally fibrous root ball. To evaluate long-term field performance of repeatedly air-root-pruned container stock, three plantings of swamp white oak (Quercus bicolor...

  13. Performance Assessment of Communication Enhancement Devices TEA HI Threat Headset

    Science.gov (United States)

    2015-08-01

    AFRL-RH-WP-TR-2015-0076 Performance Assessment of Communication Enhancement Devices: TEA HI Threat Headset Hilary L. Gallagher...of Communication Enhancement Devices: TEA HI Threat Headset 5a. CONTRACT NUMBER FA8650-14-D-6501 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER...technology in military applications. Objective performance data provided an assessment of the performance of these devices. The TEA HI Threat headset

  14. Performance of solid state supercapacitors based on polymer electrolytes containing different ionic liquids

    Science.gov (United States)

    Tiruye, Girum Ayalneh; Muñoz-Torrero, David; Palma, Jesus; Anderson, Marc; Marcilla, Rebeca

    2016-09-01

    Four Ionic Liquid based Polymer Electrolytes (IL-b-PE) were prepared by blending a Polymeric Ionic Liquid, Poly(diallyldimethylammonium) bis(trifluoromethanesulfonyl)imide (PILTFSI), with four different ionic liquids: 1-butyl-1-methylpyrrolidinium bis(trifluoromethanesulfonyl)imide (PYR14TFSI) (IL-b-PE1), 1-butyl-1-methylpyrrolidinium bis(fluorosulfonyl)imide (PYR14FSI) (IL-b-PE2), 1-(2-hydroxy ethyl)-3-methylimidazolium bis(trifluoromethylsulfonyl)imide (HEMimTFSI) (IL-b-PE3), and 1-Butyl-1-methylpyrrolidinium dicyanamide, (PYR14DCA) (IL-b-PE4). Physicochemical properties of IL-b-PE such as ionic conductivity, thermal and electrochemical stability were found to be dependent on the IL properties. For instance, ionic conductivity was significantly higher for IL-b-PE2 and IL-b-PE4 containing IL with small size anions (FSI and DCA) than IL-b-PE1 and IL-b-PE3 bearing IL with bigger anion (TFSI). On the other hand, wider electrochemical stability window (ESW) was found for IL-b-PE1 and IL-b-PE2 having ILs with electrochemically stable pyrrolidinium cation and FSI and TFSI anions. Solid state Supercapacitors (SCs) were assembled with activated carbon electrodes and their electrochemical performance was correlated with the polymer electrolyte properties. Best performance was obtained with SC having IL-b-PE2 that exhibited a good compromise between ionic conductivity and electrochemical window. Specific capacitance (Cam), real energy (Ereal) & real power densities (Preal) as high as 150 F g-1, 36 Wh kg-1 & 1170 W kg-1 were found at operating voltage of 3.5 V.

  15. Performance of japanese quails fed feeds containing different corn and limestone particle sizes

    Directory of Open Access Journals (Sweden)

    DA Berto

    2007-09-01

    Full Text Available This study aimed at evaluating performance and egg quality of Japanese quails fed feeds containing different corn and limestone particle sizes. A total number of 648 birds in the peak of production was distributed in a random complete block experimental design, using a 2x3 factorial arrangement (2 corn particle sizes and 3 limestone particle sizes. Birds were designated to one of two blocks, with six replicates of 18 birds each. Mean geometric diameter (MGD values used were 0.617mm and 0.723mm (corn fine and coarse particle sizes, respectively, and 0.361mm, 0.721mm, and 0.947mm (limestone fine, intermediate and coarse particle sizes, respectively. The following treatments were applied: T1: fine corn feed, with 100% fine limestone; T2: fine corn feed, with 50% fine limestone and 50% intermediate limestone; T3: fine corn feed, with 50% fine limestone and 50% coarse limestone; T4: coarse corn feed, with 100% fine limestone; T5: coarse corn feed, with 50% fine limestone and 50% intermediate limestone; T6: coarse corn feed, with 50% fine limestone and 50% coarse limestone. The experiment lasted 112 days, consisting of 4 cycles of 28 days. No significant interaction was observed among corn and limestone particle sizes for any of the analyzed parameters. There were no significant effects (p>0.05 of the tested corn particle sizes on quail performance or egg quality. There were significant (p<0.05 isolated effects of limestone particle size only on the percentage of cracked eggs, which was reduced when birds fed 50% coarse limestone (0.947mm and 50% fine limestone (0.361mm as compared to those fed 100% fine limestone. Therefore, the inclusion of 50% coarse limestone (0.947mm is recommended for quail egg production.

  16. Asymmetric Membranes Containing Micron-Size Silicon for High Performance Lithium Ion Battery Anode

    International Nuclear Information System (INIS)

    Byrd, Ian; Wu, Ji

    2016-01-01

    Micron-size Si anode is notorious for having extremely poor cycle life. It is mainly caused by the large volume change (∼300%) and poor mechanical strength of the Si electrode. Satisfying methods to address this issue are seriously lacking in literature. In this study, novel single-layer, double-layer and triple-layer asymmetric membranes containing micron-size silicon have been fabricated using a simple phase inversion method to dramatically improve its cyclability. The electrochemical performance of these asymmetric membranes as lithium ion battery anodes are evaluated and compared to pure micron-size Si powders and carbonaceous asymmetric membranes. All three types of asymmetric membrane electrodes demonstrate significantly enhanced stability as compared to pure Si powders. The single-layer asymmetric membrane has the largest capacity degradation due to the loss of pulverized Si powders from the membrane surface, only 40% of whose capacity can be retained in 100 cycles. But this performance is still much better than pure micron-size silicon electrode. After being coated with nanoporous carbonaceous layers on both sides of a single-layer asymmetric membrane to make a triple-layer asymmetric membrane (sandwich structure), the capacity retention is notably increased to 88% in 100 cycles at 610 mAh g"−"1 and 0.5C. The enhanced stability is attributed to the extra nanoporous coatings that can prevent the fractured Si powders from being leached out and allow facile lithium ion diffusions. Such a novel, efficient and scalable method may provide beneficiary guidance for designing high capacity lithium ion battery anodes with large volume change issues.

  17. Scientific investigation plan for NNWSI WBS element 1.2.2.5.L: NNWSI waste package performance assessment: Revision 1

    International Nuclear Information System (INIS)

    Eggert, K.G.; O'Connell, W.J.; Lappa, D.A.

    1986-01-01

    Waste package performance assessment contains three broad categories of activities. These activities are: (1) development of a hydrothermal flow and transport model to test concepts to be used in establishing boundary conditions for performance calculations, and to interface EBS release calculations with total system performance calculations; (2) development of a waste package systems model to provide integrated deterministic assessments of performance and analyses of waste package designs; and (3) development of an uncertainty methodology for combination with the system model to perform probabilistic reliability and performance analysis waste package designs. The first category contains activities that aid in determining the scope of a separate, simplified set of hydrologic calculations needed to characterize the waste package environment for performance assessment calculations. The last two activity categories are directly concerned with waste package performance calculations. A rationale for each activity under these groups is presented. All of the activities of performance assessment are either code development or analyses of waste package problems

  18. Phase II test plan for the evaluation of the performance of container filling systems

    International Nuclear Information System (INIS)

    BOGER, R.M.

    1999-01-01

    The PHMC will provide tank wastes for final treatment by BNFL from Hanford's waste tanks. Concerns about the ability for ''grab'' sampling to provide large volumes of representative waste samples has led to the development of a nested, fixed-depth sampling system. Preferred concepts for filling sample containers that meet RCRA organic sample criteria were identified by a PHMC Decision Board. These systems will replace the needle based sampling ''T'' that is currently on the sampling system. This test plan document identifies cold tests with simulants that will demonstrate the preferred bottle filling concepts abilities to provide representative waste samples and will meet RCRA criteria. Additional tests are identified that evaluate the potential for cross-contamination between samples and the ability for the system to decontaminate surfaces which have contacted tank wastes. These tests will be performed with kaolidwater and sand/water slurry simulants in the test rig that was used by AEAT to complete Phase 1 tests in FY 1999

  19. Intake, digestibility and performance of lambs fed diets containing peach palm meal.

    Science.gov (United States)

    dos Santos, Alana Batista; Pereira, Mara Lúcia Albuquerque; de Oliveira Silva, Herymá Giovane; de Carvalho, Gleidson Giordano Pinto; de Jesus Pereira, Taiala Cristina; Ribeiro, Leandro Sampaio Oliveira; Azevêdo, José Augusto Gomes; das Graças Conceição Parada Costa Silva, Maria; Sousa, Larisse Borges; Sousa, Leandro Borges; de Oliveira Alencar, Daiane

    2016-03-01

    The aim of this study was to evaluate the intake and apparent digestibility of nutrients, performance, and plasma glucose concentration of ram lambs fed diets containing peach palm meal substituting maize (0, 10, 40, 60, and 85 % dry matter (DM)). Thirty Santa Inês rams with an average initial body weight of 21.6 ± 0.87 kg were distributed in a completely randomized design with five diets and six replicates. The substitution of the maize for the peach palm meal affected (P < 0.05) the intakes of DM, organic matter (OM), crude protein (CP), neutral detergent fiber corrected for ash and protein (NDFap), total carbohydrates (TC), total digestible nutrients (TDN), and metabolizable energy (ME), which decreased linearly (P < 0.05); the intake of ether extract (EE), however, fit an increasing linear equation (P < 0.05). The apparent digestibility coefficients of DM, OM, NDFap, and TC decreased linearly (P < 0.05) as the level of peach palm meal in the concentrate was increased. The total weight gain and the average daily gain decreased by 0.09 and 0.001 kg with each level of substitution of the maize for peach palm meal, respectively. It is recommended to substitute 40 % of the maize for peach palm meal.

  20. Mechanical Properties of High Performance Concrete Containing Waste Plastic as Aggregate

    Directory of Open Access Journals (Sweden)

    Abdulkader Ismail Al-Hadithi

    2015-08-01

    Full Text Available The world's population growth and the increasing demand for new infrastructure facilities and buildings , present us with the vision of a higher resources consumption, specially in the form of more durable concrete such as High Performance Concrete (HPC . Moreover , the growth of the world pollution by plastic waste has been tremendous. The aim of this research is to investigate the change in mechanical properties of HPC with added waste plastics in concrete. For this purpose 2.5%, 5% and 7.5% in volume of natural fine aggregate in the HPC mixes were replaced by an equal volume of Polyethylene Terephthalate (PET waste , got by shredded PET bottles. The mechanical properties (compressive, splitting tensile, and flexural strength evaluated at the ages of (7 ,28, 56 and 91 days while the static modulus of elasticity tested at (28 and 91 days . The results indicated that HPC containing PET-aggregate presented lower compressive strength and static elasticity . The splitting strength displayed an arising trend at the initial stages, however, they have a tendency to decrease after a while. On the other hand, flexural strength results gave better modulus of rapture at all ages of curing , as compared with reference concrete specimens.

  1. Caffeine-containing energy drink improves physical performance of elite rugby players during a simulated match.

    Science.gov (United States)

    Del Coso, Juan; Ramírez, Juan A; Muñoz, Gloria; Portillo, Javier; Gonzalez-Millán, Cristina; Muñoz, Víctor; Barbero-Álvarez, José C; Muñoz-Guerra, Jesús

    2013-04-01

    The purpose of this study was to investigate the effectiveness of a caffeine-containing energy drink in enhancing rugby players' physical performance during a simulated match. A second purpose was to determine the urinary caffeine excretion derived from the energy drink intake. In a randomized and counterbalanced order, 26 elite rugby players (mean ± SD for age and body mass, 25 ± 2 y and 93 ± 15 kg) played 2 simulated rugby games (2 × 30 min) 60 min after ingesting (i) 3 mg of caffeine per kilogram of body mass in the form of an energy drink (Fure, ProEnergetics) or (ii) the same drink without caffeine (placebo). During the matches, the individual running distance and the instantaneous speed were measured, and the number of running actions above 20 km·h(-1) (i.e., sprints) were determined, using global positioning system devices. The number of impacts above 5 g during the matches was determined by accelerometry. The ingestion of the energy drink, compared with the placebo, increased the total distance covered during the match (4749 ± 589 vs 5139 ± 475 m, p caffeine concentration (0.1 ± 0.1 vs 2.4 ± 0.9 μg·mL(-1), p caffeine dose equivalent to 3 mg·kg(-1) considerably enhanced the movement patterns of rugby players during a simulated match.

  2. On the estimation of bias in post-closure performance assessment of underground radioactive waste disposal

    International Nuclear Information System (INIS)

    Thompson, B.G.J.; Gralewski, Z.A.; Grindrod, P.

    1995-01-01

    This paper proposes a systematic method for recording and evaluating bias in performance assessments for underground radioactive waste disposal facilities. The bias estimation approach comprises three principal components: (1) creation of a relational database containing historical assumptions and decisions made during the assessment, (2) investigation of the impact of some identified sources of internal bias through alternative assessment calculations, and (3) investigation of the impact of some identified sources of external bias by estimating degrees of belief probability. Bias corrections may help avoid unnecessary concerns by explaining and scoping the impacts of principal differences without the need to undertake additional site investigation, research, and performance analysis

  3. The Empirical Testing of a Musical Performance Assessment Paradigm

    Science.gov (United States)

    Russell, Brian E.

    2010-01-01

    The purpose of this study was to test a hypothesized model of aurally perceived performer-controlled musical factors that influence assessments of performance quality. Previous research studies on musical performance constructs, musical achievement, musical expression, and scale construction were examined to identify the factors that influence…

  4. Digestion, growth performance and caecal fermentation in growing rabbits fed diets containing foliage of browse trees

    Directory of Open Access Journals (Sweden)

    S.H. Abu Hafsa

    2016-12-01

    Full Text Available This study aimed to evaluate the effect of feeding dried foliage (leaves and petioles of Acacia saligna, Leucaena leucocephala or Moringa oleifera on the performance, digestibility, N utilisation, caecal fermentation and microbial profiles in New Zealand White (NZW rabbits. One hundred weaned male NZW rabbits weighing 819.2±16.6 g and aged 35±1 d were randomly allocated into 4 groups of 25 rabbits each. Rabbits were fed on pelleted diets containing 70% concentrate mixture and 30% Egyptian berseem (Trifolium alexandrinum hay (Control diet or one of the other 3 experimental diets, where 50% of berseem hay was replaced with A. saligna (AS, L. leucocephala (LL or M. oleifera (MO. Compared to Control diet, decreases in dry matter (DM; P=0.004, organic matter (P=0.028, crude protein (CP; P=0.001, neutral detergent fibre (P=0.033 and acid detergent fibre (P=0.011 digestibility were observed with the AS diet. However, DM and CP digestibility were increased by 3% with the MO diet, and N utilisation was decreased (P<0.05 with AS. Rabbits fed AS and LL diets showed decreased (P=0.001 average daily gain by 39 and 7%, respectively vs. Control. Feed conversion was similar in Control and MO rabbits, whereas rabbits fed AS diet ate up to 45% more feed (P=0.002 than Control rabbits to gain one kg of body weight. Caecal ammonia-N was increased (P=0.002 with LL, while acetic acid was decreased (P=0.001 with AS diet vs. other treatments. Caecal E. coli and Lactobacillus spp. bacteria counts were decreased with MO by about 44 and 51%, respectively, vs. Control. In conclusion, under the study conditions, tree foliage from M. oleifera and L. leucocephala are suitable fibrous ingredients to be included up to 150 g/kg in the diets of growing rabbits, and can safely replace 50% of berseem hay in diets of NZW rabbits without any adverse effect on their growth performance. Foliage from M. oleifera had a better potential as a feed for rabbits than that from L

  5. The Advanced Monitoring Systems Initiative--Performance Monitoring for DOE Environmental Remediation and Contaminant Containment

    Science.gov (United States)

    Haas, W. J.; Venedam, R. J.; Lohrstorfer, C. F.; Weeks, S. J.

    2005-05-01

    The Advanced Monitoring System Initiative (AMSI) is a new approach to accelerate the development and application of advanced sensors and monitoring systems in support of Department of Energy needs in monitoring the performance of environmental remediation and contaminant containment activities. The Nevada Site Office of the National Nuclear Security Administration (NNSA) and Bechtel Nevada manage AMSI, with funding provided by the DOE Office of Environmental Management (DOE EM). AMSI has easy access to unique facilities and capabilities available at the Nevada Test Site (NTS), including the Hazardous Materials (HazMat) Spill Center, a one-of-a-kind facility built and permitted for releases of hazardous materials for training purposes, field-test detection, plume dispersion experimentation, and equipment and materials testing under controlled conditions. AMSI also has easy access to the facilities and considerable capabilities of the DOE and NNSA National Laboratories, the Special Technologies Laboratory, Remote Sensing Laboratory, Desert Research Institute, and Nevada Universities. AMSI provides rapid prototyping, systems integration, and field-testing, including assistance during initial site deployment. The emphasis is on application. Important features of the AMSI approach are: (1) customer investment, involvement and commitment to use - including definition of needs, desired mode of operation, and performance requirements; and (2) employment of a complete systems engineering approach, which allows the developer to focus maximum attention on the essential new sensing element or elements while AMSI assumes principal responsibility for infrastructure support elements such as power, packaging, and general data acquisition, control, communication, visualization and analysis software for support of decisions. This presentation describes: (1) the needs for sensors and performance monitoring for environmental systems as seen by the DOE Long Term Stewardship Science and

  6. Use of individual containers for prostate biopsy samples: Do we gain diagnostic performance?

    Science.gov (United States)

    Panach-Navarrete, J; García-Morata, F; Valls-González, L; Martínez-Jabaloyas, J M

    2016-05-01

    Prostate cores from transrectal biopsies are usually sent in separate vials for pathological processing. Although this is a common practice, there are controversial studies on its usefulness. We wanted to compare the rate of prostate cancer diagnosis between processing samples in 2 containers and processing them in individual containers to see if there are differences. Our secondary objective was to check the rate of diagnosis of various tumour subtypes in each of the 2 groups. A retrospective observational study was conducted of 2,601 cases of prostate biopsies. Ten cores were extracted in each biopsy. We divided the sample into 2 groups: biopsies sent in 2 containers to the department of pathology (left and right lobes) or sent in 10 (one for each cylinder), according to the different criteria used in our centre in the past. We then classified the cases according to the absence of neoplasia, insignificant tumour (involvement of just 1 cylinder, container group, and 824 were included in the 10-container group. We diagnosed a rate of 32.4% of cancers in the 2-container group and 40% in the 10-container group, a difference that was statistically significant (Pcontainer group than in the 10-container group (6.4% vs. 4.3%, respectively; P=.03). Samples with a Gleason score of 6 were diagnosed more often in the 10-container group than in the 2-container group (11.9% vs. 8.1%, respectively; P=.002). The same occurred with the Gleason score≥7 (23.8% in the 10-container group vs. 17.9% in the 2-container group; Pcontainers. Once the procedure was conducted, we also observed in our series a reduction in the diagnoses of insignificant carcinoma to the detriment of an increased diagnosis of not insignificant carcinomas. Copyright © 2015 AEU. Publicado por Elsevier España, S.L.U. All rights reserved.

  7. How Do States Integrate Performance Assessment in Their Systems of Assessment?

    Science.gov (United States)

    Stosich, Elizabeth Leisy; Snyder, Jon; Wilczak, Katie

    2018-01-01

    This paper reviews state strategies for incorporating performance assessment in policy and practice. Specifically, the paper reviews the use of performance assessment in 12 states in the Innovation Lab Network, a group committed to developing systems of assessment that provide meaningful measures of college and career readiness. This review…

  8. Performance assessment for low-level radioactive waste disposal

    International Nuclear Information System (INIS)

    Cook, J.R.; Hsu, R.H.; Wilhite, E.L.; Yu, A.D.

    1996-01-01

    In October 1994 the Savannah River Site became the first US DOE complex to use concrete vaults to dispose of low-level radioactive solid waste and better prevent soil and groundwater contamination. This article describes the design and gives a performance assessment of the vaults. Topics include the following: Performance objectives; scope; the performance assessment process-assemble a multidisciplinary working group; collect available data; define credible pathways/scenarios; develop conceptual models; conduct screening and detailed model calculations; assess sensitivity/uncertainty; integrate and interpret results; report. 9 figs., 3 tabs

  9. Performance assessment review for DOE LLW disposal facilities

    International Nuclear Information System (INIS)

    Wilhite, Elmer L.

    1992-01-01

    The United States Department of Energy (US DOE) disposes of low-level radioactive waste in near-surface disposal facilities. Safety of the disposal operations is evaluated for operational safety as well as long-term safety. Operational safety is evaluated based on the perceived level of hazard of the operation and may vary from a simple safety assessment to a safety analysis report. Long-term safety of all low-level waste disposal systems is evaluated through the conduct of a radiological performance assessment. The US DOE has established radiological performance objectives for disposal of low-level waste. They are to protect a member of the general public from receiving over 25 mrem/y, and an inadvertent intruder into the waste from receiving over 100 mrem/y continuous exposure or 500 mrem from a single exposure. For a disposal system to be acceptable, a performance assessment must be prepared which must be technically accurate and provide reasonable assurance that these performance objectives are met. Technical quality of the performance assessments is reviewed by a panel of experts. The panel of experts is used in two ways to assure the technical quality of performance assessment. A preliminary (generally 2 day) review by the panel is employed in the late stages of development to provide guidance on finalizing the performance assessment. The comments from this review are communicated to the personnel responsible for the performance assessment for consideration and incorporation. After finalizing the performance assessment, it is submitted for a formal review. The formal review is accomplished by a much more thorough analysis of the performance assessment over a multi-week time period. The panel then formally reports their recommendations to the US DOE waste management senior staff who make the final determination on acceptability of the performance assessment. A number of lessons have been learned from conducting several preliminary reviews of performance

  10. Assessment Training Effects on Student Assessment Skills and Task Performance in a Technology-Facilitated Peer Assessment

    Science.gov (United States)

    Liu, Xiongyi; Li, Lan

    2014-01-01

    This study examines the impact of an assessment training module on student assessment skills and task performance in a technology-facilitated peer assessment. Seventy-eight undergraduate students participated in the study. The participants completed an assessment training exercise, prior to engaging in peer-assessment activities. During the…

  11. Ocean container transport : an underestimated and critical link in global supply chain performance

    NARCIS (Netherlands)

    Fransoo, J.C.; Lee, C.Y.

    2010-01-01

    With supply chains distributed across global markets, ocean container transport now is a critical element of any such supply chain. We identify key characteristics of ocean container transport from a supply chain perspective. We find that unlike continental (road) transport, service offerings tend

  12. The critical role of ocean container transport in global supply chain performance

    NARCIS (Netherlands)

    Fransoo, J.C.; Lee, C.Y.

    2013-01-01

    With supply chains distributed across global markets, ocean container transport now is a critical element of any such supply chain. We identify key characteristics of ocean container transport from a supply chain perspective. We find that unlike continental (road) transport, service offerings tend

  13. [Teaching performance assessment in Public Health employing three different strategies].

    Science.gov (United States)

    Martínez-González, Adrián; Moreno-Altamirano, Laura; Ponce-Rosas, Efrén Raúl; Martínez-Franco, Adrián Israel; Urrutia-Aguilar, María Esther

    2011-01-01

    The educational system depends upon the quality and performance of their faculty and should therefore be process of continuous improvement. To assess the teaching performance of the Public Health professors, at the Faculty of Medicine, UNAM through three strategies. Justification study. The evaluation was conducted under a mediational model through three strategies: students' opinion assessment, self-assessment and students' academic achievement. We applied descriptive statistics, Student t test, ANOVA and Pearson correlation. Twenty professors were evaluated from the Public Health department, representing 57% of all them who teach the subject. The professor's performance was highly valued self-assessment compared with assessment of student opinion, was confirmed by statistical analysis the difference was significant. The difference amongst the three evaluation strategies became more evident between self-assessment and the scores obtained by students in their academic achievement. The integration of these three strategies offers a more complete view of the teacher's performance quality. Academic achievement appears to be a more objective strategy for teaching performance assessment than students' opinion and self-assessment.

  14. Growth performance of African catfish (Clarias sp. juvenile fed on the diets containing various chromium content

    Directory of Open Access Journals (Sweden)

    H. Aryansyah

    2007-07-01

    Full Text Available This experiment was conducted to determine the effect of different dietary chromium level on the growth performance of catfish (Clarias sp. juvenile. Five experimental diets contain different chromium level, namely diet A (as a control diet 0.01; B 1.30; C 2.60; D 3.90 and E 5.20 mg/kg diet were used in this experiment. Fish with body weight of  5.57 ± 0.01 g/ind, fed on the experimental diet, twice a day, at satiation. Feeding trial was conducted for 60 days. Based on the evaluation of protein level of the whole body, protein and lipid retention, daily growth rate and feed efficiency, it was concluded that the optimum dietary chromium level for catfish  juvenile was 2.60 mg/kg diet. Keywords: chromium, growth, Clarias sp.   ABSTRAK Penelitian ini dilakukan untuk mengetahui pengaruh pemberian kromium dengan level berbeda terhadap pertumbuhan ikan lele (Clarias sp. juvenil.  Lima jenis pakan yang mengandung kromium berbeda, yaitu pakan A  (kontrol 0,01; B 1,30; C 2,60; D 3,90 dan pakan E 5,20 mg/kg digunakan dalam penelitian ini. Ikan dengan bobot 5,57 ± 0,01 g/ind., diberi pakan 2 kali sehari secara satiasi.  Pemeliharaan ikan dilakukan selama 60 hari.  Berdasarkan analisa retensi protein, kandungan protein dan retensi lemak dalam tubuh ikan lele, disimpulkan bahwa kadar kromium yang optimum untuk juvenil ikan lele adalah 2,60 mg/kg pakan. Kata kunci: kromium, pertumbuhan, Clarias sp.

  15. Feasibility assessment of copper-base waste package container materials in a tuff repository

    International Nuclear Information System (INIS)

    Acton, C.F.; McCright, R.D.

    1986-01-01

    This report discussed progress made during the second year of a two-year study on the feasibility of using copper or a copper-base alloy as a container material for a waste package in a potential repository in tuff rock at the Yucca Mountain site in Nevada. Corrosion testing in potentially corrosive irradiated environments received emphasis during the feasibility study. Results of experiments to evaluate the effect of a radiation field on the uniform corrosion rate of the copper-base materials in repository-relevant aqueous environments are given as well as results of an electrochemical study of the copper-base materials in normal and concentrated J-13 water. Results of tests on the irradiation of J-13 water and on the subsequent formation of hydrogen peroxide are given. A theoretical study was initiated to predict the long-term corrosion behavior of copper in the repository. Tests were conducted to determine whether copper would adversely affect release rates of radionuclides to the environment because of degradation of the Zircaloy cladding. A manufacturing survey to determine the feasibility of producing copper containers utilizing existing equipment and processes was completed. The cost and availability of copper was also evaluated and predicted to the year 2000. Results of this feasibility assessment are summarized

  16. Assessment of Prediction Capabilities of COCOSYS and CFX Code for Simplified Containment

    Directory of Open Access Journals (Sweden)

    Jia Zhu

    2016-01-01

    Full Text Available The acceptable accuracy for simulation of severe accident scenarios in containments of nuclear power plants is required to investigate the consequences of severe accidents and effectiveness of potential counter measures. For this purpose, the actual capability of CFX tool and COCOSYS code is assessed in prototypical geometries for simplified physical process-plume (due to a heat source under adiabatic and convection boundary condition, respectively. Results of the comparison under adiabatic boundary condition show that good agreement is obtained among the analytical solution, COCOSYS prediction, and CFX prediction for zone temperature. The general trend of the temperature distribution along the vertical direction predicted by COCOSYS agrees with the CFX prediction except in dome, and this phenomenon is predicted well by CFX and failed to be reproduced by COCOSYS. Both COCOSYS and CFX indicate that there is no temperature stratification inside dome. CFX prediction shows that temperature stratification area occurs beneath the dome and away from the heat source. Temperature stratification area under adiabatic boundary condition is bigger than that under convection boundary condition. The results indicate that the average temperature inside containment predicted with COCOSYS model is overestimated under adiabatic boundary condition, while it is underestimated under convection boundary condition compared to CFX prediction.

  17. Assessment of integrity of containment coating (Epoxy) using beta radiometry and NDT techniques

    International Nuclear Information System (INIS)

    Pujala, Usha; Sujatha, P.N.; Kumar, Amit; Menaka, M.; Subramanian, V.; Sriniyas, C.V.; Baskaran, R.; Venkataraman, B.; Preetha, R.; Kumar, J. Ashok

    2018-01-01

    The inner sides of walls of reactor containments and other fuel handling areas are coated with paint made of epoxy resins mainly for ease of decontamination and protecting rebar from corrosion environment. In addition, this gives the advantage in terms of ensuring additional leak tightness of reactor containment building (RCB) during the hypothetical Core Disruptive Accident (CDA) of Sodium Cooled Fast Reactors (SFR). During CDA, RCB will be bottled-up with sodium aerosols along with fuel and fission product aerosols. Sodium aerosols undergo chemical changes with progress of time to form hydroxide, carbonate and bicarbonate species upon reaction with atmospheric constituents. Of which, hydroxide aerosols are highly corrosive due to alkaline nature and it can cause damages to the epoxy coating. In this context, experiments have been conducted at ATF to assess the integrity of epoxy coating under the alkaline atmospheric conditions. Plywood, ordinary concrete and zinc plates are coated with epoxy paint and integrity of the coating is checked by exposing to sodium aerosols using beta radiometry technique (BRT), NDT techniques and gravimetric analysis. The results are presented in this paper

  18. Risk assessment on the use of herbal medicinal products containing pyrrolizidine alkaloids.

    Science.gov (United States)

    Allgaier, Clemens; Franz, Stephanie

    2015-11-01

    Pyrrolizidine alkaloids (PA) are common plantal toxins directed against insect herbivores. Unsaturated PAs are known to be hepatotoxic. Many of the PAs are in addition mutagenic and some may possibly be carcinogenic for humans. The risk of an exposure to PAs associated with their occurrence in herbal medicinal products and in foodstuff is under current discussion. The present risk assessment for herbal medicinal products containing PAs is based on a margin of safety derivation for foodstuff indicating that a life-long exposure to maximally 0.007 μg/kg bw/day is not expected to be associated with safety concerns. This approach offers a possibility to estimate the potential risk of PA-containing herbal medicinal products irrespective of the route of administration. It assumes PA levels in the final herbal medicinal product below 0.01 ppm and considers for dermal administration a 100% skin penetration of the PAs reflecting a worst-case scenario. As a result, the calculated margins of safety show a potential exposure using herbal medicinal products 70-, 45.5-, and 19.3-fold lower on a one-day base and 608-, 396-, and 168- fold lower on a one-year base for adults, children aged 12 years, and children aged 4 years, respectively, than the thresholds considered acceptable for foodstuff. Copyright © 2015 Elsevier Inc. All rights reserved.

  19. Hanford low-level tank waste interim performance assessment

    International Nuclear Information System (INIS)

    Mann, F.M.

    1997-01-01

    The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and performance early in the disposal system project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives

  20. Performance assessment for continuing and future operations at solid waste storage area 6

    International Nuclear Information System (INIS)

    1997-09-01

    This revised performance assessment (PA) for the continued disposal operations at Solid Waste Storage Area (SWSA) 6 on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the performance objectives for low-level radioactive waste (LLW) disposal contained in the US Department of Energy (DOE) Order 5820.2A. This revised PA considers disposal operations conducted from September 26, 1988, through the projects lifetime of the disposal facility

  1. Performance assessment for continuing and future operations at solid waste storage area 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This revised performance assessment (PA) for the continued disposal operations at Solid Waste Storage Area (SWSA) 6 on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the performance objectives for low-level radioactive waste (LLW) disposal contained in the US Department of Energy (DOE) Order 5820.2A. This revised PA considers disposal operations conducted from September 26, 1988, through the projects lifetime of the disposal facility.

  2. Performance and carcass characteristics of dairy steers fed diets containing crude glycerin

    Directory of Open Access Journals (Sweden)

    Raylon Pereira Maciel

    Full Text Available ABSTRACT The objective of the study was to assess the effects of including 0, 79.8, 159.8, and 240.0 g kg-1 crude glycerin in the total diet dry matter on the 84 days feedlot performance, nutrient digestibility, blood parameters, and carcass characteristics of crossbred dairy steers. Experimental diets were composed of 98.5 g kg-1 of sorghum silage and 901.5 g kg-1 of concentrate. Twenty-four crossbred dairy steers (337.3±39.8 kg body weight and 15 months of age were distributed in a completely randomized design with four treatments and six replicates. The intake and digestibility of the dry matter and nutrients were not altered by including crude glycerin in the diet. Crude glycerol levels did not affect the final weight (430.2 kg, daily weight gain (1.38 kg day-1, total weight gain (97.2 kg, hot carcass weight (218.9 kg, cold carcass weight (215.2 kg, hot carcass yield (0.50 kg 100 kg-1 BW, longissimus dorsi area (62.86 cm², subcutaneous fat thickness (4.05 mm, and carcass physical composition. Concentrations of serum glucose, triglycerides, total cholesterol, high-density lipoprotein cholesterol, and creatinine were not altered by including crude glycerin in the diet. Crude glycerin can be added to high concentrate diet up to 240 g kg-1 without changing the animal performance, apparent digestibility of nutrients, the main carcass characteristics, and blood parameters of finishing crossbred dairy steers.

  3. Performance and carcass characteristics of free-range broiler chickens fed diets containing alternative feedstuffs

    Directory of Open Access Journals (Sweden)

    PB Faria

    2011-09-01

    Full Text Available The present study was carried out to evaluate the effects of alternative feedstuffs as partial substitutes of corn and soybean in free-range broiler diets on performance, carcass yield and technical-economic viability. A total of 400 Pescoço Pelado broilers were distributed in a completely randomized experimental design (CRD, with four treatments (treatment 1:Control; treatment 2: 10% rice bran inclusion; treatment 3: 10% ground cassava leaves; and treatment 4: 10% ground lead tree hay with four replicates per treatment. Each replicate consisted of a group of 25 birds per paddock, separated per sex. Initial weight (IW, final weight (FW, body weight (BW, daily weight gain (DWG, feed intake (FI and feed conversion ratio (FCR were evaluated. Carcass, cuts (breast, thigh, drumstick, back, neck, leg and wings, abdominal fat and giblets (gizzard, heart and liver yields were determined. The technical-economic viability of each treatment was assessed by determining the cost of feed per kg body weight, economic efficiency index and cost. The highest final weights were obtained with the use of rice bran. Rice bran and cassava leaves promoted higher carcass yield, as well as lower back and abdominal fat yields. The use of cassava leaves showed better economic efficiency among the treatments with alternative feedstuffs. The use of alternative feedstuffs at 10% inclusion in substitution of corn and soybean meal did not not result in major changes in performance and carcass parameters, and economic efficiency, and therefore, their use is recommended when the availability or the price of key ingredients, such as soybean meal and corn, increase.

  4. performance assessment of substation site earthing using fluke ...

    African Journals Online (AJOL)

    2013-03-01

    Mar 1, 2013 ... Earthing is the fundamental requirement for protection in all electrical ... for the performance assessment of this instrument as compare to the conventional system. ... tem and the reference earth at a given operating fre- quency ...

  5. Organic migration forms of radionuclides and performance assessment

    International Nuclear Information System (INIS)

    Xu Gouqing

    2010-01-01

    Much attention is paid to inorganic migration forms of radionuclides in groundwater during performance assessment before and organic migration forms, are seldom noted. Therefore some question may come into confidence level in performance assessment. This paper mainly discusses the distribution of organic substances in groundwater and their potential effect on performance assessment. The results obtained in recent years show that clay rocks are generally impermeable to water, but in some cases the interstitial water may be observed in them and the concentration of DOC, HA and FA is rather higher than that in granitic groundwater. The concentration of DOC is relatively low in granitic groundwater, but up to now the effect of organic migration forms of radionuclides in granitic groundwater on performance assessment is not finally determined, it is necessary to make further investigations. (authors)

  6. economic assessment of the performance of private sector ...

    African Journals Online (AJOL)

    Admin

    Economic and Extension, Delta State University, Asaba Campus, Nigeria ... This paper critically attempts to assess the performance of the private sector ... economy would depend to a large extent on the quantity ..... New York, USA: McGraw.

  7. An assessment of organisational values, culture and performance in ...

    African Journals Online (AJOL)

    An assessment of organisational values, culture and performance in Cape Town's ... confusion, control, manipulation, blame, power, results orientation, hierarchy, ... Conclusion: The organisational culture of the Metro District Health Services is ...

  8. Performance analysis of a membrane humidifier containing porous metal foam as flow distributor in a PEM fuel cell system

    International Nuclear Information System (INIS)

    Afshari, Ebrahim; Baharlou Houreh, Nasser

    2014-01-01

    Highlights: • Three metal foam configurations for the membrane humidifier are introduced. • The performances of the humidifiers containing metal foam are investigated. • A 3D CFD model is developed to compare the introduced humidifiers with one another. • Using metal foam at dry side has no positive effect on the humidifier performance. - Abstract: Using metal foam as flow distributor in membrane humidifier for proton exchange membrane (PEM) fuel cell system has some unique characteristics like more water transfer, low manufacturing complexity and low cost compared to the conventional flow channel plate. Metal foam can be applied at wet side or dry side or both sides of a humidifier. The three-dimensional CFD models are developed to investigate the performance of the above mentioned meanwhile compare them with the conventional humidifier. This model consists of a set of coupled equations including conservations of mass, momentum, species and energy for all regions of the humidifier. The results indicate that with the metal foam installed at wet side and both sides, water recovery ratio and dew point at dry side outlet are more than that of the conventional humidifier, indicating a better humidifier performance; while using metal foam at dry side has no positive effect on humidifier performance. At dry side mass flow rates higher than 10 mgr/s pressure drop in humidifier containing metal foam at wet side is lower than that of the conventional humidifier. As the mass flow rate increases from 9 to 15 mgr/s humidifier containing metal foam at wet side has better performance, while at mass flow rates lower than 9 mgr/s, the humidifier containing metal foam at both sides has better performance. At dry side inlet temperatures lower than 303 K, humidifier containing metal foam at wet side has better performance and at temperatures higher than 303 K, humidifier containing metal foam at both sides has better performance

  9. ASSESSING INDIVIDUAL PERFORMANCE ON INFORMATION TECHNOLOGY ADOPTION: A NEW MODEL

    OpenAIRE

    Diah Hari Suryaningrum

    2012-01-01

    This paper aims to propose a new model in assessing individual performance on information technology adoption. The new model to assess individual performance was derived from two different theories: decomposed theory of planned behavior and task-technology fit theory. Although many researchers have tried to expand these theories, some of their efforts might lack of theoretical assumptions. To overcome this problem and enhance the coherence of the integration, I used a theory from social scien...

  10. Performance assessment for underground radioactive waste disposal systems

    International Nuclear Information System (INIS)

    1985-01-01

    A waste disposal system comprises a number of subsystems and components. The performance of most systems can be demonstrated only indirectly because of the long period that would be required to test them. This report gives special attention to performance assessment of subsystems within the total waste disposal system, and is an extension of an IAEA report on Safety Assessment for the Underground Disposal of Radioactive Wastes

  11. Preformed amide-containing biopolymer for improving the environmental performance of synthesized urea–formaldehyde in agro-fiber composites

    Science.gov (United States)

    Altaf H. Basta; Houssni El-Saied; Jerrold E. Winandy; Ronald Sabo

    2011-01-01

    Investigations have continued for production high performance agro-based composites using environmentally acceptable approaches. This study examines the role of adding amide-containing biopolymers during synthesis of urea–formaldehyde (UF) on properties of adhesive produced, especially its adhesion potential. The environmental performance of UF-resin synthesized in the...

  12. Assessment of the Biodegradability of Containers for Low and Intermediate Level Nuclear Waste

    International Nuclear Information System (INIS)

    Zlobenko, B.P.

    2013-01-01

    over a long-term period might have negative environmental consequences for the concretes waste containers as fungi (under certain environmental conditions) are able to dissolved the cement matrix resulting in the formation of a biofilm with accumulated structural elements. However, as microbial effects under repository conditions are unknown and difficult to study in a laboratory, no safety assessments conclusions can be made based on results from his study. Long term studies under repository conditions are needed. (author)

  13. Conceptual framework for performance assessment: competency, competence and performance in the context of assessments in healthcare--deciphering the terminology.

    Science.gov (United States)

    Khan, Kamran; Ramachandran, Sankaranarayanan

    2012-01-01

    The definitions of performance, competence and competency are not very clear in the literature. The assessment of performance and the selection of tools for this purpose depend upon a deep understanding of each of the above terms and the factors influencing performance. In this article, we distinguish between competence and competency and explain the relationship of competence and performance in the light of the Dreyfus model of skills acquisition. We briefly critique the application of the principles described by Miller to the modern assessment tools and distinguish between assessment of actual performance in workplace settings and the observed performance, demonstrated by the candidates in the workplace or simulated settings. We describe a modification of the Dreyfus model applicable to assessments in healthcare and propose a new model for the assessment of performance and performance rating scale (PRS) based on this model. We propose that the use of adapted versions of this PRS will result in benchmarking of performance and allowing the candidates to track their progression of skills in various areas of clinical practice.

  14. Performance and Cognitive Assessment in 3-D Modeling

    Science.gov (United States)

    Fahrer, Nolan E.; Ernst, Jeremy V.; Branoff, Theodore J.; Clark, Aaron C.

    2011-01-01

    The purpose of this study was to investigate identifiable differences between performance and cognitive assessment scores in a 3-D modeling unit of an engineering drafting course curriculum. The study aimed to provide further investigation of the need of skill-based assessments in engineering/technical graphics courses to potentially increase…

  15. Visual art teachers and performance assessment methods in ...

    African Journals Online (AJOL)

    This paper examines the competencies of visual arts teachers in using performance assessment methods, and to ascertain the extent to which the knowledge, skills and experiences of teachers affect their competence in using assessment strategies in their classroom. The study employs a qualitative research design; ...

  16. Data on Student Performance Under Different Forms of Assessment

    Science.gov (United States)

    King, Russell

    1976-01-01

    Recognition of various abilities and skills in university degree work, and the development of an appropriate range of assessment modes to test these abilities, presupposes that students will perform differently under the various forms of assessment. The limited data available to test this supposition are reviewed and analysis of one geography…

  17. Performance Assessment of the Masses in 30 Seconds or Less

    Science.gov (United States)

    Dunbar, Laura

    2012-01-01

    Performance assessment does not have to be a time-consuming ordeal; it is a great way to assess our students' skills. It is essential to create a rubric that is simple, quick, and objective. This article discusses the process of creating a rubric as well as showing a rubric used by the author in her general music classroom for several years.…

  18. An assessment of post-LOCA radiolytic generation of hydrogen in reactor containment of Indian PHWRs

    International Nuclear Information System (INIS)

    Bose, H.; Shah, G.C.; Dutta, S.

    2002-01-01

    Full text: An event-wise assessment has been carried out for the 220 MWe Indian PHWRs of standardized design, to estimate the post-LOCA release of radiolytic hydrogen inside reactor containment, in absence of steam-zirconium reaction. The assessment is based on (i) the dissolved hydrogen concentration build-up in water corresponding to the decaying gamma dose profile and (ii) the rate of concentration dependent mass-transfer of hydrogen from water to gas-space. It is observed that the total radiolytic hydrogen released is about three times less than that obtained by the conventional method of calculation which assumes the radiolytic yield of hydrogen to be equal to the primary yield G(H 2 ) = 0.44 molecules per 100 eV. It is also seen that a major part (∼90 %) of the total release is due to the spillage of fission product irradiated suppression pool water flowing through the core, followed by moderator and suppression pool surface releases respectively

  19. Containment performance analyses for the Advanced Neutron Source Reactor at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Kim, S.H.; Taleyarkhan, R.P.; Georgevich, V.

    1992-10-01

    This paper discusses salient aspects of methodology, assumptions, and modeling of various features related to estimation of source terms from two conservatively scoped severe accident scenarios in the Advanced Neutron Source (ANS) reactor at the Oak Ridge National Laboratory. Various containment configurations are considered for steaming-pool-type accidents and an accident involving molten core-concrete interaction. Several design features (such as rupture disks) are examined to study containment response during postulated severe accidents. Also, thermal-hydraulic response of the containment and radionuclide transport and retention in the containment are studied. The results are described as transient variations of source terms for each scenario, which are to be used for studying off-site radiological consequences and health effects for these postulated severe accidents. Also highlighted will be a comparison of source terms estimated by two different versions of the MELCOR code

  20. Self- and peer-assessments of ambulance drivers' driving performance

    Directory of Open Access Journals (Sweden)

    Anna Sundström

    2012-07-01

    Full Text Available The aim of the present study was to develop and examine the quality of the Ambulance Driver Self-assessment Questionnaire (ADSQ and the Ambulance Driver Peer-assessment Questionnaire (ADPQ measuring aspects of, driving performance, driving style and driving competence. In addition the ADSQ measures self-reflection and safety-attitudes. The aim of the study was also to examine ambulance drivers' self- and peer-assessments as well as to examine the accuracy of self-assessments by comparing self-assessed and peer-assessed driving performance, driving style and competence. 76 ambulance drivers employed at two ambulance stations in northern Sweden completed ADSQ and ADPQ. Item analyses were conducted to examine the psychometric properties of the items, and based on the results some revisions were made to improve the questionnaires. The revised questionnaires were functioning rather well, although some subscale demonstrated low internal consistency. Subscale inter-correlations provided support for construct validity. Self- and peer-assessments indicated safe driving performance and good driver competence, which is positive from a traffic safety perspective. A comparison of mean self- and peer-assessment ratings, controlling for age, gender and driving experience showed no significant differences, except for the subscale overtaking. This indicates that ambulance drivers' self-assessments are realistic in most areas.

  1. Performance Objective for Tank Farm Closure Risk Assessments

    International Nuclear Information System (INIS)

    MANN, F.M.; KNEPP, A.J.; BADDEN, J.

    2003-01-01

    To be meaningful, results from a numeric risk assessment of the consequences of an action must be compared against the standards for such an action. That is, before one disposes of waste or closes a facility with waste, one must show that the disposal or closure action protects the public health and safety and the environment. These standards are called performance objectives. Regulations requiring performing performance assessments, (whether federal ones like the Department of Energy [DOE] Order 435.1, Radioactive Waste Management and its implementing guides or Washington State ones like the regulations implementing the Washington Administrative Code [WAC] 173-340 ''Model Toxics Control Act - Cleanup''), usually require that the determination of performance objectives be one of the first steps performed. These performance objectives not only set comparison level for the numeric results, but also define the media, pathways, exposure scenarios (receptors), spatial locations, and times that the performance assessment must consider. Thus, a performance objective consists of a compliance level, place(s) of compliance, and time(s) of compliance. Performance objectives are not the levels that a regulatory agency will enforce in a permit or authorization. Those levels, often called enforcement levels, will be set in the permit or authorization. Rather, performance objectives are those levels against which the results of the numeric simulation will be compared to judge the success of the proposed cleanup or disposal actions. Additional comparison levels may be requested for information purposes, but are not officially part of the decision on the adequacy of the proposed action. To emphasize that the performance objectives discussed in this document are not regulatory performance objectives, the three components of the performance objective will be renamed in this document as assessment standard, point(s) of assessment, and time(s) of assessment. However, whenever

  2. Subjective and objective performance assessment : Performance pay at Trelleborg Forsheda AB

    OpenAIRE

    Luotonen, David; Hasselström, Markus

    2009-01-01

      The purpose of this thesis is to understand the opinions and potential effects of objective and subjective assessments of performance as a basis for performance pay for blue-collar workers. The study takes a qualitative approach to find out how and why four companies - Trelleborg Forsheda, Finnveden Powertrain, Isaberg Rapid and Parker Hannifin- work with salaries, incentive system and performance assessment the way they do. The concept of individual salary is central in this thesis, and in...

  3. 10 CFR 63.114 - Requirements for performance assessment.

    Science.gov (United States)

    2010-01-01

    ... processes of engineered barriers in the performance assessment, including those processes that would adversely affect the performance of natural barriers. Degradation, deterioration, or alteration processes of... surrounding region to the extent necessary, and information on the design of the engineered barrier system...

  4. The Concept of Performance Levels in Criterion-Referenced Assessment.

    Science.gov (United States)

    Hewitson, Mal

    The concept of performance levels in criterion-referenced assessment is explored by applying the idea to different types of tests commonly used in schools, mastery tests (including diagnostic tests) and achievement tests. In mastery tests, a threshold performance standard must be established for each criterion. Attainment of this threshold…

  5. The assessment and treatment of performance anxiety in musicians.

    Science.gov (United States)

    Clark, D B; Agras, W S

    1991-05-01

    Performance anxiety in musicians may be severe enough to require intervention but has been the subject of relatively little clinical research. The authors' objectives were to describe the results of a comprehensive clinical and laboratory assessment and to perform a double-blind, placebo-controlled study comparing buspirone, cognitive-behavior therapy, and the combination of these treatments for performance anxiety. Ninety-four subjects were recruited by mass media announcements and were seen in a university-based outpatient psychiatric clinic. Assessments were 1) questionnaires for all 94 subjects, 2) diagnostic interview of 50 subjects, and 3) laboratory performance of 34 subjects. Treatment conditions were 1) 6 weeks of buspirone, 2) 6 weeks of placebo, 3) a five-session, group cognitive-behavior therapy program with buspirone, or 4) the cognitive-behavior therapy program with placebo. Treatment outcome measures included subjective anxiety ratings and heart rate measures during a laboratory performance, a questionnaire measure of performance confidence, and a blind rating of musical performance quality. All subjects fulfilled criteria for DSM-III-R social phobia. Of the 15 full-time professional musicians, ten had tried propranolol and three had stopped performing. Most of the subjects had substantial anxiety and heart rate increases during laboratory speech and musical performances. Cognitive-behavior therapy resulted in statistically significant reductions in subjective anxiety, improved quality of musical performance, and improved performance confidence. Buspirone was not an effective treatment. Cognitive-behavior therapy is a viable treatment approach for performance anxiety in musicians.

  6. ANALYSING PERFORMANCE ASSESSMENT IN PUBLIC SERVICES: HOW USEFUL IS THE CONCEPT OF A PERFORMANCE REGIME?

    Science.gov (United States)

    Martin, Steve; Nutley, Sandra; Downe, James; Grace, Clive

    2016-03-01

    Approaches to performance assessment have been described as 'performance regimes', but there has been little analysis of what is meant by this concept and whether it has any real value. We draw on four perspectives on regimes - 'institutions and instruments', 'risk regulation regimes', 'internal logics and effects' and 'analytics of government' - to explore how the concept of a multi-dimensional regime can be applied to performance assessment in public services. We conclude that the concept is valuable. It helps to frame comparative and longitudinal analyses of approaches to performance assessment and draws attention to the ways in which public service performance regimes operate at different levels, how they change over time and what drives their development. Areas for future research include analysis of the impacts of performance regimes and interactions between their visible features (such as inspections, performance indicators and star ratings) and the veiled rationalities which underpin them.

  7. Performance assessment techniques for groundwater recovery and treatment systems

    Energy Technology Data Exchange (ETDEWEB)

    Kirkpatrick, G.L. [Environmental Resources Management, Inc., Exton, PA (United States)

    1993-03-01

    Groundwater recovery and treatment (pump and treat systems) continue to be the most commonly selected remedial technology for groundwater restoration and protection programs at hazardous waste sites and RCRA facilities nationwide. Implementing a typical groundwater recovery and treatment system includes the initial assessment of groundwater quality, characterizing aquifer hydrodynamics, recovery system design, system installation, testing, permitting, and operation and maintenance. This paper focuses on methods used to assess the long-term efficiency of a pump and treat system. Regulatory agencies and industry alike are sensitive to the need for accurate assessment of the performance and success of groundwater recovery systems for contaminant plume abatement and aquifer restoration. Several assessment methods are available to measure the long-term performance of a groundwater recovery system. This paper presents six assessment techniques: degree of compliance with regulatory agency agreement (Consent Order of Record of Decision), hydraulic demonstration of system performance, contaminant mass recovery calculation, system design and performance comparison, statistical evaluation of groundwater quality and preferably, integration of the assessment methods. Applying specific recovery system assessment methods depends upon the type, amount, and quality of data available. Use of an integrated approach is encouraged to evaluate the success of a groundwater recovery and treatment system. The methods presented in this paper are for engineers and corporate management to use when discussing the effectiveness of groundwater remediation systems with their environmental consultant. In addition, an independent (third party) system evaluation is recommended to be sure that a recovery system operates efficiently and with minimum expense.

  8. Machine performance assessment and enhancement for a hexapod machine

    Energy Technology Data Exchange (ETDEWEB)

    Mou, J.I. [Arizona State Univ., Tempe, AZ (United States); King, C. [Sandia National Labs., Livermore, CA (United States). Integrated Manufacturing Systems Center

    1998-03-19

    The focus of this study is to develop a sensor fused process modeling and control methodology to model, assess, and then enhance the performance of a hexapod machine for precision product realization. Deterministic modeling technique was used to derive models for machine performance assessment and enhancement. Sensor fusion methodology was adopted to identify the parameters of the derived models. Empirical models and computational algorithms were also derived and implemented to model, assess, and then enhance the machine performance. The developed sensor fusion algorithms can be implemented on a PC-based open architecture controller to receive information from various sensors, assess the status of the process, determine the proper action, and deliver the command to actuators for task execution. This will enhance a hexapod machine`s capability to produce workpieces within the imposed dimensional tolerances.

  9. Digestibility and performance of juvenile Nile tilapia fed with diets containing forage palm

    Directory of Open Access Journals (Sweden)

    Hannah Bandeira Thame Daniel

    2016-09-01

    Full Text Available Supplying the nutritional needs of animals in an economical way is essential to the success of any type of production. The forage palm is a cactaceae well-adapted to semiarid regions and commonly used in the feeding of ruminants. However, studies assessing its use in fishes are scarce. We aimed to evaluate the digestibility of bran from five different forage palm cultivars (Opuntia fícus in juvenile Nile tilapia and the development of juveniles when receiving increasing levels of the cultivar with the best apparent digestibility coefficient of crude protein (ADCCP (75.2%. We used 90 masculinized juvenile Nile tilapia (with an average weight of 6.02 ± 0.65 g in the digestibility experiment to determine the apparent digestibility coefficients of dry matter (ADCDM, crude energy (ADCCP, and crude protein of the cultivars (Orelha de onça, Miúda, Gigante, Comum, and IPA 20. The experimental design was completely randomized (CRD with five treatments and three repetitions. In the development experiment, 300 masculinized juvenile Nile tilapia (with average weight of 1.39 ± 0.12 g received feed with different inclusion levels (0, 72, 144, and 216 g Kg-1 of IPA 20 palm bran in a CRD with four treatments and five repetitions. We observed significant differences (P < 0.05 for ADCDM and ADCCP between the treatments. The cultivars that presented the highest ADCDM were IPA 20 (41.75%, Orelha de onça (36.41%, and Gigante (32.59%. For ADCCP, the best cultivar was IPA 20 with 75.2%, followed by Orelha de onça (61.5%, and Miúda (56.1%. As for the performance, the inclusion of IPA 20 palm bran at a rate of 113 g/kg-1 provided the best values in terms of weight gain and final weight in juvenile Nile tilapia.

  10. Incorrect Weighting of Absolute Performance in Self-Assessment

    Science.gov (United States)

    Jeffrey, Scott A.; Cozzarin, Brian

    Students spend much of their life in an attempt to assess their aptitude for numerous tasks. For example, they expend a great deal of effort to determine their academic standing given a distribution of grades. This research finds that students use their absolute performance, or percentage correct as a yardstick for their self-assessment, even when relative standing is much more informative. An experiment shows that this reliance on absolute performance for self-evaluation causes a misallocation of time and financial resources. Reasons for this inappropriate responsiveness to absolute performance are explored.

  11. Treatment of uncertainty in low-level waste performance assessment

    International Nuclear Information System (INIS)

    Kozak, M.W.; Olague, N.E.; Gallegos, D.P.; Rao, R.R.

    1991-01-01

    Uncertainties arise from a number of different sources in low-level waste performance assessment. In this paper the types of uncertainty are reviewed, and existing methods for quantifying and reducing each type of uncertainty are discussed. These approaches are examined in the context of the current low-level radioactive waste regulatory performance objectives, which are deterministic. The types of uncertainty discussed in this paper are model uncertainty, uncertainty about future conditions, and parameter uncertainty. The advantages and disadvantages of available methods for addressing uncertainty in low-level waste performance assessment are presented. 25 refs

  12. Performance Assessment for Pump-and-Treat Closure or Transition

    Energy Technology Data Exchange (ETDEWEB)

    Truex, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Johnson, Christian D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Becker, Dave J. [U.S. Army Corps of Engineers Environmental and Munitions Center of Expertise, Huntsville, AL (United States); Lee, Michelle H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Nimmons, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-09-29

    A structured performance assessment approach is useful to evaluate pump-and-treat (P&T) groundwater remediation, which has been applied at numerous sites. Consistent with the U.S. Environmental Protection Agency’s Groundwater Road Map, performance assessment during remedy implementation may be needed, and should consider remedy optimization, transition to alternative remedies, or remedy closure. In addition, a recent National Research Council study examined groundwater remediation at complex contaminated sites and concluded that it may be beneficial to evaluate remedy performance and the potential need for transition to alternative approaches at these sites. The intent of this document is to provide a structured approach for assessing P&T performance to support a decision to optimize, transition, or close a P&T remedy. The process presented in this document for gathering information and performing evaluations to support P&T remedy decisions includes use of decision elements to distinguish between potential outcomes of a remedy decision. Case studies are used to augment descriptions of decision elements and to illustrate each type of outcome identified in the performance assessment approach. The document provides references to resources for tools and other guidance relevant to conducting the P&T assessment.

  13. Assessment of a gel-type chelating preparation containing 1-hydroxyethylidene-1, 1-bisphosphonate.

    Science.gov (United States)

    Girard, S; Paqué, F; Badertscher, M; Sener, B; Zehnder, M

    2005-11-01

    To test an aqueous gel containing 1-hydroxyethylidene-1, 1-bisphosphonate (HEBP) regarding its interactions with sodium hypochlorite, its calcium binding capacity, and its potential in preventing the formation of a smear layer when used in conjunction with rotary root canal preparation. The experimental aqueous gel consisted of (w/v) 2% alginate, 3% aerosil, 10% Tween 80 and 18% HEBP. Interactions of gel components with hypochlorite were assessed using iodometric titration and monochromatic ultraviolet spectrometry. Two commercial paste-type chelators containing ethylenediaminetetraacetic acid (EDTA) and peroxide (RC-Prep and Glyde) served as controls. Calcium-binding capacities were measured in mixtures with a Ca2+ standard solution buffered at pH 10 using a calcium-selective measuring chain. Finally, root canals of 16 extracted single-rooted premolars per group were instrumented using ProFile instruments dipped in the experimental gel, RC-Prep, or nothing. Additionally, canals were rinsed with 10 mL of a 1% NaOCl solution during/after preparation. Smear scores in instrumented teeth were monitored using scanning electron microscopy. None of the experimental gel components showed short-term interactions with hypochlorite, whilst EDTA, peroxide, RC-Prep and Glyde immediately reduced the hypochlorite in solution. The experimental gel chelated 30 mg Ca2+ g-1, compared with 16 mg Ca2+ g-1 and 11 mg Ca2+ g-1 chelated by RC-Prep and Glyde respectively. Smear scores obtained with the experimental gel were significantly (P<0.05) lower than with RC-Prep in coronal and middle root thirds, whilst no differences were observed in apical root thirds. Under the conditions of this study, an HEBP gel appeared advantageous over currently available products.

  14. Performance Analysis of the Capability Assessment Tool for Sustainable Manufacturing

    Directory of Open Access Journals (Sweden)

    Enda Crossin

    2013-08-01

    Full Text Available This paper explores the performance of a novel capability assessment tool, developed to identify capability gaps and associated training and development requirements across the supply chain for environmentally-sustainable manufacturing. The tool was developed to assess 170 capabilities that have been clustered with respect to key areas of concern such as managing energy, water, material resources, carbon emissions and waste as well as environmental management practices for sustainability. Two independent expert teams used the tool to assess a sample group of five first and second tier sports apparel and footwear suppliers within the supply chain of a global sporting goods manufacturer in Asia. The paper addresses the reliability and robustness of the developed assessment method by formulating the expected links between the assessment results. The management practices of the participating suppliers were shown to be closely connected to their performance in managing their resources and emissions. The companies’ initiatives in implementing energy efficiency measures were found to be generally related to their performance in carbon emissions management. The suppliers were also asked to undertake a self-assessment by using a short questionnaire. The large gap between the comprehensive assessment and these in-house self-assessments revealed the suppliers’ misconceptions about their capabilities.

  15. Assessing performance and validating finite element simulations using probabilistic knowledge

    Energy Technology Data Exchange (ETDEWEB)

    Dolin, Ronald M.; Rodriguez, E. A. (Edward A.)

    2002-01-01

    Two probabilistic approaches for assessing performance are presented. The first approach assesses probability of failure by simultaneously modeling all likely events. The probability each event causes failure along with the event's likelihood of occurrence contribute to the overall probability of failure. The second assessment method is based on stochastic sampling using an influence diagram. Latin-hypercube sampling is used to stochastically assess events. The overall probability of failure is taken as the maximum probability of failure of all the events. The Likelihood of Occurrence simulation suggests failure does not occur while the Stochastic Sampling approach predicts failure. The Likelihood of Occurrence results are used to validate finite element predictions.

  16. Self-assessed performance improves statistical fusion of image labels

    International Nuclear Information System (INIS)

    Bryan, Frederick W.; Xu, Zhoubing; Asman, Andrew J.; Allen, Wade M.; Reich, Daniel S.; Landman, Bennett A.

    2014-01-01

    Purpose: Expert manual labeling is the gold standard for image segmentation, but this process is difficult, time-consuming, and prone to inter-individual differences. While fully automated methods have successfully targeted many anatomies, automated methods have not yet been developed for numerous essential structures (e.g., the internal structure of the spinal cord as seen on magnetic resonance imaging). Collaborative labeling is a new paradigm that offers a robust alternative that may realize both the throughput of automation and the guidance of experts. Yet, distributing manual labeling expertise across individuals and sites introduces potential human factors concerns (e.g., training, software usability) and statistical considerations (e.g., fusion of information, assessment of confidence, bias) that must be further explored. During the labeling process, it is simple to ask raters to self-assess the confidence of their labels, but this is rarely done and has not been previously quantitatively studied. Herein, the authors explore the utility of self-assessment in relation to automated assessment of rater performance in the context of statistical fusion. Methods: The authors conducted a study of 66 volumes manually labeled by 75 minimally trained human raters recruited from the university undergraduate population. Raters were given 15 min of training during which they were shown examples of correct segmentation, and the online segmentation tool was demonstrated. The volumes were labeled 2D slice-wise, and the slices were unordered. A self-assessed quality metric was produced by raters for each slice by marking a confidence bar superimposed on the slice. Volumes produced by both voting and statistical fusion algorithms were compared against a set of expert segmentations of the same volumes. Results: Labels for 8825 distinct slices were obtained. Simple majority voting resulted in statistically poorer performance than voting weighted by self-assessed performance

  17. Self-assessed performance improves statistical fusion of image labels

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, Frederick W., E-mail: frederick.w.bryan@vanderbilt.edu; Xu, Zhoubing; Asman, Andrew J.; Allen, Wade M. [Electrical Engineering, Vanderbilt University, Nashville, Tennessee 37235 (United States); Reich, Daniel S. [Translational Neuroradiology Unit, National Institute of Neurological Disorders and Stroke, National Institutes of Health, Bethesda, Maryland 20892 (United States); Landman, Bennett A. [Electrical Engineering, Vanderbilt University, Nashville, Tennessee 37235 (United States); Biomedical Engineering, Vanderbilt University, Nashville, Tennessee 37235 (United States); and Radiology and Radiological Sciences, Vanderbilt University, Nashville, Tennessee 37235 (United States)

    2014-03-15

    Purpose: Expert manual labeling is the gold standard for image segmentation, but this process is difficult, time-consuming, and prone to inter-individual differences. While fully automated methods have successfully targeted many anatomies, automated methods have not yet been developed for numerous essential structures (e.g., the internal structure of the spinal cord as seen on magnetic resonance imaging). Collaborative labeling is a new paradigm that offers a robust alternative that may realize both the throughput of automation and the guidance of experts. Yet, distributing manual labeling expertise across individuals and sites introduces potential human factors concerns (e.g., training, software usability) and statistical considerations (e.g., fusion of information, assessment of confidence, bias) that must be further explored. During the labeling process, it is simple to ask raters to self-assess the confidence of their labels, but this is rarely done and has not been previously quantitatively studied. Herein, the authors explore the utility of self-assessment in relation to automated assessment of rater performance in the context of statistical fusion. Methods: The authors conducted a study of 66 volumes manually labeled by 75 minimally trained human raters recruited from the university undergraduate population. Raters were given 15 min of training during which they were shown examples of correct segmentation, and the online segmentation tool was demonstrated. The volumes were labeled 2D slice-wise, and the slices were unordered. A self-assessed quality metric was produced by raters for each slice by marking a confidence bar superimposed on the slice. Volumes produced by both voting and statistical fusion algorithms were compared against a set of expert segmentations of the same volumes. Results: Labels for 8825 distinct slices were obtained. Simple majority voting resulted in statistically poorer performance than voting weighted by self-assessed performance

  18. Inherent N,O-containing carbon frameworks as electrode materials for high-performance supercapacitors.

    Science.gov (United States)

    Hu, Fangyuan; Wang, Jinyan; Hu, Shui; Li, Linfei; Wang, Gang; Qiu, Jieshan; Jian, Xigao

    2016-09-15

    N,O-Containing micropore-dominated materials have been developed successfully via temperature-dependent cross-linking of 4,4'-(dioxo-diphenyl-2,3,6,7-tetraazaanthracenediyl)dibenzonitrile (DPDN) monomers. By employing a molecular engineering strategy, we have designed and synthesized a series of porous heteroatom-containing carbon frameworks (PHCFs), in which nitrogen and oxygen heteroatoms are distributed homogeneously throughout the whole framework at the atomic level, which can ensure the stability of its electrical properties. The as-made PHCFs@550 exhibits a high specific capacitance of 378 F g -1 , with an excellent long cycling life, including excellent cycling stability (capacitance retention of ca. 120% over 20 000 cycles). Moreover, the successful preparation of PHCFs provides new insights for the fabrication of nitrogen and oxygen-containing electrode materials from readily available components via a facile route.

  19. Improving Performance of Cold-Chain Insulated Container with Phase Change Material: An Experimental Investigation

    Directory of Open Access Journals (Sweden)

    Li Huang

    2017-12-01

    Full Text Available The cold-chain transportation is an important means to ensure the drug and food safety. An cold-chain insulated container incorporating with Phase Change Material (PCM has been developed for a temperature-controlled transportation in the range of 2~8 °C. The container configuration and different preconditioning methods have been determined to realize a 72-h transportation under extremely high, extremely low, and alternating temperature conditions. The experimental results showed that the temperature-controlled time was extended from 1 h to more than 80 h and the internal temperature maintained at 4~5 °C by using a PCM with a melting/freezing point of 5 °C, while the container presented a subcooling effect in a range of −1~2 °C when using water as PCM. The experimental values of the temperature-controlled time agreed well with the theoretical values.

  20. Assessment of Student Music Performances Using Deep Neural Networks

    Directory of Open Access Journals (Sweden)

    Kumar Ashis Pati

    2018-03-01

    Full Text Available Music performance assessment is a highly subjective task often relying on experts to gauge both the technical and aesthetic aspects of the performance from the audio signal. This article explores the task of building computational models for music performance assessment, i.e., analyzing an audio recording of a performance and rating it along several criteria such as musicality, note accuracy, etc. Much of the earlier work in this area has been centered around using hand-crafted features intended to capture relevant aspects of a performance. However, such features are based on our limited understanding of music perception and may not be optimal. In this article, we propose using Deep Neural Networks (DNNs for the task and compare their performance against a baseline model using standard and hand-crafted features. We show that, using input representations at different levels of abstraction, DNNs can outperform the baseline models across all assessment criteria. In addition, we use model analysis techniques to further explain the model predictions in an attempt to gain useful insights into the assessment process. The results demonstrate the potential of using supervised feature learning techniques to better characterize music performances.