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Sample records for proposed technical basis

  1. TECHNICAL BASIS DOCUMENT FOR NATURAL EVENT HAZARDS

    International Nuclear Information System (INIS)

    KRIPPS, L.J.

    2006-01-01

    This technical basis document was developed to support the documented safety analysis (DSA) and describes the risk binning process and the technical basis for assigning risk bins for natural event hazard (NEH)-initiated accidents. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls

  2. TECHNICAL BASIS FOR VENTILATION REQUIREMENTS IN TANK FARMS OPERATING SPECIFICATIONS DOCUMENTS

    Energy Technology Data Exchange (ETDEWEB)

    BERGLIN, E J

    2003-06-23

    This report provides the technical basis for high efficiency particulate air filter (HEPA) for Hanford tank farm ventilation systems (sometimes known as heating, ventilation and air conditioning [HVAC]) to support limits defined in Process Engineering Operating Specification Documents (OSDs). This technical basis included a review of older technical basis and provides clarifications, as necessary, to technical basis limit revisions or justification. This document provides an updated technical basis for tank farm ventilation systems related to Operation Specification Documents (OSDs) for double-shell tanks (DSTs), single-shell tanks (SSTs), double-contained receiver tanks (DCRTs), catch tanks, and various other miscellaneous facilities.

  3. FLAMMABLE GAS TECHNICAL BASIS DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    KRIPPS, L.J.

    2005-03-03

    This document describes the qualitative evaluation of frequency and consequences for DST and SST representative flammable gas accidents and associated hazardous conditions without controls. The evaluation indicated that safety-significant structures, systems and components (SSCs) and/or technical safety requirements (TSRs) were required to prevent or mitigate flammable gas accidents. Discussion on the resulting control decisions is included. This technical basis document was developed to support WP-13033, Tank Farms Documented Safety Analysis (DSA), and describes the risk binning process for the flammable gas representative accidents and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous condition based on an evaluation of the event frequency and consequence.

  4. Technical basis document for natural event hazards

    International Nuclear Information System (INIS)

    CARSON, D.M.

    2003-01-01

    This technical basis document was developed to support the Tank Farms Documented Safety Analysis (DSA), and describes the risk binning process and the technical basis for assigning risk bins for natural event hazards (NEH)-initiated representative accident and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', as described in this report

  5. ITER technical basis

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-01-01

    Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties.

  6. ITER technical basis

    International Nuclear Information System (INIS)

    2002-01-01

    Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties

  7. Technical basis for tumbleweed survey requirements and disposal criteria

    International Nuclear Information System (INIS)

    J. D. Arana

    2000-01-01

    This technical basis document describes the technique for surveying potentially contaminated tumbleweeds in areas where the Environmental Restoration Contractor has jurisdiction and the disposal criteria based on these survey results. The report also discusses the statistical basis for surveys and the historical basis for the assumptions that are used to interpret the surveys

  8. Technical Basis for Tumbleweed Survey Requirements and Disposal Criteria

    International Nuclear Information System (INIS)

    Arana, J.D.

    2000-01-01

    This technical basis document describes the technique for surveying potentially contaminated tumbleweeds in areas where the Environmental Restoration Contractor has jurisdiction and the disposal criteria based on these survey results. The report also discusses the statistical basis for surveys and the historical basis for the assumptions that are used to interpret the surveys

  9. Technical basis document for external events

    International Nuclear Information System (INIS)

    OBERG, B.D.

    2003-01-01

    This document supports the Tank Farms Documented Safety Analysis and presents the technical basis for the FR-equencies of externally initiated accidents. The consequences of externally initiated events are discussed in other documents that correspond to the accident that was caused by the external event. The external events include aircraft crash, vehicle accident, range fire, and rail accident

  10. Internal dosimetry technical basis manual

    International Nuclear Information System (INIS)

    1990-01-01

    The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs

  11. Internal dosimetry technical basis manual

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-20

    The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs.

  12. FLAMMABLE GAS TECHNICAL BASIS DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    KRIPPS, L.J.

    2005-02-18

    This document describes the qualitative evaluation of frequency and consequences for double shell tank (DST) and single shell tank (SST) representative flammable gas accidents and associated hazardous conditions without controls. The evaluation indicated that safety-significant SSCs and/or TSRS were required to prevent or mitigate flammable gas accidents. Discussion on the resulting control decisions is included. This technical basis document was developed to support of the Tank Farms Documented Safety Analysis (DSA) and describes the risk binning process for the flammable gas representative accidents and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous condition based on an evaluation of the event frequency and consequence.

  13. Technical basis for the aboveground structure failure and associated represented hazardous conditions

    International Nuclear Information System (INIS)

    GOETZ, T.G.

    2003-01-01

    This technical basis document describes the risk binning process and the technical basis for assigning risk bins for the aboveground structure failure representative accident and associated represented hazardous conditions. This document was developed to support the documented safety analysis

  14. Technical basis and evaluation criteria for an air sampling/monitoring program

    International Nuclear Information System (INIS)

    Gregory, D.C.; Bryan, W.L.; Falter, K.G.

    1993-01-01

    Air sampling and monitoring programs at DOE facilities need to be reviewed in light of revised requirements and guidance found in, for example, DOE Order 5480.6 (RadCon Manual). Accordingly, the Oak Ridge National Laboratory (ORNL) air monitoring program is being revised and placed on a sound technical basis. A draft technical basis document has been written to establish placement criteria for instruments and to guide the ''retrospective sampling or real-time monitoring'' decision. Facility evaluations are being used to document air sampling/monitoring needs, and instruments are being evaluated in light of these needs. The steps used to develop this program and the technical basis for instrument placement are described

  15. ALWR utility requirements - A technical basis for updated emergency planning

    International Nuclear Information System (INIS)

    Leaver, David E.W.; DeVine, John C. Jr.; Santucci, Joseph

    2004-01-01

    U.S. utilities, with substantial support from international utilities, are developing a comprehensive set of design requirements in the form of a Utility Requirements Document (URD) as part of an industry wide effort to establish a technical foundation for the next generation of light water reactors. A key aspect of the URD is a set of severe accident-related design requirements which have been developed to provide a technical basis for updated emergency planning for the ALWR. The technical basis includes design criteria for containment performance and offsite dose during severe accident conditions. An ALWR emergency planning concept is being developed which reflects this severe accident capability. The main conclusion from this work is that the likelihood and consequences of a severe accident for an ALWR are fundamentally different from that assumed in the technical basis for existing emergency planning requirements, at least in the U.S. The current technical understanding of severe accident risk is greatly improved compared to that available when the existing U.S. emergency planning requirements were established nearly 15 years ago, and the emerging ALWR designs have superior core damage prevention and severe accident mitigation capability. Thus, it is reasonable and prudent to reflect this design capability in the emergency planning requirements for the ALWR. (author)

  16. Technical basis for the ITER-FEAT outline design

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-11-01

    This ITER EDA Documentation Series issue summarizes the results of the ITER Engineering Design Activities on the technical basis for the ITER-FEAT outline design. This issue also comprises some physical analysis activities as well as structure and goals of the Physics Expert Group activities.

  17. Technical basis for the ITER-FEAT outline design

    International Nuclear Information System (INIS)

    2000-01-01

    This ITER EDA Documentation Series issue summarizes the results of the ITER Engineering Design Activities on the technical basis for the ITER-FEAT outline design. This issue also comprises some physical analysis activities as well as structure and goals of the Physics Expert Group activities

  18. RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

    International Nuclear Information System (INIS)

    KOZLOWSKI, S.D.

    2007-01-01

    This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below

  19. Technical Basis for PNNL Beryllium Inventory

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, Michelle Lynn

    2014-07-09

    The Department of Energy (DOE) issued Title 10 of the Code of Federal Regulations Part 850, “Chronic Beryllium Disease Prevention Program” (the Beryllium Rule) in 1999 and required full compliance by no later than January 7, 2002. The Beryllium Rule requires the development of a baseline beryllium inventory of the locations of beryllium operations and other locations of potential beryllium contamination at DOE facilities. The baseline beryllium inventory is also required to identify workers exposed or potentially exposed to beryllium at those locations. Prior to DOE issuing 10 CFR 850, Pacific Northwest Nuclear Laboratory (PNNL) had documented the beryllium characterization and worker exposure potential for multiple facilities in compliance with DOE’s 1997 Notice 440.1, “Interim Chronic Beryllium Disease.” After DOE’s issuance of 10 CFR 850, PNNL developed an implementation plan to be compliant by 2002. In 2014, an internal self-assessment (ITS #E-00748) of PNNL’s Chronic Beryllium Disease Prevention Program (CBDPP) identified several deficiencies. One deficiency is that the technical basis for establishing the baseline beryllium inventory when the Beryllium Rule was implemented was either not documented or not retrievable. In addition, the beryllium inventory itself had not been adequately documented and maintained since PNNL established its own CBDPP, separate from Hanford Site’s program. This document reconstructs PNNL’s baseline beryllium inventory as it would have existed when it achieved compliance with the Beryllium Rule in 2001 and provides the technical basis for the baseline beryllium inventory.

  20. Technical Basis Document for PFP Area Monitoring Dosimetry Program

    CERN Document Server

    Cooper, J R

    2000-01-01

    This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual.

  1. Technical Basis Document for PFP Area Monitoring Dosimetry Program

    International Nuclear Information System (INIS)

    COOPER, J.R.

    2000-01-01

    This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual

  2. Mixing of incompatible materials in waste tanks technical basis document

    International Nuclear Information System (INIS)

    SANDGREN, K.R.

    2003-01-01

    This technical basis document was developed to support the Tank Farms Documented Safety Analysis (DSA) and describes the risk binning process, the technical basis for assigning risk bins, and the controls selected for the mixing of incompatible materials representative accident and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSCs) and/or technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the FR-equency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR level controls. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', as described in this report

  3. Technical Basis Document for PFP Area Monitoring Dosimetry Program

    Energy Technology Data Exchange (ETDEWEB)

    COOPER, J.R.

    2000-04-17

    This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual.

  4. Magnetic field calculations for the technical proposal of the TESLA spectrometer magnet

    International Nuclear Information System (INIS)

    Morozov, N.A.; Schreiber, H.J.

    2003-01-01

    The TESLA electron-positron linear collider is under consideration at DESY (Hamburg). The realization of the physical program at this collider requires the knowledge of the beam energy of both beams (e + and e - ) with a precision of ΔE/E ≤ 10 -4 . The magnetic spectrometer was proposed as an energy measuring device. The report describes calculations for the preliminary conceptual design of this type of the spectrometer. The 2D calculations of the magnetic field for the spectrometer magnet have been performed by POISSON SUPERFISH computer code. The basic technical parameters of the magnet have been determined. These data will serve as a basis for the technical design of the spectrometer magnet and discuss its integration in the spectrometer

  5. Technical basis for classification of low-activity waste fraction from Hanford site tanks

    Energy Technology Data Exchange (ETDEWEB)

    Petersen, C.A., Westinghouse Hanford

    1996-07-17

    The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level wastes, for disposal in a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

  6. Technical basis for classification of low-activity waste fraction from Hanford site tanks

    Energy Technology Data Exchange (ETDEWEB)

    Petersen, C.A.

    1996-09-20

    The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

  7. Technical Basis to Describe the Use of the Eberline E-600

    International Nuclear Information System (INIS)

    Brehm, D.M.

    1998-03-01

    This technical basis document describes the parameters and conditions under which the Eberline E-600 rate meter and the associated detectors can be operated to quantify ionizing radiation and radiological contamination

  8. Technical basis for removal of 221-T tunnel from airborne radiological area status

    International Nuclear Information System (INIS)

    Geuther, W.J.

    1996-01-01

    This document provides the technical basis for removal of the 221-T Tunnel from airborne radiological control. T Plant Radiological Control has evaluated air sampling data and engineering controls, and determined the necessary administrative controls to make this transition. With these administrative controls (specified within document) in place, the tunnel can be removed from Airborne Radioactive Area status. The removal of the tunnel from airborne status will allow work to be performed within the tunnel under controlled conditions, as outlined in this technical basis, without the use of respiratory protection equipment

  9. Flammable gas tank safety program: Technical basis for gas analysis and monitoring

    International Nuclear Information System (INIS)

    Estey, S.D.

    1998-01-01

    Several Hanford waste tanks have been observed to exhibit periodic releases of significant quantities of flammable gases. Because potential safety issues have been identified with this type of waste behavior, applicable tanks were equipped with instrumentation offering the capability to continuously monitor gases released from them. This document was written to cover three primary areas: (1) describe the current technical basis for requiring flammable gas monitoring, (2) update the technical basis to include knowledge gained from monitoring the tanks over the last three years, (3) provide the criteria for removal of Standard Hydrogen Monitoring System(s) (SHMS) from a waste tank or termination of other flammable gas monitoring activities in the Hanford Tank farms

  10. Technical Basis for Implementation of the PCM-1B for Personnel Release at Tank Farms

    International Nuclear Information System (INIS)

    BROWN, R.L.

    1999-01-01

    The purpose of this document is to define the technical basis and implementing guidelines for using automated personnel contamination monitors, such as the PCM-1B, at the River Protection Project (RPP) in lieu of performing a hand-held instrument followed by a PCM-1B survey for personnel release from contamination areas requiring a beta-gamma whole body survey. This document provides the basis for full implementation of the PCM-1B release survey, without the supplemental hand and foot survey, as currently implemented at RPP. This document applies only to RPP facilities. This document does not provide the technical basis for determining the equivalency of an automated system to hand-held instruments, or to the effective counting capability of automated systems as such technical determinations are contained in TBTN: GDGH-9604-RLS-0015

  11. Technical basis for internal dosimetry at Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

    1991-07-01

    The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ({sup 58}Co, {sup 60}Co, {sup 54}Mn, and {sup 59}Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs.

  12. Technical basis for internal dosimetry at Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

    1989-04-01

    The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products (/sup 58/Co, /sup 60/Co, /sup 54/Mn, and /sup 59/Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs.

  13. Technical basis for internal dosimetry at Hanford

    International Nuclear Information System (INIS)

    Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

    1991-07-01

    The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs

  14. Technical basis for internal dosimetry at Hanford

    International Nuclear Information System (INIS)

    Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

    1989-04-01

    The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs

  15. Technical basis for the internal dosimetry program at the Y-12 Plant

    International Nuclear Information System (INIS)

    Ashley, J.C.; Barber, J.M.; Snapp, L.M.; Turner, J.E.

    1992-01-01

    Since the beginning of plant operations. almost all work with radioactive materials has involved isotopes associated with uranium, enriched or depleted in U 235 . While limited quantities of isotopes of elements other than uranium are present, workplace monitoring and precess knowledge have established that internal exposure from these other isotopes is insignificant in comparison with uranium. While the changing plant mission may necessitate the consideration of internal exposure from other isotopes at some point in time, only enriched and depleted uranium will be considered in this basis document. The portions of the internal dosimetry technical basis which may be unique to the Y-12 Plant is considered in this manual. This manual presents the technical basis of the routine in vivo and in vitro bioassay programs including choice of frequency, participant selection criteria, and action level guidelines. Protocols for special bioassay will be presented in the chapters which described the basis for intake, uptake, and dam assessment. A discussion of the factors which led to the need to develop a special biokinetic model for uranium at the Y-12 Plant, as well as a description of the model's basic parameters, are included in this document

  16. Conceptual framework and technical basis for clearance of materials with residual radioactivity

    International Nuclear Information System (INIS)

    Chen, S.Y.

    1997-01-01

    The primary impediment to the release of materials containing residual radioactivity from a controlled environment is the lack of a suitable framework within which release standards can be developed. Recently, the 'risk-based' approach has been proposed as an appropriate means of setting standards. The term 'clearance' has been introduced by the International Atomic Energy Commission as a regulatory process for releasing radioactive materials posing trivial risks. A 'trivial' risk level has been determined to be on the order of 10[sup -6] to 10[sup -7] annual risk to an exposed individual, and a population risk of no more than 0.1 annually. Under these strict constraints, exposure scenarios may account for processing, disposal, and product end-use of materials. This paper discusses these scenarios and also describes the technical basis for deriving release levels under the suggested risk (or dose) constraints

  17. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

    International Nuclear Information System (INIS)

    Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

    1995-06-01

    The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report

  18. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B. [Mitre Corp., McLean, VA (United States)

    1995-06-01

    The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report.

  19. Technical basis document for internal dosimetry

    CERN Document Server

    Hickman, D P

    1991-01-01

    This document provides the technical basis for the Chem-Nuclear Geotech (Geotech) internal dosimetry program. Geotech policy describes the intentions of the company in complying with radiation protection standards and the as low as reasonably achievable (ALARA) program. It uses this policy and applicable protection standards to derive acceptable methods and levels of bioassay to assure compliance. The models and computational methods used are described in detail within this document. FR-om these models, dose- conversion factors and derived limits are computed. These computations are then verified using existing documentation and verification information or by demonstration of the calculations used to obtain the dose-conversion factors and derived limits. Recommendations for methods of optimizing the internal dosimetry program to provide effective monitoring and dose assessment for workers are provided in the last section of this document. This document is intended to be used in establishing an accredited dosi...

  20. TECHNICAL SUPPORT AS A BASIS OF HIGH AVAILABILITY LEVEL AND IT SYSTEM SERVICE QUALITY

    Directory of Open Access Journals (Sweden)

    Dejan Vidojevic

    2007-06-01

    Full Text Available This work presents the development and implementation methodology of technical support in IT1system operation. Methodology is developed and applied in realistic system (Information system of the Tax administration - DIS 2003, which is technically very complex and highly distributed. The results of IT system availability assessment and identification of the critical components are input parameters in the process of establishing of the technical support. The importance of technical support for achieving optimal IT system availability and IT service quality is assessed according to its operation during one year. The history of technical support system operation is a basis for further continuous improvement.

  1. Technical basis for the initiation and cessation of environmentally-assisted cracking of low-alloy steels in elevated temperature PWR environments

    International Nuclear Information System (INIS)

    James, L.A.

    1997-01-01

    The Section 11 Working Group on Flaw Evaluation of the ASME B and PV Code Committee is considering a Code Case to allow the determination of the conditions under which environmentally-assisted cracking of low-alloy steels could occur in PWR primary environments. This paper provides the technical support basis for such an EAC Initiation and Cessation Criterion by reviewing the theoretical and experimental information in support of the proposed Code Case

  2. Technical basis for the initiation and cessation of environmentally-assisted cracking of low-alloy steels in elevated temperature PWR environments

    Energy Technology Data Exchange (ETDEWEB)

    James, L.A.

    1997-10-01

    The Section 11 Working Group on Flaw Evaluation of the ASME B and PV Code Committee is considering a Code Case to allow the determination of the conditions under which environmentally-assisted cracking of low-alloy steels could occur in PWR primary environments. This paper provides the technical support basis for such an EAC Initiation and Cessation Criterion by reviewing the theoretical and experimental information in support of the proposed Code Case.

  3. 48 CFR 27.407 - Rights to technical data in successful proposals.

    Science.gov (United States)

    2010-10-01

    ... Copyrights 27.407 Rights to technical data in successful proposals. The clause at 52.227-23, Rights to... successful proposals. Pursuant to the clause, the prospective contractor is afforded the opportunity to... exclusion is not dispositive of the protective status of the data, but any excluded technical data, as well...

  4. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Executive summary: Volume 1

    International Nuclear Information System (INIS)

    Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

    1995-06-01

    The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer software used in the safety systems of nuclear power plants. The framework for the work consisted of the following software development and assurance activities: requirements specification; design; coding; verification and validation, including static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire range of software life-cycle activities; the assessment of the technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary, includes an overview of the framework and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; Volume 2 is the main report

  5. Technical Basis for Water Chemistry Control of IGSCC in Boiling Water Reactors

    Science.gov (United States)

    Gordon, Barry; Garcia, Susan

    Boiling water reactors (BWRs) operate with very high purity water. However, even the utilization of near theoretical conductivity water cannot prevent intergranular stress corrosion cracking (IGSCC) of sensitized stainless steel, wrought nickel alloys and nickel weld metals under oxygenated conditions. IGSCC can be further accelerated by the presence of certain impurities dissolved in the coolant. The goal of this paper is to present the technical basis for controlling various impurities under both oxygenated, i.e., normal water chemistry (NWC) and deoxygenated, i.e., hydrogen water chemistry (HWC) conditions for mitigation of IGSCC. More specifically, the effects of typical BWR ionic impurities (e.g., sulfate, chloride, nitrate, borate, phosphate, etc.) on IGSCC propensities in both NWC and HWC environments will be discussed. The technical basis for zinc addition to the BWR coolant will also provided along with an in-plant example of the most severe water chemistry transient to date.

  6. Technical Basis for Electromagnetic Compatibility Regulatory Guidance Update

    Energy Technology Data Exchange (ETDEWEB)

    Ewing, Paul D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Korsah, Kofi [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Harrison, Thomas J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wood, Richard Thomas [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Mays, Gary T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-03-01

    The objective of this report is to serve as the technical basis document for the next, planned revision of this RG that highlights and provides the rationale for the recommended changes. The structure of this document follows and summarizes the several assessment activities undertaken during the course of this project to evaluate new and updated electromagnetic compatibility (EMC) standards, testing methods and limits, and relevant technology developments being incorporated into plant activities that may have EMI/RFI implications, as well as other specific issues, including impacts of electrostatic discharge (ESD) on safety equipment and impacts on increased usage of wireless devices in nuclear power plants.

  7. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    International Nuclear Information System (INIS)

    Rathbone, Bruce A.

    2006-01-01

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL's Hanford External Dosimetry Program which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL's Electronic Records & Information Capture Architecture (ERICA) database

  8. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    Energy Technology Data Exchange (ETDEWEB)

    Rathbone, Bruce A.

    2005-02-25

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database.

  9. TECHNICAL BASIS DOCUMENT FOR AT-POWER SIGNIFICANCE DETERMINATION PROCESS (SDP) NOTEBOOKS

    International Nuclear Information System (INIS)

    AZARM, M.A.; SMANTA, P.K.; MARTINEZ-GURIDI, G.; HIGGINS, J.

    2004-01-01

    To support the assessment of inspection findings as part of the risk-informed inspection in the United States Nuclear Regulatory Commission's (USNRC's) Reactor Oversight Process (ROP), risk inspection notebooks, also called significance determination process (SDP) notebooks, have been developed for each of the operating plants in the United States. These notebooks serve as a tool for assessing risk significance of inspection findings along with providing an engineering understanding of the significance. Plant-specific notebooks are developed to capture plant-specific features, characteristics, and analyses that influence the risk profile of the plant. At the same time, the notebooks follow a consistent set of assumptions and guidelines to assure consistent treatment of inspection findings across the plants. To achieve these objectives, notebooks are designed to provide specific information that are unique both in the manner in which the information is provided and in the way the screening risk assessment is carried out using the information provided. The unique features of the SDP notebooks, the approaches used to present the information for assessment of inspection findings, the assumptions used in consistent modeling across different plants with due credit to plant-specific features and analyses form the technical basis of the SDP notebooks. In this document, the unique features and the technical basis for the notebooks are presented. The types of information that are included and the reasoning/basis for including that information are discussed. The rules and basis for developing the worksheets that are used by the inspectors in the assessment of inspection findings are presented. The approach to modeling plants' responses to different initiating events and specific assumptions/considerations used for each of the reactor types are also discussed

  10. Technical Basis - Spent Nuclear Fuels (SNF) Project Radiation and Contamination Trending Program

    International Nuclear Information System (INIS)

    ELGIN, J.C.

    2000-01-01

    This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, radiation surveys of the Cold Vacuum Drying Facility (CVD), and radiation surveys of the Canister Storage Building (CSB) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas

  11. Technical Basis Document (TBD) and user guides

    International Nuclear Information System (INIS)

    Chiaro, P.J. Jr.

    1998-09-01

    A Technical Basis Document (TBD) should provide the background information for establishment of an instrument's operational requirements. Due to the amount and location of DOE facilities, no one set of requirements is possible. Operational requirements will vary based on the local environments and missions at each facility. Environmental conditions that can affect an instrument's operations are ambient temperature, humidity, and radio frequency, and to a lesser extent, magnetic fields, and interfering ionizing radiations. Consideration should also be made regarding how an instrument is to be used. If an instrument will be transported around the facility, vibration and shock can cause problems if they are not addressed in the TBD. This document provides guidance for the development of a TBD. This document applies to radiation instruments used for personnel and equipment contamination monitoring, dose rate monitoring, and air monitoring

  12. Technical basis for exemption from alpha surveys for personnel, material, and equipment in the 324 facility

    International Nuclear Information System (INIS)

    RIDDELLE, J.G.

    1998-01-01

    The purpose of this document is to establish the technical basis for characterizing grouted B-Cell waste for disposal at the Hanford Burial Grounds using the 3-82B shipping cask. The scope of this document includes establishing the technical basis for loading the shipping package, an HN-200 Grout Container, to ensure that: (1) the amount of material in the grout container does not exceed the 100 nCl alpha/g limit that would cause the waste to be designated as ''greater that Category 3'' (GC3) or transuranic (TRU) waste (2) the amount of heat generated by the waste in the grout container does not exceed the 60 Watt heat generation limit established in the 3-82B shipping cask Safety Analysis Report (SAR); and (3) the dose rate on the surface of the shipping cask after loading does not exceed the 200 mrem/h limit established in the cask SAR. This document establishes the technical basis for performing measurements and analyses that will ensure that none of these three limits are exceeded

  13. Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Bradley, E.W.; Wu, C.F.; Goff, T.E.

    1993-01-01

    The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report

  14. Providing a Scientific and Technical Basis for Repository Decisions

    International Nuclear Information System (INIS)

    2001-01-01

    The Nuclear Waste Policy Act (NWPA) of 1982 directed the U. S. Department of Energy (DOE) to research sites and design a deep geologic repository for the disposal of our nation's spent nuclear fuel and high-level radioactive waste. In 1987, Congress amended the NWPA and directed the DOE to focus only on Yucca Mountain, Nevada, to determine whether it is a suitable site for a repository. For more than 15 years, the DOE has been studying Yucca Mountain and has accumulated an enormous amount of scientific and technical information about the mountain and the area surrounding it. The secretary of energy will decide whether to recommend Yucca Mountain to the president as a suitable site for a repository. This decision will be based on the scientific and technical information resulting from the Department of Energy's studies of Yucca Mountain and on the views and comments submitted by other governmental groups and the public. One required basis for the secretary's decision will be a scientific analysis called a total system performance assessment

  15. Public safety around dams : proposed technical bulletins

    Energy Technology Data Exchange (ETDEWEB)

    Raska, C [BC Hydro, Burnaby, BC (Canada); Rowat, L [Ontario Power Generation Inc., Niagara Falls, ON (Canada)

    2009-07-01

    This presentation provided an introduction to the Canadian Dam Association (CDA) public safety guideline and proposed technical bulletins for exterior danger and warning signs; waterway booms and buoys; and audible and visual alerts for water conveyance structures. The presentation outlined the hierarchy of documents for principles, guidelines and technical bulletins. Effective signage includes signs in which the text is sized according to the viewing distance; the message identifies the hazard and the actions to take; and the wording is understood by the public. The criteria for effective booms and buoys were discussed in terms of visibility of booms; types of buoys to use; distance between booms floats; design issues for headpond application versus tailrace application; angling to facilitate self-rescue; and distance from structure. Proposed criteria for audible and visual alerts were also discussed. The audible and visual danger signal should have a designated signal reception area where people can recognize and react to the signal. If a visual signalling device is used, it should be red to indicate danger. Maintenance and inspection tests should be performed regularly on audible and visual signalling devices. 1 ref., 2 figs.

  16. Sandia National Laboratories Internal Dosimetry Technical Basis Manual (Rev 4)

    Energy Technology Data Exchange (ETDEWEB)

    Goke, Sarah Hayes [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Elliott, Nathan Ryan [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-09-01

    The Sandia National Laboratories’ Internal Dosimetry Technical Basis Manual is intended to provide extended technical discussion and justification of the internal dosimetry program at SNL. It serves to record the approach to evaluating internal doses from radiobioassay data, and where appropriate, from workplace monitoring data per the Department of Energy Internal Dosimetry Program Guide DOE G 441.1C. The discussion contained herein is directed primarily to current and future SNL internal dosimetrists. In an effort to conserve space in the TBM and avoid duplication, it contains numerous references providing an entry point into the internal dosimetry literature relevant to this program. The TBM is not intended to act as a policy or procedure statement, but will supplement the information normally found in procedures or policy documents. The internal dosimetry program outlined in this manual is intended to meet the requirements of Federal Rule 10CFR835 for monitoring the workplace and for assessing internal radiation doses to workers.

  17. The research project on technical information basis for aging management in Fukui and Kinki area. Final report

    International Nuclear Information System (INIS)

    Fujimura, Kimiya; Nagayama, Shigeru; Watarumi, Chikae; Toudou, Tsugihiko

    2011-01-01

    The Research Project on Technical Information Basis for Aging Management was initiated in FY2006 by the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI) as a five-year program effectively, to promote aging management of domestic nuclear power plants. Its main objective was to improve the technical basis on which aging nuclear power plants are regulated. Upon taking part in the technical strategy map for Aging Management and Safe Long Term Operation, the experiences and achievements of the participating organizations were taken into account and the following four topics were chosen. The regional characteristics of the Fukui and Kinki area where 15 nuclear power plants, mainly PWRs, and many nuclear related research institutes and universities are located, were also considered. 1) The improvement of pipe thinning management in nuclear power plants, 2) The development of inspection techniques to monitor the initiation and propagation of defects, 3) The development of a guideline for evaluating weld repair methods, 4) The development of a guideline for evaluating the degradation of main structures. To promote this research project, INSS has established a regional consortium (called the 'Fukui Regional Cluster' in coordination with universities, research institutes, electric utilities and venders in the Fukui and Kinki area. INSS is acting as a coordinator to make contracts, facilitate execution, and compile annual reports. In FY2010, 11 continuing research subjects were proposed for this project and all were accepted. Of these, 5 subjects were related to the first topic (pipe thinning), 4 subjects to the second topic (inspection technique) and 1 subject to each of the other two topics (weld repair and main structures). All the subjects have been completed, fulfilling the requirements and expectations. (author)

  18. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    Energy Technology Data Exchange (ETDEWEB)

    Rathbone, Bruce A.

    2009-08-28

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document.

  19. Establishment of the technical basis to apply the viscous damper in nuclear power plant

    International Nuclear Information System (INIS)

    Nakajima, J.; Suezono, N.; Higuchi, T.; Katayama, H.

    2014-01-01

    In recent years, the technical development of the damper using viscous fluid (hereinafter called 'the viscous damper') for the structures, bridges and components in the general industrial field is remarkable, and the experiences of the application to mitigate influence in an earthquake is being gathered now. In this paper, purpose of the whole activity, schedule, the research and test results carried out so far, and future plan to establish the technical basis to apply the viscous damper in nuclear power plant are reported. (author)

  20. Establishment of the technical basis to apply the viscous damper in nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Nakajima, J.; Suezono, N.; Higuchi, T. [Toshiba Corp., Isogo Nuclear Engineering Center, Isogo-ku, Yokohama (Japan); Katayama, H. [Toshiba Corp., Power and Industrial Systems Research and Development Center, Isogo-ku, Yokohama (Japan)

    2014-07-01

    In recent years, the technical development of the damper using viscous fluid (hereinafter called 'the viscous damper') for the structures, bridges and components in the general industrial field is remarkable, and the experiences of the application to mitigate influence in an earthquake is being gathered now. In this paper, purpose of the whole activity, schedule, the research and test results carried out so far, and future plan to establish the technical basis to apply the viscous damper in nuclear power plant are reported. (author)

  1. Technical basis document for internal dosimetry

    International Nuclear Information System (INIS)

    Hickman, D.P.

    1991-01-01

    This document provides the technical basis for the Chem-Nuclear Geotech (Geotech) internal dosimetry program. Geotech policy describes the intentions of the company in complying with radiation protection standards and the as low as reasonably achievable (ALARA) program. It uses this policy and applicable protection standards to derive acceptable methods and levels of bioassay to assure compliance. The models and computational methods used are described in detail within this document. FR-om these models, dose- conversion factors and derived limits are computed. These computations are then verified using existing documentation and verification information or by demonstration of the calculations used to obtain the dose-conversion factors and derived limits. Recommendations for methods of optimizing the internal dosimetry program to provide effective monitoring and dose assessment for workers are provided in the last section of this document. This document is intended to be used in establishing an accredited dosimetry program in accordance with expected Department of Energy Laboratory Accreditation Program (DOELAP) requirements for the selected radionuclides provided in this document, including uranium mill tailing mixtures. Additions and modifications to this document and procedures derived FR-om this document are expected in the future according to changes in standards and changes in programmatic mission

  2. 48 CFR 52.214-23 - Late submissions, modifications, revisions, and withdrawals of technical proposals under two-step...

    Science.gov (United States)

    2010-10-01

    ..., modifications, revisions, and withdrawals of technical proposals under two-step sealed bidding. 52.214-23... Late submissions, modifications, revisions, and withdrawals of technical proposals under two-step..., Modifications, Revisions, and Withdrawals of Technical Proposals Under Two-Step Sealed Bidding (NOV 1999) (a...

  3. 77 FR 9216 - Native American Career and Technical Education Program; Proposed Waivers and Extension of the...

    Science.gov (United States)

    2012-02-16

    ... DEPARTMENT OF EDUCATION Native American Career and Technical Education Program; Proposed Waivers...) 2007 under the Native American Career and Technical Education Program (NACTEP), the Secretary proposes... secondary school career and technical education programs. \\1\\ Section 116(a)(2) of the Carl D. Perkins...

  4. Technical basis for a minimum hydroxide concentration in tanks containing dilute waste

    International Nuclear Information System (INIS)

    Zapp, P.E.

    1995-05-01

    Laboratory tests were performed to address the protection of waste tank steel from corrosion in situations of elevated temperatures up to 75 C (hot spots) in the sludge layer of Extended Sludge Processing (ESP) tanks. Coupon immersion tests were conducted at 75 C in two ESP simulants at four hydroxide (or pH) levels. The nitrite concentrations of the simulants were calculated from the ESP technical standards based on a temperature of 40 C. The results showed that a hydroxide concentration of at least 0.01 M prevented significant corrosion of the steel at the elevated temperature. This conclusion provides the technical basis for the revised minimum hydroxide concentration of 0.01 M in the draft WSRC 241-82H Control Room Process Requirements, for the ESP tanks

  5. Technical basis for the preparation of emergency plans relating to pressurized water reactors

    International Nuclear Information System (INIS)

    L'Homme, A.; Manesse, D.; Gauvain, J.; Crabol, B.

    1989-01-01

    The paper begins by summarizing the standard French approach to management of severe accidents at PWR plants. It goes on to define the source term used as a general basis for emergency plans for protection of the civil population. The paper describes the impact this source term has on both the site and the environment, which is subsequently used as a technical basis for determining the response of the utility and the public authorities concerned. The discussion concludes with a brief outline of the current status of various emergency plans and a description of additional work currently in progress and aimed at improving these plans [fr

  6. Technical basis of safeguards

    International Nuclear Information System (INIS)

    Buechler, C.

    1975-01-01

    Definition of nuclear materials control. Materials accountancy and physical control as technical possibilities. Legal possibilities and levels of responsibility: material holders, national and international authority. Detection vs. prevention. Physical security and containment surveillance. Accountancy: materials balance concept. Materials measurement: inventory taking, flow determination. IAEA safeguards; verification of operator's statement. (HP) [de

  7. Process Technical Basis Documentation Diagram for a solid-waste processing facility

    International Nuclear Information System (INIS)

    Benar, C.J.; Petersen, C.A.

    1994-02-01

    The Process Technical Basis Documentation Diagram is for a solid-waste processing facility that could be designed to treat, package, and certify contact-handled mixed low-level waste for permanent disposal. The treatment processes include stabilization using cementitious materials and immobilization using a polymer material. The Diagram identifies several engineering/demonstration activities that would confirm the process selection and process design. An independent peer review was conducted at the request of Westinghouse Hanford Company to determine the technical adequacy of the technical approach for waste form development. The peer review panel provided comments and identified documents that it felt were needed in the Diagram as precedence for Title I design. The Diagram is a visual tool to identify traceable documentation of key activities, including those documents suggested by the peer review, and to show how they relate to each other. The Diagram is divided into three sections: (1) the Facility section, which contains documents pertaining to the facility design, (2) the Process Demonstration section, which contains documents pertaining to the process engineering/demonstration work, and 3) the Regulatory section, which contains documents describing the compliance strategy for each acceptance requirement for each feed type, and how this strategy will be implemented

  8. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    Energy Technology Data Exchange (ETDEWEB)

    Rathbone, Bruce A.

    2010-04-01

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision

  9. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    Energy Technology Data Exchange (ETDEWEB)

    Rathbone, Bruce A.

    2011-04-04

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision

  10. Technical basis for nuclear accident dosimetry at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Kerr, G.D.; Mei, G.T.

    1993-08-01

    The Oak Ridge National Laboratory (ORNL) Environmental, Safety, and Health Emergency Response Organization has the responsibility of providing analyses of personnel exposures to neutrons and gamma rays from a nuclear accident. This report presents the technical and philosophical basis for the dose assessment aspects of the nuclear accident dosimetry (NAD) system at ORNL. The issues addressed are regulatory guidelines, ORNL NAD system components and performance, and the interpretation of dosimetric information that would be gathered following a nuclear accident

  11. Technical basis to describe and document the use of the E-600 and SHP-380 detector

    International Nuclear Information System (INIS)

    Hensley, J.R.

    1997-06-01

    This technical basis document describes and documents the parameters under which the Eberline E-600 ratemeter and the associated SHP-380 detector can be operated to quantify alpha and beta contamination levels. 3 refs., 3 tabs

  12. Fiscal Year 2001 Tank Characterization Technical Sampling Basis and Waste Information Requirements Document

    International Nuclear Information System (INIS)

    ADAMS, M.R.

    2000-01-01

    The Fiscal Year 2001 Tank Characterization Technical Sampling Basis and Waste Information Requirements Document (TSB-WIRD) has the following purposes: (1) To identify and integrate sampling and analysis needs for fiscal year (FY) 2001 and beyond. (2) To describe the overall drivers that require characterization information and to document their source. (3) To describe the process for identifying, prioritizing, and weighting issues that require characterization information to resolve. (4) To define the method for determining sampling priorities and to present the sampling priorities on a tank-by-tank basis. (5) To define how the characterization program is going to satisfy the drivers, close issues, and report progress. (6)To describe deliverables and acceptance criteria for characterization deliverables

  13. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Hassan, M.; Tanaka, T.J.

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

  14. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Hassan, M. [Brookhaven National Lab., Upton, NY (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States)

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.

  15. Risk management through dynamic technical specifications

    International Nuclear Information System (INIS)

    Klopp, George T.; Petersen, Thomas A.

    2004-01-01

    The wide deployment of plant specific probabilistic risk assessments for nuclear power plants has provided the means to effect a fresh risk management perspective and a fresh, risk based, regulatory outlook on nuclear power. There has been a great deal of conversation on risk based regulation within the U. S. nuclear power industry but, curiously, very little on effective risk management. This paper proposes a means to link the two subjects through the plant Technical Specifications. A revised concept for Technical Specifications is suggested which is based on deterministic analyses and probabilistic risk assessments for each plant. The revised Technical Specifications would consider, on a real-time basis, the exact state of the plant in terms of the status of key components and systems. It would depict current plant risk levels and compare those levels to the desired and limiting (alert/action) levels. It would advise the plant operator on the risk impact of proposed actions through a simple query system and illustrate the impact of such actions on plant status relative to designated risk values. The basis for the proposed approach lies in realistic deterministic plant analyses and probabilistic risk assessment (PRA) deployment tools being developed, in parallel, by a number of parties in the U.S. today. These PRAs are based primarily on the existing plant responses to Generic Letter 88-20, 'Individual Plant Examinations' (IPEs). Each of these tools allows the plant operator to input, on a real-time basis, the status of key equipment and systems. The tools then provide explicit illustrations of dependency effects; updated, 'real-time' risk status indications such as core damage frequency; and, in some cases, allow the operator to assess the risk impact of removing from service selected components for maintenance or testing. These systems generally operate on personal computers and provide nearly instantaneous responses to plant queries. Moving from these tools to

  16. Proposal for outline of training and evaluation method for non-technical skills

    International Nuclear Information System (INIS)

    Nagasaka, Akihiko; Shibue, Hisao

    2015-01-01

    The purpose of this study is to systematize measures for improvement of emergency response capability focused on non-technical skills. As the results of investigation of some emergency training in nuclear power plant and referring to CRM training, following two issues were picked up. 1) Lack of practical training method for improvement of non-technical skills. 2) Lack of evaluation method of non-technical skills. Then, based on these 7 non-technical skills 'situational awareness' 'decision making' 'communication' 'teamworking' 'leadership' 'managing stress' 'coping with fatigue' are promotion factors to improve emergency response capability, we propose practical training method for each non-technical skill. Also we give example of behavioral markers as evaluation factor, and indicate approaches to introduce the evaluation method of non-technical skills. (author)

  17. Technical meeting on progress in managing, and limiting the consequences of events exceeding the design basis

    International Nuclear Information System (INIS)

    Fabian, H.

    2004-01-01

    The Technical Groups on 'Reactor Safety' and 'Thermodynamics and Fluid Dynamics' of the Kerntechnische Gesellschaft e.V. organized a joint technical meeting on 'Progress in Managing, and Limiting the Consequences of, Events Exceeding the Design Basis' at the FTU Training Center of the Karlsruhe Research Center. The topic chosen, the papers presented, the presenters, and the non-technical part of the program met with lively interest on the part of institutions in the nuclear field. These were the objectives of the technical meeting: - Establishing a forum for communicating relevant topics. - In-depth discussion of the main topic, i.e. the advanced development of reactor safety, research in the field, and its application, in twenty selected papers presented by speakers from different institutions. - Presentation of topical work in a nuclear technology institution, the Karlsruhe Research Center. (orig.) [de

  18. River Corridor Project Workplace Air Monitoring Technical Basis

    International Nuclear Information System (INIS)

    MANTOOTH, D.S.

    2001-01-01

    This document provides the technical basis by which the workplace air monitoring and sampling program is operated in the River Corridor Project (RCP). Revision 2 addresses and incorporates changes in the air monitoring program drivers and implementing documents which occurred after the previous revision was issued. This revision also includes an additional RCP project to make Revision 2 applicable to the entire RCP. These changes occurred in the following areas: (1) Changes resulting from the conversion of the Hanford Site Radiological Control Manual (HSRCM-1) into the Project Hanford Radiological Control Manual (F-5173). HNF-5173 is now the implementing document for 10CFR835. (2) Changes resulting from the issue of new and revised Hanford Site implementing procedures. (3) Changes resulting from the issue of new and revised, as well as the cancellation of RCP implementing procedures. (4) Addition of the 200 Area Accelerated Deactivation Project (ADP). (5) Modification of some air sampling/monitoring locations to better meet the needs of facility operations. (6) Changes resulting from the RCP reorganization

  19. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    International Nuclear Information System (INIS)

    Rathbone, Bruce A.

    2007-01-01

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL's Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL's Electronic Records and Information Capture Architecture (ERICA) database. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Minor

  20. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    Energy Technology Data Exchange (ETDEWEB)

    Rathbone, Bruce A.

    2007-03-12

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Minor

  1. 78 FR 64146 - 30-Day Notice of Proposed Information Collection: Technical Processing Requirements for...

    Science.gov (United States)

    2013-10-25

    ... Information Collection: Technical Processing Requirements for Multifamily Project Mortgage Insurance AGENCY: Office of the Chief Information Officer, HUD. ACTION: Notice. SUMMARY: HUD has submitted the proposed... Information Collection Title of Information Collection: Technical Processing Requirements for Multifamily...

  2. 75 FR 6683 - Notice of Proposed Information Collection: Comment Request; Technical Processing Requirements for...

    Science.gov (United States)

    2010-02-10

    ... Information Collection: Comment Request; Technical Processing Requirements for Multifamily Project Mortgage... information: Title of Proposal: Technical Processing Requirements for Multifamily Project Mortgage Insurance... information collection requirement described below will be submitted to the Office of Management and Budget...

  3. Safety Basis Report

    International Nuclear Information System (INIS)

    R.J. Garrett

    2002-01-01

    As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities

  4. Safety Basis Report

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2002-01-14

    As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities.

  5. Technical evaluation report on the proposed design modifications and technical-specification changes on grid voltage degradation for the San Onofre Nuclear Genetating Station, Unit 1

    International Nuclear Information System (INIS)

    Selan, J.C.

    1982-01-01

    This report documents the technical evaluation of the proposed design modifications and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the San Onofre Nuclear Generating Station, Unit 1. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation finds that the proposed design modifications and Technical Specification changes will ensure that the Class 1E equipment will be protected from sustained voltage degradation

  6. The Associative Basis of Scientific Creativity: A Model Proposal

    Directory of Open Access Journals (Sweden)

    Esra Kanli

    2014-06-01

    Full Text Available Creativity is accepted as an important part of scientific skills. Scientific creativity proceeds from a need or urge to solve a problem, and in-volves the production of original and useful ideas or products. Existing scientific creativity theories and tests do not feature the very im-portant thinking processes, such as analogical and associative thinking, which can be consid-ered crucial in creative scientific problem solv-ing. Current study’s aim is to provide an alter-native model and explicate the associative basis of scientific creativity. Emerging from the re-viewed theoretical framework, Scientific Asso-ciations Model is proposed. This model claims that, similarity and mediation constitutes the basis of creativity and focuses on three compo-nents namely; associative thinking, analogical thinking (analogical reasoning & analogical problem solving and insight which are consid-ered to be main elements of scientific associa-tive thinking.

  7. Technical basis and radiological release plan for Trackhoes used at 100 BC-1 and 100 DR-1

    International Nuclear Information System (INIS)

    De Mers, S.K.

    1997-06-01

    To develop a method for the radiological release of tracked heavy equipment vehicles used in the excavation of the 100-BC-1 and 100-DR remedial action sites, including the technical basis for selection of release criteria and the instrumentation to be used for surveys

  8. 48 CFR 452.215-71 - Instructions for the Preparation of Technical and Business Proposals.

    Science.gov (United States)

    2010-10-01

    ... contained in the technical proposal so that the contractor's understanding of the statement of work may be... required if appropriate.) (2) Business Proposal. (a) Furnish financial statements for the last two years... specified in the statement of work. Any “alternate” proposal may be considered if overall performance would...

  9. The research project on technical information basis for aging management in Fukui and Kinki area (2nd report)

    International Nuclear Information System (INIS)

    Fujimura, Kimiya; Watarumi, Chikae; Toudou, Tsugihiko

    2009-01-01

    The Research Project on Technical Information Basis for Aging Management was initiated in 2006 by the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI), to promote aging management of domestic nuclear power plants. Its main objective was to improve the technical basis on which aging plants are regulated. Upon taking part in the R and D Roadmaps for Aging Management and Safe Long Term Operation, the experience and results of the participating organizations were considered and the following four topics were extracted. The regional characteristics of the Fukui and Kinki area where 15 nuclear power plants, mainly PWRs, and many nuclear related research institutes and universities are located, were also considered. 1) The improvement of pipe thinning management in nuclear power plants. 2) The development of inspection techniques to monitor the initiation and propagation of defects. 3) The development of a guideline for evaluating weld repair methods. 4) The development of a guideline for evaluating the degradation of main structures. To promote this research project, INSS has established a regional consortium (called the 'Fukui Regional Cluster' in coordination with universities, research institutes, electric utilities and venders in the Fukui and Kinki area. INSS is acting as of coordinator to make a contracts, facilitate execution, and compile annual reports. In FY2008, 11 research subjects were proposed for this project and all were accepted. Of these, 4 subjects were related to the first topic (pipe thinning), 3 subjects were related to the second topic (inspection technique) and I subject was related to each of the other two topics (weld repair and main structures). All the subjects have been completed, fulfilling the requirements and expectations. (author)

  10. The research project on technical information basis for aging management in Fukui and Kinki area. 3rd report

    International Nuclear Information System (INIS)

    Fujimura, Kimiya; Watarumi, Chikae; Toudou, Tsugihiko

    2010-01-01

    The Research Project on Technical Information Basis for Aging Management was initiated in FY2006 by the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI), to promote aging management of domestic nuclear power plants. Its main objective was to improve the technical basis on which aging nuclear power plants are regulated. Upon taking part in the R and D Roadmaps for Aging Management and Safe Long Term Operation, the experiences and achievements of the participating organizations were taken into account and the following four topics were chosen. The regional characteristics of the Fukui and Kinki area where 15 nuclear power plants, mainly PWRs, and many nuclear related research institutes and universities are located, were also considered. (1) The improvement of pipe thinning management in nuclear power plants, (2) The development of inspection techniques to monitor the initiation and propagation of defects, (3) The development of a guideline for evaluating weld repair methods, (4) The development of a guideline for evaluating the degradation of main structures. To promote this research project, INSS has established a regional consortium (called the 'Fukui Regional Cluster' in coordination with universities, research institutes, electric utilities and venders in the Fukui and Kinki area. INSS is acting as a coordinator to make contracts, facilitate execution, and compile annual reports. In FY2009, 11 research subjects were proposed for this project and all were accepted. Of these, 4 subjects were related to the first topic (pipe thinning), 3 subjects to the second topic (inspection technique) and 1 subject to each of the other two topics (weld repair and main structures). All the subjects have been completed, fulfilling the requirements and expectations. (author)

  11. Light Water Reactor Sustainability Program Technical Basis Guide Describing How to Perform Safety Margin Configuration Risk Management

    Energy Technology Data Exchange (ETDEWEB)

    Curtis Smith; James Knudsen; Bentley Harwood

    2013-08-01

    The INL has carried out a demonstration of the RISMC approach for the purpose of configuration risk management. We have shown how improved accuracy and realism can be achieved by simulating changes in risk – as a function of different configurations – in order to determine safety margins as the plant is modified. We described the various technical issues that play a role in these configuration-based calculations with the intent that future applications can take advantage of the analysis benefits while avoiding some of the technical pitfalls that are found for these types of calculations. Specific recommendations have been provided on a variety of topics aimed at improving the safety margin analysis and strengthening the technical basis behind the analysis process.

  12. Estimation of regulated term of technical systems further operation

    International Nuclear Information System (INIS)

    Strel'nikov, V.P.

    2008-01-01

    The technique of estimating the regulated term of technical systems further operation on the basis of data on failures during operation and use of probabilistic-physical model of failures (DN-distribution) is proposed

  13. Innovative and practical technical development of nuclear energy. Efforts on proposal and recruitment type technical development of nuclear energy

    International Nuclear Information System (INIS)

    Matsui, Kazuaki; Shioiri, Akio; Hamada, Jun; Kanagawa, Takashi; Mori, Yukihide; Kouno, Koji

    2003-01-01

    In technical development of nuclear energy conceiving a view on energy environment problem at the 21st Century, technical development on innovative nuclear energy system as well as next generation LWR is an important subject. Even in Japan, on the 'Long-term program for research, development and utilization of nuclear energy (LPRNE)' summarized by the Atomic Energy Commission, investigation on R and Ds of innovative reactors under cooperation of government, industrial field, and universities is required. In the Energy Generalized Engineering Institute, by receiving a subsidy from the Ministry of Economy and Industry since 2000, a proposal recruitment business on innovative and practical technical development of nuclear energy has been carried out. Here were introduced hopeful and unique five themes out of them applied to the recruitment, such as a super-critical pressure water cooling reactor (SCPR), an integrated modular LWR (IMR): technical development for practice, technical development on general purpose boiling transitional analysis method, technical development on direct extraction of U and Pu from consumed fuels based on super-DIREX reprocessing method, and material transfer forecasting in natural barriers at landfill disposal of radioactive wastes. (G.K.)

  14. Technical evaluation of the proposed changes in the technical specifications for emergency power sources for the Big Rock Point nuclear power plant

    International Nuclear Information System (INIS)

    Latorre, V.R.

    1979-12-01

    The technical evaluation is presented for the proposed changes to the Technical Specifications for emergency power sources for the Big Rock Point nuclear power plant. The criteria used to evaluate the acceptability of the changes include those delineated in IEEE Std-308-1974, and IEEE Std-450-1975 as endorsed by US NRC Regulatory Guide 1.129

  15. Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2015-11-01

    The demands on nuclear fuel have recently been increasing, and include transient regimes, higher discharge burnup and longer fuel cycles. This has resulted in an increase of loads on fuel and core internals. In order to satisfy these demands while ensuring compliance with safety criteria, new national and international programmes have been launched and advanced modelling codes are being developed. The Fukushima Daiichi accident has particularly demonstrated the need for adequate analysis of all aspects of fuel performance to prevent a failure and also to predict fuel behaviour were an accident to occur.This publication presents the Proceedings of the Technical Meeting on Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents, which was hosted by the Nuclear Power Institute of China (NPIC) in Chengdu, China, following the recommendation made in 2013 at the IAEA Technical Working Group on Fuel Performance and Technology. This recommendation was in agreement with IAEA mid-term initiatives, linked to the post-Fukushima IAEA Nuclear Safety Action Plan, as well as the forthcoming Coordinated Research Project (CRP) on Fuel Modelling in Accident Conditions. At the technical meeting in Chengdu, major areas and physical phenomena, as well as types of code and experiment to be studied and used in the CRP, were discussed. The technical meeting provided a forum for international experts to review the state of the art of code development for modelling fuel performance of nuclear fuel for water cooled reactors with regard to steady state and transient conditions, and for design basis and early phases of severe accidents, including experimental support for code validation. A round table discussion focused on the needs and perspectives on fuel modelling in accident conditions. This meeting was the ninth in a series of IAEA meetings, which reflects Member States’ continuing interest in nuclear fuel issues. The previous meetings were held in 1980 (jointly with

  16. Scoliosis angle. Conceptual basis and proposed definition

    Energy Technology Data Exchange (ETDEWEB)

    Marklund, T [Linkoepings Hoegskola (Sweden)

    1978-01-01

    The most commonly used methods of assessing the scoliotic deviation measure angles that are not clearly defined in relation to the anatomy of the patient. In order to give an anatomic basis for such measurements it is proposed to define the scoliotic deviation as the deviation the vertebral column makes with the sagittal plane. Both the Cobb and the Ferguson angles may be based on this definition. The present methods of measurement are then attempts to measure these angles. If the plane of these angles is parallel to the film, the measurement will be correct. Errors in the measurements may be incurred by the projection. A hypothetical projection, called a 'rectified orthogonal projection', is presented, which correctly represents all scoliotic angles in accordance with these principles. It can be constructed in practice with the aid of a computer and by performing measurements on two projections of the vertebral column; a scoliotic curve can be represented independent of the kyphosis and lordosis.

  17. Place of the adoption of technical proposals from research in farmers’ adaptation strategies

    Directory of Open Access Journals (Sweden)

    P. Pedelahore

    2011-01-01

    Full Text Available Technical innovation is often presented as the main lever to improve economical performances and livelihoods of family farmers. It is thus a way to face the variability of the socio-economical environment. The aim of this study was to analyze the role of the adoption of technical proposals from research within the range of the adaptation strategies used by farmers to maintain or even improve their livelihoods and that of their descendants. Semi-structured and structured interviews carried out on a sample of representative family farmers of South Cameroon showed that migrations, off farm activities, increase of cultivated areas, and cash crop diversification were adaptation strategies more often used by farmers than the adoption of technical proposals. The study highlighted that improving crop management sequences and performances of family farming systems could not be the sole orientation of research and development policies. The increase of farmers spatial and professional mobility points the need to develop research and development policies that focus more closely on territorial and farmers’ management and on interactions between the different sectors of the national economy.

  18. Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the Millstone Nuclear Power Station, Unit 2 (Docket No. 50-336)

    International Nuclear Information System (INIS)

    Selan, J.C.

    1983-01-01

    This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the Millstone Nuclear Power Station, Unit 2. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

  19. Biomass heating at East Surrey Hospital: technical evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Landen, R; Rippengal, R

    2000-07-01

    This report provides the results of a detailed evaluation of the proposed biomass heating installation at East Surrey Hospital. It is intended to allow the Trust to make a decision on whether to proceed further with the scheme and, if so, on what basis. Specific areas assessed and reported on include: existing services provision for heating and cooling; technical aspects of the proposed biomass scheme; commercial aspects of the proposed biomass scheme. (author)

  20. Cultivating Advanced Technical Writing Skills through a Graduate-Level Course on Writing Research Proposals

    Science.gov (United States)

    McCarthy, Brian D.; Dempsey, Jillian L.

    2017-01-01

    A graduate-level course focused on original research proposals is introduced to address the uneven preparation in technical writing of new chemistry graduate students. This course focuses on writing original research proposals. The general course structure features extensive group discussions, small-group activities, and regular in-class…

  1. Technical basis for acceptance criteria on the susceptibility of digital systems to electromagnetic interference

    International Nuclear Information System (INIS)

    Ewing, P.D.; Korsah, K.; Antonescu, C.

    1992-01-01

    This paper discusses the development of the technical basis for establishing acceptance criteria on the susceptibility of digital systems to electromagnetic interference (EMI). The effort is sponsored by the US Nuclear Regulatory Commission and stems from the safety-related issues that need to be addressed with the application of digital instrumentation and controls systems in nuclear power plants. Designers of digital circuits are incorporating increasingly higher clock frequencies and lower logic voltage levels, thereby leading to the risk of susceptibility when spurious interference is misinterpreted as legitimate logic. Development of the technical basis for acceptance criteria centers around establishing good engineering practices to ensure that sufficient levels of electromagnetic compatibility (EMC) are maintained between the nuclear power plant's electronic and electromechanical systems. First, good EMC design and installation practices are needed to control the emissions from interference sources and their impact on other nearby circuits and systems. Then, a test and evaluation program is needed to outline the EMI tests to be performed, the associated test methods to be followed, and adequate test limits to ensure that the circuit or system under test meets the recommended guidelines. Test and evaluation should be followed by periodic maintenance to assess whether the recommended EMI control practices continue to be adhered to as part of the routine operation of the nuclear power plant. By following these steps, the probability of encountering safety-related problems associated with EMI will be greatly reduced

  2. Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the James A. Fitzpatrick Nuclear Power Plant (Docket No. 50-333)

    International Nuclear Information System (INIS)

    Selan, J.C.

    1983-01-01

    This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the James A. FitzPatrick Nuclear Power Plant. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

  3. Technical evaluation of the proposed design modifications and technical specification changes on grid voltage degradation (Part A) for the Pilgrim Nuclear Power Station, Unit 1

    International Nuclear Information System (INIS)

    White, R.L.

    1980-01-01

    This report documents the technical evaluation of the proposed design modifications and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the Pilgrim Nuclear Power Station. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation compares the submittals made by the licensee with the NRC staff positions and the review criteria and presents the reviewer's conclusion on the acceptability of the proposed system

  4. Scientific and technical basis for the near surface disposal of low and intermediate level waste

    International Nuclear Information System (INIS)

    2002-01-01

    This report presents an overview of the scientific and technical basis for the disposal of low- and intermediate-level radioactive waste in near surface repositories. The focus is on basic principles, approaches, methodologies and technical criteria that can be used to develop and assess the performance of a disposal facility, and for building confidence in repository safety. This includes consideration of the multiple barrier concept, the performance of engineered barriers, the role of natural barriers and the development of a safety case. The emphasis is on defining the conditions relevant to the containment of the radionuclides in the repository and the processes that may affect the integrity of the engineered barriers. Both generic and specific data requirements for repository development and the assurance of safety are addressed. A large number of bibliographical references are given to support the information provided in this report

  5. Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the Indian Point Nuclear Power Plant, Unit 3 (Docket No. 50-286)

    International Nuclear Information System (INIS)

    Selan, J.C.

    1983-01-01

    This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the Indian Point Nuclear Power Plant, Unit 3. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

  6. FAIR - Baseline technical report. Executive summary

    International Nuclear Information System (INIS)

    Gutbrod, H.H.; Augustin, I.; Eickhoff, H.; Gross, K.D.; Henning, W.F.; Kraemer, D.; Walter, G.

    2006-09-01

    This document presents the Executive Summary, the first of six volumes comprising the 2006 Baseline Technical Report (BTR) for the international FAIR project (Facility for Antiproton and Ion Research). The BTR provides the technical description, cost, schedule, and assessments of risk for the proposed new facility. The purpose of the BTR is to provide a reliable basis for the construction, commissioning and operation of FAIR. The BTR is one of the central documents requested by the FAIR International Steering Committee (ISC) and its working groups, in order to prepare the legal process and the decisions on the construction and operation of FAIR in an international framework. It provides the technical basis for legal contracts on contributions to be made by, so far, 13 countries within the international FAIR Consortium. The BTR begins with this extended Executive Summary as Volume 1, which is also intended for use as a stand-alone document. The Executive Summary provides brief summaries of the accelerator facilities, the scientific programs and experimental stations, civil construction and safety, and of the workproject structure, costs and schedule. (orig.)

  7. Ideal Based Cyber Security Technical Metrics for Control Systems

    Energy Technology Data Exchange (ETDEWEB)

    W. F. Boyer; M. A. McQueen

    2007-10-01

    Much of the world's critical infrastructure is at risk from attack through electronic networks connected to control systems. Security metrics are important because they provide the basis for management decisions that affect the protection of the infrastructure. A cyber security technical metric is the security relevant output from an explicit mathematical model that makes use of objective measurements of a technical object. A specific set of technical security metrics are proposed for use by the operators of control systems. Our proposed metrics are based on seven security ideals associated with seven corresponding abstract dimensions of security. We have defined at least one metric for each of the seven ideals. Each metric is a measure of how nearly the associated ideal has been achieved. These seven ideals provide a useful structure for further metrics development. A case study shows how the proposed metrics can be applied to an operational control system.

  8. Improving the technical preparation of football players on the basis of the control of discriminative characteristics when performing combinations of techniques during a game

    Directory of Open Access Journals (Sweden)

    Mitova Olena

    2016-06-01

    Full Text Available The paper examines the issue of improving the technical preparation of football players during initial basic training. A special attention is paid to the development and experimental substantiation of the methods of technical preparation of young football players in an annual cycle at the stage of initial basic training on the basis of the control of discriminative characteristics when performing inseparable combinations of techniques during a game. An attempt was made to uncover the underlying causes of a low technical preparedness of football players at different stages of multi-year training and to implement an integrated scientific approach to improvement of the process of technical preparation of 10-11 years old football players in an annual cycle at the stage of initial basic training on the basis of the control of discriminative characteristics when performing inseparable combinations of techniques during competitive activity, along with the peculiarities of psychophysical condition and a level of development of physical qualities. This approach in teaching technical skills will be of interest to specialists and coaches in football, since the pedagogical experiment has determined the effectiveness of the developed methodology.

  9. Ensuring the conflict sustainability of the information systems on the basis of technical means

    Directory of Open Access Journals (Sweden)

    L. E. Mistrov

    2016-01-01

    Full Text Available The analysis of the purposes, tasks, functions and ways of ensuring conflict stability of func-tioning of information systems on the ba-sis of application of a complex of technical means is carried out. The main contours of management of elements of the organizational and technical systems (OTS in various forms of actions are defined. It is noted that a basis of functioning of OTS, infor-mation sup-port makes, classes of the data making him are defined. It is shown that ensuring conflict stability of functioning of the information sys-tems (IS is carried out by the complex of technical means (CTM, as a part of subsystems of reception / transfer, collecting and de-struction / distortion of information, their main functions are defined. Wednesday in which KTS function, is defined as an information and target situation which is understood as the part of a social and economic situa-tion characterized by existence of KTS providing functioning with IS, their location, operating modes, parameters of the information streams (IS, characteristics of technical means of processing, storage, submission of information realized by ways of the information security (IS for the solution of tasks in dynamics of information conflict. At the same time the information conflict is part target (the difficult conflict OTS representing information ex-change of KTS providing conflict steady functioning of IS at realization of processes of collection of information, transfer and counter-action to carrying out similar actions by the competing party with means of the destroying / distorting in-fluences (RIV. The special at-tention is paid to research of actions of a subsystem of collection of information, methods of collection of information are defined, con-ditions of application of methods of processing of the collected data are shown, features of functioning of subsystems of KTS at vari-ous stages of application are considered. The conclusion is drawn that

  10. Technical-evaluation report on the proposed technical-specification changes on degraded grid-voltage protection for the Rancho Seco Nuclear Generating Plant (Docket No. 50-312)

    International Nuclear Information System (INIS)

    Selan, J.C.

    1983-01-01

    This Technical Evaluation Report is a revision and contains supplemental information to the Technical Evaluations documented in previous LLNL reports dated October 1980 (UCID-18690), November 10, 1981 (UCID-19113), and July 15, 1983 (UCID-19708). These reports encompass the NRC requirements on Degraded Grid Voltage Protection and Adequacy of Station Electric Distribution System Voltages. The evaluation finds that the proposed Technical Specification changes on the undervoltage/overvoltage trip setpoints and Limiting Conditions for Operation provide the required protection to the Class 1E Equipment from sustained abnormal voltages

  11. System requirements and design description for the document basis database interface (DocBasis)

    International Nuclear Information System (INIS)

    Lehman, W.J.

    1997-01-01

    This document describes system requirements and the design description for the Document Basis Database Interface (DocBasis). The DocBasis application is used to manage procedures used within the tank farms. The application maintains information in a small database to track the document basis for a procedure, as well as the current version/modification level and the basis for the procedure. The basis for each procedure is substantiated by Administrative, Technical, Procedural, and Regulatory requirements. The DocBasis user interface was developed by Science Applications International Corporation (SAIC)

  12. Standard Technical Specifications, Babcock and Wilcox plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The unproved STS were developed based on the, criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop proved plant-specific technical specifications. This report contains three volumes. This document, Volume 1 contains the Specifications for all chapters and sections of the improved STS

  13. Technical basis for the ITER-FEAT outline design. Progress in resolving open design issues from the outline design report

    International Nuclear Information System (INIS)

    2000-01-01

    In this publication the technical basis for the ITER-FEAT outline design is presented. It comprises the Plant Design Specifications, the Safety Principles and Environmental Criteria, the Site Requirements and Site Design Assumptions. The outline of the key features of the ITER-FEAT design includes main physical parameters and assessment, design overview and preliminary safety assessment, cost and schedule

  14. Proceedings of the joint CSNI/CNRA workshop on redefining the large break LOCA: technical basis and its implications

    International Nuclear Information System (INIS)

    2003-01-01

    -informing technical requirement. In the third paper, the European reactor vendor gave its view on LB-LOCA definition for new reactors (EPR). The proposed concept take into account the LB-LOCA (of the main coolant line) for designing the ECCS and the containment but not for mechanical design of the main coolant lines itself. An important prerequisite for LBB and break exclusion in the EPR is also reliable monitoring and inspection. 2. Does adequate technical basis exist to support a redefinition of the LB-LOCA? None of the participants suggested that the probability of LB LOCA could be so high that it represents a significant contribution to the overall risk. There was a general confidence that the probability of a fast occurring large leak from the main reactor coolant circuit can be made insignificant with the right corrective measures. This is true at least in the new plants where lessons learned during the last 30 years have been implemented. The session had a well coordinated set of four complementary presentations aimed at measuring the technical basis to support a redefinition of the LB-LOCA, through the potential development of a spectrum of break sizes, their expected frequencies and the corresponding consequences. With that aim, the four papers presented, in a sequential manner: the critical issues and technical approaches to the subject from the risk requirements point of view, the known and potential aging mechanisms in primary pipes, the technical and administrative developments to prevent pressure boundary fractures through in service inspections and the new developments to detect such fractures through advanced leak detection technologies. The NRC presentation identified issues related to materials engineering, risk considerations, and plant response analysis, and discussed NRC's ongoing technical approaches to address these issues and develop a technical basis for the risk-informed revision of the rule. The EDF presentation was very insightful as it reflected

  15. Upper Caraş River (Danube watershed fish populations fragmentation – technical rehabilitation proposal

    Directory of Open Access Journals (Sweden)

    Voicu Răzvan

    2018-01-01

    Full Text Available We propose a technical solution for fish movement based on the flow of water over a spill threshold. Such barriers are common in the Danube system. The proposed system has a range of operating components which are easily detachable from the spill threshold, are resistant to corrosion and will not harm the fish. In fact, if designed to complement swimming abilities of target fish, it should provide adequate passage for both adults and juveniles. If implemented correctly, the design may offer a solution to help displaced fish recolonize upstream habitats.

  16. Technical basis for high-level waste repository land control requirements for Palo Duro Basin, Paradox Basin, and Richton Dome

    International Nuclear Information System (INIS)

    Chen, C.P.; Raines, G.E.

    1987-02-01

    Three sites, the Palo Duro Basin in Texas, the Paradox Basin in Utah, and the Richton Dome in Mississippi, are being investigated by the US Department of Energy for high-level radioactive-waste disposal in mined, deep geologic repositories in salt. This report delineates the use of regulatory, engineering, and performance assessment information to establish the technical basis for controlled area requirements. Based on the size of the controlled area determined, plus that of the geologic repository operations area, recommendations of possible land control or ownership area requirements for each locale are provided. On a technical basis, the following minimum land control or ownership requirements are recommended, assuming repository operations area of 2240 ac (907 ha), or 3.5 mi 2 (9.1 km 2 ): Palo Duro Basin - 4060 ac (1643 ha), or 6.3 mi 2 (16.4 km 2 ); Paradox Basin - 4060 ac (1643 ha), or 6.3 mi 2 (16.4 km 2 ); and Richton Dome - 5000 ac (2024 ha), or 7.8 mi 2 (20.2 km 2 ). Of the factors used to determine the technically based recommendations, one was found to dominate each locale. For the Palo Duro and Paradox Basins, the dominant factor was the need to limit potential radionuclide release by ground-water flow to the accessible environment. For the Richton Dome, the dominant factor was the need to limit the potential effects of solution mining on dome and repository integrity

  17. 78 FR 52963 - 60-Day Notice of Proposed Information Collection: Technical Processing Requirements for...

    Science.gov (United States)

    2013-08-27

    ... Information Collection: Technical Processing Requirements for Multifamily Project Mortgage Insurance AGENCY...: HUD is seeking approval from the Office of Management and Budget (OMB) for the information collection... interested parties on the proposed collection of information. The purpose of this notice is to allow for 60...

  18. Analysis of the prevailing standard and technical documents for their applicability under conditions of the 'Ukrytie' operation and technical proposals relating to the elaboration of new ones concerning fire safety

    International Nuclear Information System (INIS)

    Nazarenko, B.S.; Emets, V.G.

    1998-01-01

    An analysis of the prevailing laws and standards and technical documents (STD) to ensure safe operation of nuclear power installations, with requirements of nuclear, radiation and fire safety taken into account, has been performed. Proposals on application of some items of prevailing STD under conditions of the 'Ukrytie' operation are presented. Also given are technical proposals on correction of the prevailing operational standard documents and elaboration of special STD

  19. Standard Technical Specifications, Westinghouse plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document, Volume 3, contains the Bases for Sections 3.4--3.9 of the improved STS

  20. Standard Technical Specifications, Westinghouse Plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the unproved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS which contain information on safety limits, reactivity control systems, power distribution limits, and instrumentation

  1. Standard Technical Specifications, Westinghouse plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  2. Standard Technical Specifications, Babcock and Wilcox Plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) plants and documents the positions of the Nuclear Regulatory Commission (NRC) based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council. The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for developing improved plant-specific technical specifications by individual nuclear power plant licensees. This volume contains sections 3.4--3.9 which cover: Reactor coolant systems, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations

  3. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    Energy Technology Data Exchange (ETDEWEB)

    Rathbone, Bruce A.

    2010-01-01

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the

  4. Technical basis for storage of elastomer-sealed produce cans in the DOE-STD-3013-94 package

    International Nuclear Information System (INIS)

    Horrell, D.R.; Stakebake, J.L.; Szempruch, R.W.

    1996-11-01

    Department of Energy standard DOE-STD-3013-94 establishes criteria for the long-term packaging of plutonium metal and oxide. The inclusion of organic materials in sealed packages of plutonium may produce gases that contribute to container pressurization. To expedite processing, it would be desirable to permit, within the DOE-outlined criteria, limited amounts of organic materials to be used as a sealing gasket in some packaging containers. This paper presents a technical basis for allowing elastomer-sealed cans to be packaged inside the sealed inner container of a double weld-sealed DOE-STD-3013-94 container system

  5. 75 FR 75186 - Interview Room Video System Standard Special Technical Committee Request for Proposals for...

    Science.gov (United States)

    2010-12-02

    ... DEPARTMENT OF JUSTICE Office of Justice Programs [OJP (NIJ) Docket No. 1534] Interview Room Video System Standard Special Technical Committee Request for Proposals for Certification and Testing Expertise... Interview Room Video System Standard and corresponding certification program requirements. This work is...

  6. Technical basis for dose reconstruction

    International Nuclear Information System (INIS)

    Anspaugh, L.R.

    1996-01-01

    The purpose of this paper is to consider two general topics: Technical considerations of why dose-reconstruction studies should or should not be performed and methods of dose reconstruction. The first topic is of general and growing interest as the number of dose-reconstruction studies increases, and one asks the question whether it is necessary to perform a dose reconstruction for virtually every site at which, for example, the Department of Energy (DOE) has operated a nuclear-related facility. And there is the broader question of how one might logically draw the line at performing or not performing dose-reconstruction (radiological and chemical) studies for virtually every industrial complex in the entire country. The second question is also of general interest. There is no single correct way to perform a dose-reconstruction study, and it is important not to follow blindly a single method to the point that cheaper, faster, more accurate, and more transparent methods might not be developed and applied. 90 refs., 4 tabs

  7. Technical basis for dose reconstruction

    International Nuclear Information System (INIS)

    Anspaugh, L.R.

    1996-01-01

    The purpose of this paper is to consider two general topics: technical considerations of why dose-reconstruction studies should or should not be performed and methods of dose reconstruction. The first topic is of general and growing interest as the number of dose-reconstruction studies increases, and one asks the question whether it is necessary to perform a dose reconstruction for virtually every site at which, for example, the Department of Energy (DOE) has operated a nuclear-related facility. And there is the broader question of how one might logically draw the line at performing or not performing dose-reconstruction (radiological and chemical) studies for virtually every industrial complex in the entire country. The second question is also of general interest. There is no single correct way to perform a dose-reconstruction study, and it is important not to follow blindly a single method to the point that cheaper, faster, more accurate, and more transparent methods might not be developed and applied

  8. Technical evaluation report on the proposed design modifications and technical specification changes on grid voltage degradation for the Millstone Nuclear Power Station, Unit 1

    International Nuclear Information System (INIS)

    Selan, J.C.

    1982-01-01

    This report documents the technical evaluation of the proposed design modifications and Technical Specification change for protection of Class 1E equipment from grid voltage degradation for the Millstone Nuclear Power Station, Unit 1. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation finds that the licensee has not provided sufficient information on the undervoltage protection system to allow a complete evaluation into the adequacy of protecting the Class 1E equipment from sustained voltage degradation

  9. Standard Technical Specifications, Combustion Engineering plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (M) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  10. Standard Technical Specifications, Combustion Engineering plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved SM. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3 contains the Bases for Sections 3.4--3.9 of the improved M

  11. Standard Technical Specifications, General Electric plants, BWR/4

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power specifications. This report contains three volumes. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS

  12. Technical basis for staffing levels at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Shurberg, D.A.; Haber, S.B. [Brookhaven National Lab., Upton, NY (United States); Morisseau, D. [Nuclear Regulatory Commission, Washington, DC (United States)] [and others

    1995-04-01

    The objective of this project is to provide a technical basis for the establishment of criteria for minimum staffing levels of licensed and non-licensed NPP shift personnel. Minimum staffing levels for the purpose of this study, are defined as those necessary for successful accomplishment of all safety and additional functions that must be performed in order for the licensee to meet applicable regulatory requirements. This project involves a multi-faceted approach to the investigation of the issue. Relevant NRC documentation was identified and reviewed. Using the information obtained from this documentation review, a test plan was developed to aid in the collection of further information regarding the adequacy of current shift staffing levels. The test plan addresses three different activities to be conducted to provide information to the NRC for use in the assessment of current minimum staffing levels. The first activity is collection of data related to industry shift staffing practices through site visits to seven nuclear power plants. The second activity is a simulator study, which will use licensed operator crews responding to a simulated event, under two different staffing levels. Finally, workload models will be constructed for both licensed and non-licensed personnel, using a priori knowledge of the simulator scenarios with data resulting from one of the staffing levels studied in the simulator, and the data collected from the site visits. The model will then be validated against the data obtained from the second staffing level studied in the simulator. The validated model can then be used to study the impact of changing staffing-related variables on the plant shift crew`s ability to effectively mitigate an event.

  13. Conversion of NEK standard technical specifications into improved technical specifications

    International Nuclear Information System (INIS)

    Glaser, B.

    2003-01-01

    Neck is currently using a standard format of operation's Technical Specifications - STS (based on NUREG-0452), which are planned to be converted into Improved Technical Specifications - ITS (based on NUREG-1431). To facilitate the development of individual ITS, each reactor vendor owners group (OG) and the NRC staff developed improved standard TS (ISTS). For Westinghouse plants, the ISTS are published as NUREG-1431, and this document is going to be the basis for the new NEK ITS. It has been recognized that nuclear safety in all plants would benefit from improvement and standardization of ITS, so this was also addressed and recognized by the NRC. There are several plants around Europe and US, which have replaced the format into ITS which brings a lot of improvements and practical value in operations. The main objective of conversion is to completely rewrite, reformat, and streamline the existing STS. Emphasis is placed on human factors principles to improve clarity and understanding. The Bases section will be significantly expanded to clarify and better explain the purpose and foundation of each specification. There might be some proposed changes to the existing STS that deviated from the ITS in NUREG-1431 and constitute a relaxation of the existing STS. Each of these additional proposed changes will be described and evaluated in amendment application and justified on a case-by-case basis. Since the NEK is going to operate for more than 20 year without considering life extension, such conversion will be beneficial for operation personnel as well as regulation, surveillance and focus on operation's safety. At the present, only preliminary plan of STS conversion exists, showing the time frame of approximately 2 years of conversion process and numerous tasks that need to be performed. The plan is to begin with process in year 2004 and finish project in 2006, which means use of new ITS in main control room in year 2007. Beside the main process of conversion, there are

  14. Statement of Basis/Proposed Plan for the Gunsite 720 Rubble Pit Unit (631-18G)

    International Nuclear Information System (INIS)

    Palmer, E.

    1996-07-01

    This Statement of Basis/Proposed Plan for the Gunsite 720 Rubble Pit Unit is issued by the U.S. Department of Energy, the lead agency for the Savannah River Site remedial activities, with concurrence by the U.S. Environmental Protection Agency - Region IV, and the South Carolina Department of Health and Environmental Control

  15. Proposed design modifications and technical specification changes on grid voltage degradation for the Point Beach Nuclear Plant, Units 1 and 2 (Docket Nos. 50-266 and 50-301). Technical evaluation report

    International Nuclear Information System (INIS)

    White, R.L.

    1981-01-01

    This report documents the technical evaluation of the proposed design mofifications and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the Point Beach Nuclear Plant, Units 1 and 2. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation compares the submittals made by the licensee with the NRC staff positions and the review criteria and presents the reviewer's conclusion on the acceptability of the proposed system

  16. Parallel Algorithms for Groebner-Basis Reduction

    Science.gov (United States)

    1987-09-25

    22209 ELEMENT NO. NO. NO. ACCESSION NO. 11. TITLE (Include Security Classification) * PARALLEL ALGORITHMS FOR GROEBNER -BASIS REDUCTION 12. PERSONAL...All other editions are obsolete. Productivity Engineering in the UNIXt Environment p Parallel Algorithms for Groebner -Basis Reduction Technical Report

  17. Addendum to Technical Proposal: A Facility to Search for Hidden Particles (SHiP) at the CERN SPS

    CERN Document Server

    SHiP Collaboration

    2015-01-01

    With the Technical Proposal submitted to the SPSC committee in April 2015, the SHiP collaboration declared its interest in proceeding towards a Comprehensive Design Study phase with the aim of preparing for the Technical Design Reports pending an approval by the CERN committees. Following the recommendation by the SPSC, it has been decided to complement the TP with this addendum that provides an update of the key aspects for the review of the SHiP project.

  18. Technical basis for evaluating electromagnetic and radio-frequency interference in safety-related I ampersand C systems

    International Nuclear Information System (INIS)

    Ewing, P.D.; Korsah, K.

    1994-04-01

    This report discusses the development of the technical basis for the control of upsets and malfunctions in safety-related instrumentation and control (I ampersand C) systems caused by electromagnetic and radio-frequency interference (EMI/RFI) and power surges. The research was performed at the Oak Ridge National Laboratory (ORNL) and was sponsored by the USNRC Office of Nuclear Regulatory Research (RES). The motivation for research stems from the safety-related issues that need to be addressed with the application of advanced I ampersand C systems to nuclear power plants. Development of the technical basis centered around establishing good engineering practices to ensure that sufficient levels of electromagnetic compatibility (EMC) are maintained between the nuclear power plant's electronic and electromechanical systems known to be the source(s) of EMI/RFI and power surges. First, good EMC design and installation practices need to be established to control the impact of interference sources on nearby circuits and systems. These EMC good practices include circuit layouts, terminations, filtering, grounding, bonding, shielding, and adequate physical separation. Second, an EMI/RFI test and evaluation program needs to be established to outline the tests to be performed, the associated test methods to be followed, and carefully formulated acceptance criteria based on the intended environment to ensure that the circuit or system under test meets the recommended guidelines. Third, a program needs to be developed to perform confirmatory tests and evaluate the surge withstand capability (SWC) and of I ampersand C equipment connected to or installed in the vicinity of power circuits within the nuclear power plant. By following these three steps, the design and operability of safety-related I ampersand C systems against EMI/RFI and power surges can be evaluated, acceptance criteria can be developed, and appropriate regulatory guidance can be provided

  19. Analysis and evaluation of the ASTEC model basis. Relevant experiments. Technical report

    International Nuclear Information System (INIS)

    Koppers, V.; Koch, M.K.

    2015-12-01

    The present report is a Technical Report within the research project ''ASMO'', funded by the German Federal Ministry of Economics and Technology (BMWi 1501433) and projected at the Reactor Simulation and Safety Group, Chair of Energy Systems and Energy Economics (LEE) at the Ruhr-Universitaet Bochum (RUB). The project deals with the analysis of the model basis of the Accident Source Term Evaluation Code (ASTEC). This report focuses on the containment part of ASTEC (CPA) and presents the simulation results of the experiment TH20.7. The experimental series TH20 was performed in the test vessel THAI (Thermal-hydraulics, Aerosols, Iodine) to investigate the erosion of a helium layer by a blower generated air jet. Helium is used as a substitute for hydrogen. In the experiment TH20.7 a light-gas layer is established and eroded by a momentum driven jet. The simulation of momentum driven jets is challenging for CPA because there is no model to simulate the kinetic momentum transfer. Subject of this report is the analysis of the capability of the code with the current model basis to model momentum driven phenomena. The jet is modelled using virtual ventilation systems, so called FAN-Systems. The FAN-Systems are adapted to the erosion velocity. The simulation results are compared to the experimental results and a basic calculation using FAN-Systems without any adjustments. For further improvement, different variation calculations are performed. At first, the vertical nodalization is refined. Subsequently, the resistance coefficients are adjusted to support the jet flow pattern and the number of the FAN-Systems is reduced. The analysis shows that the simulation of a momentum driven light-gas layer erosion is possible using adjusted FAN-Systems. A fine selected vertical nodalization and adaption of the resistance coefficients improves the simulation results.

  20. Standard Technical Specifications, Babcock and Wilcox plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  1. Key issues and technical route of cyber physical distribution system

    Science.gov (United States)

    Zheng, P. X.; Chen, B.; Zheng, L. J.; Zhang, G. L.; Fan, Y. L.; Pei, T.

    2017-01-01

    Relying on the National High Technology Research and Development Program, this paper introduced the key issues in Cyber Physical Distribution System (CPDS), mainly includes: composite modelling method and interaction mechanism, system planning method, security defence technology, distributed control theory. Then on this basis, the corresponding technical route is proposed, and a more detailed research framework along with main schemes to be adopted is also presented.

  2. Revision of the European Ecolabel Criteria for Personal, Notebook and Tablet Computers TECHNICAL REPORT Summary of the final criteria proposals

    OpenAIRE

    DODD NICHOLAS; VIDAL ABARCA GARRIDO CANDELA; WOLF Oliver; GRAULICH Kathrin; BUNKE Dirk; GROSS Rita; LIU Ran; MANHART Andreas; PRAKASH Siddharth

    2015-01-01

    This technical report provide the background information for the revision of the EU Ecolabel criteria for Personal and Notebook Computers. The study has been carried out by the Joint Research Centre with technical support from the Oeko-Institut. The work has been developed for the European Commission's Directorate General for the Environment. The main purpose of this report is to provide a summary of the technical background and rationale for each criterion proposal. This document is compl...

  3. Project proposals on the creation of Russian-American joint enterprise for investigation, development and manufacture of power plants on the basis of solid oxide fuel cells

    Energy Technology Data Exchange (ETDEWEB)

    Smotrov, N.V.; Kleschev, Yu.N.

    1996-04-01

    This paper describes a proposal for a joint Russian-American enterprise for performing scientific investigations, development, and manufacture of fuel cell power plants on the basis of the solid oxide fuel cell. RASOFCo. Russian-American Solid Oxide Fuel Cells Company. RASOFCo will provide the series output of the electrochemical generator (ECG) of 1kW power, then of 5kW and 10kW as well as the development and the output of 10kW power plant with the subsequent output of a power plant of greater power. An ECG based on solid oxide fuel cells uses methane as a fuel. Predicted technical characteristics, market analysis, assessment of potential demands for power plants of low power for Tyumentransgas, participants of the joint enterprise and their founding contributions, strategy for manufacture and financing, and management of RASOFCo are discussed.

  4. Technical Meeting on Existing and Proposed Experimental Facilities for Fast Neutron Systems. Presentations

    International Nuclear Information System (INIS)

    2013-01-01

    The objective of the TM on “Existing and proposed experimental facilities for fast neutron systems” is threefold: first, it is intended for presenting and exchanging information about existing and planned experimental facilities in support of the development of innovative fast neutron systems; second, it will allow to create a catalogue of existing and planned experimental facilities currently operated/developed within national or international fast reactors programmes; third, once a clear picture of the existing experimental infrastructures is defined, new experimental facilities will be discussed and proposed, on the basis of the identified R&D needs

  5. Reentry planning: The technical basis for offsite recovery following warfare agent contamination

    Energy Technology Data Exchange (ETDEWEB)

    Watson, A.P.; Munro, N.B.

    1990-04-01

    In the event on an unplanned release of chemical agent during any stage of Chemical Stockpile Disposal Program (CSDP), the potential exists for contamination of drinking water, forage crops, grains, garden produce and livestock. Persistent agents, such as VX or sulfur mustard, pose the greatest human health concern for reentry. The purpose of this technical support study is to provide information and analyses that can be used by federal, state and local emergency planners in determining the safety or reentry to, as well as the potential for recovery of, contaminated or suspect areas beyond the installation boundary. Guidelines for disposition of livestock, agricultural crops and personal/real property are summarized. Advisories for ingestion of food crops, water, meat and milk from the affected zones are proposed. This document does not address potential adverse effects to, or agent contamination of, wild species of plants or animals. 80 refs., 4 figs., 29 tabs.

  6. MCO loading and cask loadout technical manual

    International Nuclear Information System (INIS)

    PRAGA, A.N.

    1998-01-01

    A compilation of the technical basis for loading a multi-canister overpack (MCO) with spent nuclear fuel and then placing the MCO into a cask for shipment to the Cold Vacuum Drying Facility. The technical basis includes a description of the process, process technology that forms the basis for loading alternatives, process control considerations, safety considerations, equipment description, and a brief facility structure description

  7. Technical basis for PWR emergency plans forming

    International Nuclear Information System (INIS)

    L'Homme, A.; Manesse, D.; Gauvain, J.; Crabol, B.

    1989-10-01

    Our speech first summarizes the french approach concerning the management of severe accidents which could occur on PWR stations. Then it defines the source-term which is being used as a general support for elaborating the emergency plans devoted to the protection of the population. It describes next the consequences of this source-term on the site and in the environment, which constitute the technical bases for defining actions of utilities and concerned authorities. It gives lastly information on the present status of the different emergency plans and the complementary work undertaken to improve them [fr

  8. Acceptable risk as a basis for design

    International Nuclear Information System (INIS)

    Vrijling, J.K.; Hengel, W. van; Houben, R.J.

    1998-01-01

    Historically, human civilisations have striven to protect themselves against natural and man-made hazards. The degree of protection is a matter of political choice. Today this choice should be expressed in terms of risk and acceptable probability of failure to form the basis of the probabilistic design of the protection. It is additionally argued that the choice for a certain technology and the connected risk is made in a cost-benefit framework. The benefits and the costs including risk are weighed in the decision process. A set of rules for the evaluation of risk is proposed and tested in cases. The set of rules leads to technical advice in a question that has to be decided politically

  9. Technical bases for criticality safety standards

    International Nuclear Information System (INIS)

    Clayton, E.D.

    1980-01-01

    An American National Standard implies a consensus of those substantially concerned with its scope and provisions. The technical basis, or foundation, on which the consensus rests, must in turn, be firmly established and documented for public review. The technical bases are discussed and reviewed of several standards in different stages of completion and acceptance: ANSI/ANS-8.12, 1978, Nuclear Criticality Control and Safety of Homogeneous Plutonium - Uranium Mixtures Outside Reactors (Approved July 17, 1978); ANS-815, Nuclear Criticality Control of Special Actinide Elements (Draft No. 5 of newly proposed standard); ANS-8.14, Use of Solutions of Neutron Absorbers for Criticality Control (Draft No. 4 of newly proposed standard); ANS-8.5 (Revision of N16.4, 1971), Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material (Draft No. 5 as a result of prescribed five-year review and update of old standard). In each of the preceding, the newly proposed (or revised) limits are based on the extension of experimental data via well established calculations, or by means of independent calculations with adequate margins for uncertainties. The four cases serve to illustrate the insight of the work group members in the establishment of the technical bases for the limits and the level of activity required on their part in the preparation of ANSI Standards. A time span of from four up to seven years has not been uncommon for the preparation, review, and acceptance of an ANSI Standard. 8 figures. 7 tables

  10. Technical basis for the proposed high efficiency nuclear fuel program

    International Nuclear Information System (INIS)

    MacDonald, P.E.; Herring, J.S.; Crawford, D.C.; Neimark, L.E.

    1999-01-01

    Greenhouse gas emissions from fossil fired electricity generating stations will dramatically increase over the next 20 years. Nuclear energy is the only fully developed technology able to supply large amounts of electricity without generation of greenhouse gases. However, the problem of noncompetitive economics and public concerns about radioactive waste disposal, safety, and nuclear weapons proliferation may prevent the reemergence of nuclear power as a preferred option for new electric energy generation in the U.S. This paper discusses a new research program to help address these issues, by developing fuel designs capable of burnup values in excess of 60 MWD/kgU. The objectives of the program are to: improve the reliability and robustness of light water reactor fuel, thereby improving safety margins; Significantly increase the energy generated by each fuel loading, thereby achieving longer operating cycles, higher capacity factors, and lower cost electric power; Significantly reduce the volume of spent nuclear fuel discharged for disposal by allowing more energy to be extracted from each fuel element prior to discharge; Develop fuel that is much more proliferation resistant. (author)

  11. Standard Technical Specifications, General Electric Plants, BWR/6

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

  12. Standard Technical Specifications, General Electric plants, BWR/4

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

  13. Standard Technical Specifications, General Electric plants, BWR/6

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  14. Standard Technical Specifications, General Electric Plants, BWR/6

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  15. Standard Technical Specifications, General Electric plants, BWR/4

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  16. Proposal on application of Russian technical facilities for International Mars Research Program for 2009 2015

    Science.gov (United States)

    Polishchuk, Georgy; Pichkhadze, Konstantin; Vorontsov, Victor; Pavel, Kazmerchuk

    2006-07-01

    Recently International Mars Research Program is widely discussed. Well-known initiative of President of the USA, recent progress of American and European scientists and engineers in implementation of “Mars Odyssey” and “Mars-Express” projects and Russian proposals on cooperation and participation in “Phobos Sample Return” mission declare every intention to join efforts in the ambitious Martian Program realization. The final goal of the program for nearly 15 20 years is landing of a man on the Martian surface. Before this event happens another critical stage will be Martian soil sample return. Within the next 10 years, apparently, a major task will be scale research by means of various types of technical facilities. A crucial issue for this research will be creation of research station network which would allow collecting information about planetary conditions at far-remote points. By this time within the frame of “Phobos Sample Return Program” to be launched in 2009 it is planned to deliver some meteorological mini-landers developed by the Russian and Finnish specialists on the Martian surface. From this point view it is also interesting to use balloons capable to cover considerable distance. Such proposals have been made by Russian side for “Scout” mission. European “Aurora” program also anticipates application of wide range of technical means to explore the Martian atmosphere and surface including inflatable devices. Thus, for the International Mars Exploration Program, it seems to be very prospective to use apart from launch vehicles, upper stages etc. such technical means as mini-stations, Mars rovers, penetrators, balloons, etc.

  17. Substantiation of selection method of preferred alternative of belt conveyor drive systems on the basis of the analytic hierarchy process

    Directory of Open Access Journals (Sweden)

    Goncharov K.A.

    2016-06-01

    Full Text Available This paper provides substantiation of selection method of preferred alternative of belt conveyor drive systems on the basis of the analytic hierarchy process. Conditions for the correct application of the proposed method in the selection process of preferred alternative of technical objects were worked out. The set of criteria of system effectiveness evalua-tion and the corresponding hierarchical structure in accordance with the developed conditions was proposed.

  18. Technical Meeting on Existing and Proposed Experimental Facilities for Fast Neutron Systems. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    The objective of the TM on “Existing and proposed experimental facilities for fast neutron systems” was threefold: 1) presenting and exchanging information about existing and planned experimental facilities in support of the development of innovative fast neutron systems; 2) allow creating a catalogue of existing and planned experimental facilities currently operated/developed within national or international fast reactors programmes; 3) once a clear picture of the existing experimental infrastructures is defined, new experimental facilities are discussed and proposed, on the basis of the identified R&D needs

  19. Human-system Interfaces to Automatic Systems: Review Guidance and Technical Basis

    International Nuclear Information System (INIS)

    O'Hara, J.M.; Higgins, J.C.

    2010-01-01

    Automation has become ubiquitous in modern complex systems and commercial nuclear power plants are no exception. Beyond the control of plant functions and systems, automation is applied to a wide range of additional functions including monitoring and detection, situation assessment, response planning, response implementation, and interface management. Automation has become a 'team player' supporting plant personnel in nearly all aspects of plant operation. In light of the increasing use and importance of automation in new and future plants, guidance is needed to enable the NRC staff to conduct safety reviews of the human factors engineering (HFE) aspects of modern automation. The objective of the research described in this report was to develop guidance for reviewing the operator's interface with automation. We first developed a characterization of the important HFE aspects of automation based on how it is implemented in current systems. The characterization included five dimensions: Level of automation, function of automation, modes of automation, flexibility of allocation, and reliability of automation. Next, we reviewed literature pertaining to the effects of these aspects of automation on human performance and the design of human-system interfaces (HSIs) for automation. Then, we used the technical basis established by the literature to develop design review guidance. The guidance is divided into the following seven topics: Automation displays, interaction and control, automation modes, automation levels, adaptive automation, error tolerance and failure management, and HSI integration. In addition, we identified insights into the automaton design process, operator training, and operations.

  20. Final technical evaluation report for the proposed revised reclamation plan for the Atlas Corporation Moab Mill

    International Nuclear Information System (INIS)

    1997-03-01

    This final Technical Evaluation Report (TER) summarizes the US Nuclear Regulatory Commission staff's review of Atlas Corporation's proposed reclamation plan for its uranium mill tailings pile near Moab, Utah. The proposed reclamation would allow Atlas to (1) reclaim the tailings pile for permanent disposal and long-term custodial care by a government agency in its current location on the Moab site, (2) prepare the site for closure, and (3) relinquish responsibility of the site after having its NRC license terminated. The NRC staff concludes that, subject to license conditions identified in the TER, the proposed reclamation plan meets the requirements identified in NRC regulations, which appear primarily in 10 CFR Part 40. 112 refs., 6 figs., 16 tabs

  1. Statement of Basis/Proposed Plan for the P-Area Burning Rubble Pit (131-P)

    International Nuclear Information System (INIS)

    Bland, T.

    2002-01-01

    The Statement of Basis/Proposed Plan (SB/PP) is being issued by the United States Department of Energy (USDOE), which functions as the lead agency for Savannah River Site (SRS) remedial activities, with concurrence by the United States Environmental Protection Agency (USEPA) and the South Carolina Department of Health and Environmental Control (SCDHEC). The purpose of this SB/PP is to describe the preferred remedial alternatives for the P-Area Burning/Rubble Pit (131-P) (PBRP) Operable Unit (OU) and to provide for public involvement in the decision-making process

  2. On an Objective Basis for the Maximum Entropy Principle

    Directory of Open Access Journals (Sweden)

    David J. Miller

    2015-01-01

    Full Text Available In this letter, we elaborate on some of the issues raised by a recent paper by Neapolitan and Jiang concerning the maximum entropy (ME principle and alternative principles for estimating probabilities consistent with known, measured constraint information. We argue that the ME solution for the “problematic” example introduced by Neapolitan and Jiang has stronger objective basis, rooted in results from information theory, than their alternative proposed solution. We also raise some technical concerns about the Bayesian analysis in their work, which was used to independently support their alternative to the ME solution. The letter concludes by noting some open problems involving maximum entropy statistical inference.

  3. Analytical study for frequency effects on the EPRI/USNRC piping component tests. Part 1: Theoretical basis and model development

    International Nuclear Information System (INIS)

    Adams, T.M.; Branch, E.B.; Tagart, S.W. Jr.

    1994-01-01

    As part of the engineering effort for the Advanced Light Water Reactor the Advanced Reactor Corporation formed a Piping Technical Core Group to develop a set of improved ASME Boiler and Pressure Vessel Code, Section III design rules and approaches for ALWR plant piping and support design. The technical basis for the proposed changes to the ASME Boiler and Pressure Vessel Code developed by Technical Core Group for the design of piping relies heavily on the failure margins determined from the EPRI/USNRC piping component test program. The majority of the component tests forming the basis for the reported margins against failure were run with input frequency to natural frequency ratios (Ω/ω) in the range of 0.74 to 0.87. One concern investigated by the Technical Core Group was the effect which could exist on measured margins if the tests had been run at higher or lower frequency ratios than those in the limited frequency ratio range tested. Specifically, the concern investigated was that the proposed Technical Core Group Piping Stress Criteria will allow piping to be designed in the low frequency range (Ω/ω ≥ 2.0) for which there is little test data from the EPRI/USNRC test program. The purpose of this analytical study was to: (1) evaluate the potential for margin variation as a function of the frequency ratio (R ω = Ω/ω, where Ω is the forcing frequency and ω is the natural component frequency), (2) recommend a margin reduction factor (MRF) that could be applied to margins determined from the EPRI/USNRC test program to adjust those margins for potential margin variation with frequency ratio. Presented in this paper is the analytical approach and methodology, which are inelastic analysis, which was the basis of the study. Also, discussed is the development of the analytical model, the procedure used to benchmark the model to actual test results, and the various parameter studies conducted

  4. Harmonized technical standards in the nuclear field

    International Nuclear Information System (INIS)

    Carbone, Ferdinando

    1976-01-01

    The need was felt of harmonizing and gradually standardizing technical norms, from the well-known Anglo-Saxon type codes of practice to the equally well-known recommendations of the International Commission on Radiological Protection (ICRP). The latter provide the basis for the Euratom Directives (basic standards), which, following their adoption, were embodied in the national laws of community Member countries. ISO (International Standardization Organization) is active in the nuclear technical regulations field, in particular through its Committee ISO/TC 85 ''Nuclear Energy'' at international level and, in Italy, through the National Italian Unification Agency (UNI) and its Nuclear Unification Commission (UNICEN). At its XI plenary meeting this body, on the proposal of the Secretary-General, set up a Study Group to promote revision of the regulation in force and coordination between legislation and development of UNICEN standards, considered as a set of integrative industrial technical standards. CISDEN, the Italian Nuclear Energy Forum (FIEN) and other interested organizations have been invited to collaborate in this work. (N.E.A.)

  5. Final technical evaluation report for the proposed revised reclamation plan for the Atlas Corporation Moab Mill

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    This final Technical Evaluation Report (TER) summarizes the US Nuclear Regulatory Commission staff`s review of Atlas Corporation`s proposed reclamation plan for its uranium mill tailings pile near Moab, Utah. The proposed reclamation would allow Atlas to (1) reclaim the tailings pile for permanent disposal and long-term custodial care by a government agency in its current location on the Moab site, (2) prepare the site for closure, and (3) relinquish responsibility of the site after having its NRC license terminated. The NRC staff concludes that, subject to license conditions identified in the TER, the proposed reclamation plan meets the requirements identified in NRC regulations, which appear primarily in 10 CFR Part 40. 112 refs., 6 figs., 16 tabs.

  6. Long Term Operation R and D to Investigate the Technical Basis for Life Extension and License Renewal Decisions

    International Nuclear Information System (INIS)

    Gaertner, John

    2012-01-01

    Establishing an improved technical basis for long term operation of existing plants is a nuclear industry priority. The Electric Power Research Institute (EPRI) has responded with a comprehensive Long Term Operation (LTO) Program addressing this need for existing nuclear power plants world-wide. The program supports both the business decisions necessary to achieve high performance operation and the licensing requirements for operation beyond 60 years. The program selects its R and D priorities in a structured and objective way with much industry input to provide useful results for decisions in the 2014 to 2019 time frame. The program is highly collaborative with U.S. Department of Energy (DOE) and with EPRI-member utilities. The R and D portfolio includes materials aging (metals, concrete, and cables), modernization of information and control technology, enhanced safety analysis, advanced fuel design, demonstration plant activities, life cycle management, and identification of aging management program need for subsequent license renewal. The program has focussed stakeholders world-wide on the technical issues of long term operation, and it is on-track to provide practical results for life extension and license renewal decisions. (author)

  7. Human-system Interfaces to Automatic Systems: Review Guidance and Technical Basis

    Energy Technology Data Exchange (ETDEWEB)

    OHara, J.M.; Higgins, J.C.

    2010-01-31

    Automation has become ubiquitous in modern complex systems and commercial nuclear power plants are no exception. Beyond the control of plant functions and systems, automation is applied to a wide range of additional functions including monitoring and detection, situation assessment, response planning, response implementation, and interface management. Automation has become a 'team player' supporting plant personnel in nearly all aspects of plant operation. In light of the increasing use and importance of automation in new and future plants, guidance is needed to enable the NRC staff to conduct safety reviews of the human factors engineering (HFE) aspects of modern automation. The objective of the research described in this report was to develop guidance for reviewing the operator's interface with automation. We first developed a characterization of the important HFE aspects of automation based on how it is implemented in current systems. The characterization included five dimensions: Level of automation, function of automation, modes of automation, flexibility of allocation, and reliability of automation. Next, we reviewed literature pertaining to the effects of these aspects of automation on human performance and the design of human-system interfaces (HSIs) for automation. Then, we used the technical basis established by the literature to develop design review guidance. The guidance is divided into the following seven topics: Automation displays, interaction and control, automation modes, automation levels, adaptive automation, error tolerance and failure management, and HSI integration. In addition, we identified insights into the automaton design process, operator training, and operations.

  8. Torus II. Technical description of the design proposal

    International Nuclear Information System (INIS)

    Aymar, R.; Deck, C.; Deschamps, P.; Lafon, D.; Leloup, C.; Pariente, M.; Renaud, C.; Sledziewski, Z.; Torossian, A.

    1976-06-01

    A new Tokamak device, called TORUS II, is proposed to be built inside the EURATOM-CEA Association. This is a large machine: I=1.7MA; B=30kGs; R=1.8m; a=75cm, designed to be a successor to TFR and to follow the lines of research already initiated in the present TFR programme, i.e. on plasma heating, on impurities, on energy confinement and scaling laws, providing to JET a very efficient backing. This part of the report provides a technical description of the main components of the basic machine, according to the state of design reached in June 1976. Every subsystem whose assembly forms the basic machine is the subject of one section: vacuum vessel, toroidal field coils, poloidal field system, mechanical structures, monitoring, control and data acquisition, and power supplies. The first part in each section attempts to summarize the solution that was retained, pointing out the problems to be solved and the choice made. No contribution takes into account the problems of installation and buildings and the time schedule which is given is only concerned with the simplest solution. By way, contributions are given which show the state of development of the peripheral systems envisaged for TORUS II, mainly: additional heating, control of impurities and plasma diagnostics [fr

  9. Technical support document for proposed 1994 revision of the MEC thermal envelope requirements

    Energy Technology Data Exchange (ETDEWEB)

    Conner, C.C.; Lucas, R.G.

    1994-03-01

    This report documents the development of the proposed revision of the Council of American Building Officials` (CABO) 1994 supplement to the 1993 Model Energy Code (MEC) building thermal envelope requirements for maximum component U{sub 0}-value. The 1994 amendments to the 1993 MEC were established in last year`s code change cycle and did not change the envelope requirements. The research underlying the proposed MEC revision was conducted by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) Building Energy Standards program. The goal of this research was to develop revised guidelines based on an objective methodology that determines the most cost-effective (least total cost) combination of energy conservation measures (ECMs) (insulation levels and window types) for residential buildings. This least-cost set of ECMs was used as a basis for proposing revised MEC maximum U{sub 0}-values (thermal transmittances). ECMs include window types (for example, double-pane vinyl) and insulation levels (for example, R-19) for ceilings, walls, and floors.

  10. Basis of valve operator selection for SMART

    International Nuclear Information System (INIS)

    Kang, H. S.; Lee, D. J.; See, J. K.; Park, C. K.; Choi, B. S.

    2000-05-01

    SMART, an integral reactor with enhanced safety and operability, is under development for use of the nuclear energy. The valve operator of SMART system were selected through the data survey and technical review of potential valve fabrication vendors, and it will provide the establishment and optimization of the basic system design of SMART. In order to establish and optimize the basic system design of SMART, the basis of selection for the valve operator type were provided based on the basic design requirements. The basis of valve operator selection for SMART will be used as a basic technical data for the SMART basic and detail design and a fundamental material for the new reactor development in the future

  11. Basis of valve operator selection for SMART

    Energy Technology Data Exchange (ETDEWEB)

    Kang, H. S.; Lee, D. J.; See, J. K.; Park, C. K.; Choi, B. S

    2000-05-01

    SMART, an integral reactor with enhanced safety and operability, is under development for use of the nuclear energy. The valve operator of SMART system were selected through the data survey and technical review of potential valve fabrication vendors, and it will provide the establishment and optimization of the basic system design of SMART. In order to establish and optimize the basic system design of SMART, the basis of selection for the valve operator type were provided based on the basic design requirements. The basis of valve operator selection for SMART will be used as a basic technical data for the SMART basic and detail design and a fundamental material for the new reactor development in the future.

  12. Draft Function Allocation Framework and Preliminary Technical Basis for Advanced SMR Concepts of Operations

    Energy Technology Data Exchange (ETDEWEB)

    Hugo, Jacques [Idaho National Lab. (INL), Idaho Falls, ID (United States); Forester, John [Idaho National Lab. (INL), Idaho Falls, ID (United States); Gertman, David [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey [Idaho National Lab. (INL), Idaho Falls, ID (United States); Medema, Heather [Idaho National Lab. (INL), Idaho Falls, ID (United States); Persensky, Julius [Idaho National Lab. (INL), Idaho Falls, ID (United States); Whaley, April [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2013-08-01

    This report presents preliminary research results from the investigation into the development of new models and guidance for Concepts of Operations in advanced small modular reactor (AdvSMR) designs. AdvSMRs are nuclear power plants (NPPs), but unlike conventional large NPPs that are constructed on site, AdvSMRs systems and components will be fabricated in a factory and then assembled on site. AdvSMRs will also use advanced digital instrumentation and control systems, and make greater use of automation. Some AdvSMR designs also propose to be operated in a multi-unit configuration with a single central control room as a way to be more cost-competitive with existing NPPs. These differences from conventional NPPs not only pose technical and operational challenges, but they will undoubtedly also have regulatory compliance implications, especially with respect to staffing requirements and safety standards.

  13. Technical basis for the CANDU steam generator tube fitness-for-service guidelines

    International Nuclear Information System (INIS)

    Kozluk, M.J.; Scarth, D.A.; Graham, D.B.

    2002-01-01

    Active degradation mechanisms in steam generators and preheaters in Canadian CANDU T M generating stations are managed through Steam Generator Programs that incorporate tube inspection, maintenance (cleaning), fitness-for-service assessment, and preventative plugging as part of the overall steam generator management strategy. Steam generator and preheater tubes are inspected in accordance with the CSA Standard CAN/CSA-N285.4-94[l]. When a detected flaw indication does not satisfy the criteria of acceptance by examination, CSA-N285.4-94 permits a fitness-for-service assessment to determine acceptability. In 1999 Ontario Power Generation issued, for trial use, fitness-for-service guidelines for steam generator and preheater tubes in CANDU nuclear power plants. The main objectives of the Fitness-for-Service Guidelines are to provide reasonable assurance that tube structural integrity is maintained, and to provide reasonable assurance that there are adequate margins between estimated accumulated dose and applicable site dose limits. The Fitness-for-Service Guidelines are intended to provide industry-standard acceptance criteria and evaluation procedures for assessing the condition of steam generator and preheater tubes in terms of tube structural integrity, operational leak rate, and consequential leakage during an upset or abnormal event. This paper describes the technical basis for the minimum required safety factors specified in Table IC-1 of the Fitness-for-Service Guidelines and for the flaw models used to develop the flaw stability requirements in the nonmandatory, Appendix C of the Fitness-for-Service Guidelines. (author)

  14. The Architectural and Technical Consequences of Different Window Details in a Danish Passive House

    DEFF Research Database (Denmark)

    Brunsgaard, Camilla; Heiselberg, Per; Jensen, Rasmus Lund

    2008-01-01

     This paper focuses on a study of window details from "The Comfort Houses" in relation to "traditional" Danish construction solutions. The aim is to evaluate different ways of solving a window detail and to identify both architectural and technical consequences. It is important to investigate bot...... aspects of a detail because the best technical solution might not be the best architectural solution. A proposal from "The Comfort Houses" - a brick passive house, will be used as a basis....... This paper focuses on a study of window details from "The Comfort Houses" in relation to "traditional" Danish construction solutions. The aim is to evaluate different ways of solving a window detail and to identify both architectural and technical consequences. It is important to investigate both...

  15. Cognitive processes and neural basis of language switching: proposal of a new model.

    Science.gov (United States)

    Moritz-Gasser, Sylvie; Duffau, Hugues

    2009-12-09

    Although studies on bilingualism are abundant, cognitive processes and neural foundations of language switching received less attention. The aim of our study is to provide new insights to this still open question: do dedicated region(s) for language switching exist or is this function underlain by a distributed circuit of interconnected brain areas, part of a more general cognitive system? On the basis of recent behavioral, neuroimaging, and brain stimulation studies, we propose an original 'hodological' model of language switching. This process might be subserved by a large-scale cortico-subcortical network, with an executive system (prefrontal cortex, anterior cingulum, caudate nucleus) controlling a more dedicated language subcircuit, which involves postero-temporal areas, supramarginal and angular gyri, Broca's area, and the superior longitudinal fasciculus.

  16. Technical basis for environmental qualification of computer-based safety systems in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Tanaka, T.J.; Antonescu, C.E.

    1997-01-01

    This paper summarizes the results of research sponsored by the US Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. This research was conducted by the Oak Ridge National Laboratory (ORNL) and Sandia National Laboratories (SNL). ORNL investigated potential failure modes and vulnerabilities of microprocessor-based technologies to environmental stressors, including electromagnetic/radio-frequency interference, temperature, humidity, and smoke exposure. An experimental digital safety channel (EDSC) was constructed for the tests. SNL performed smoke exposure tests on digital components and circuit boards to determine failure mechanisms and the effect of different packaging techniques on smoke susceptibility. These studies are expected to provide recommendations for environmental qualification of digital safety systems by addressing the following: (1) adequacy of the present preferred test methods for qualification of digital I and C systems; (2) preferred standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging in qualification testing for equipment that is to be located in mild environments; and (5) determination of an appropriate approach to address smoke in a qualification program

  17. Understanding and capturing NSSS design basis

    International Nuclear Information System (INIS)

    Palo, W.J.; Miller, B.

    1993-01-01

    Changes to, and technical evaluations of nuclear generating station designs are often warranted. Comprehensive documentation and understanding of the NSSS Design Basis are essential to support these activities. Effective configuration management tools are also needed to maintain the plant within design basis limits. Efficient design basis reconstitution can be realized via: In-depth understanding of the design process; Utilization of effective data collection methodology; State of the art data basing tools. A database can be created to generate a Design Basis Manual (DBM). This database can communicate electronically with other plant databases. A living document vice a static snapshot of the plant design is the goal. A design basis database can serve as the cornerstone for a global electronic information control system

  18. Program of scientific investigations and development of solid-oxide fuel cells (SOFC) in VNIITF. Proposals on scientific and technical collaboration and SOFC commercialization

    Energy Technology Data Exchange (ETDEWEB)

    Kleschev, Yu.N.; Chukharev, V.F.

    1996-04-01

    This paper describes proposals on scientific and technical collaborations pertaining to solid oxide fuel cell commercialization. Topics included for discussion are: materials research and manufacture; market estimation and cost; directions of collaboration; and project of proposals on joint enterprise creation.

  19. Technical Proposal Salton Sea Geothermal Power Pilot Plant Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1975-03-28

    The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical and technical point-of-view; preliminary design of mineral recovery and brine clean-up facilities of sufficient size to match the planned pilot power plant. The Reservoir Production Subprogram will include monitoring the operation and maintenance of brine production, handling and injection systems which were built with private funding in phase 0, and monitoring of the brine characteristics and potential subsidence effects during well production and injection. Based on the above, recommendations and specifications will be prepared for production and

  20. Technical Proposal for the Phase-II Upgrade of the CMS Detector

    CERN Document Server

    CMS Collaboration; Contardo, D; Klute, M; Mans, J; Silvestris, L; Butler, J; CERN. Geneva. The LHC experiments Committee; LHCC

    2015-01-01

    This Technical Proposal presents the upgrades foreseen to prepare the CMS experiment for the High Luminosity LHC. In this second phase of the LHC physics program, the accelerator will provide to CMS an additional integrated luminosity of about 2500 fb-1 over 10 years of operation, starting in 2025. This will substantially enlarge the mass reach in the search for new particles and will also greatly extend the potential to study the properties of the Higgs boson discovered at the LHC in 2012. In order to meet the experimental challenges of unprecedented p-p luminosity, the CMS collaboration will need to address the aging of the present detector and to improve the ability of the apparatus to isolate and precisely measure the products of the most interesting collisions. This document describes the conceptual designs and the expected performance of the upgrades, along with the plans to develop the appropriate experimental techniques. The infrastructure upgrades and the logistics of the installation in the experim...

  1. Technical Details on Beyond Design Basis Event Pilot Evaluations

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2013-01-01

    The primary focus of the BDBE pilot project was the review of BDBE analysis and mitigation features at four DOE nuclear facilities representing a range of DOE sites, nuclear facility types/activities, and responsible program offices. The pilots looked at (1) how beyond design basis accidents were evaluated and documented in the facility Documented Safety Analysis, (2) potential BDBE vulnerabilities and margins to failure of facility safety features as obtained from general area and specific system walkdowns and design documents reviews, and (3) preparations made in facility and site emergency management programs to respond to severe accidents. It also evaluated whether draft BDBE guidance on safety analysis and emergency management could be used to improve the analysis of and preparations for mitigating severe and beyond design basis accidents. The details of these activities are organized in this report as described below.

  2. Postclosure risks at the proposed Yucca Mountain repository: A review of methodological and technical issues

    International Nuclear Information System (INIS)

    Emel, J.; Kasperson, R.E.; Goble, R.; Renn, O.

    1988-06-01

    Accordingly, the first section of the report provides an overview and critique of the risk analysis methodology proposed by the US Department of Energy (DOE 1988) in the Draft Site Characterization Plan (SCP) and related documents. The second section addresses specific technical problems associated with the site. Each section considers the significance or implications of the issues for the successful long-term isolation of radioactive wastes from the biosphere. We conclude with overall observations on the adequacy of current understandings and approaches in the waste disposal program and implications for the State of Nevada

  3. Final report on a study of coherence in acceptability criteria for the technical aspects of risks associated with potentially hazardous installations

    International Nuclear Information System (INIS)

    Chicken, J.C.

    1988-01-01

    This report describes the results of the study that was made, under Contract No ECI-1390-B7221-85D, for the European Atomic Energy Community. The aim of the study was to examine and assess the feasibility of developing coherent and uniform criteria for judging the acceptability of the technical aspects of the risks associated with potentially hazardous installations. The report is arranged in five main parts. First the nature of hazardous installations is considered and this provides the basis for examination of the currently-used technical risk acceptability criteria. Next, the possible forms of criteria are explored and then universally consistent partial and overall technical risk acceptability criteria are proposed. Following this the implications of using the criteria proposed at the design, regulatory and operating levels are examined. Then, by testing the criteria against some real decisions, the practical problems of using the proposed criteria are explored. This leads to consideration of possible alternatives to the proposed criteria. Finally the conclusions that appear to be justified are summarized and the need for further work is identified

  4. Technical endoscopy

    International Nuclear Information System (INIS)

    Cavalar, K.O.

    1988-01-01

    A survey is provided on different versions of endoscopes, taking into account the new developments of video endoscopy. With a variety of practical examples it is shown that technical tests using endoscopy are a demanding task for nondestructive testing, whose requirements can only be met on a customized basis. (orig./HP) [de

  5. Technical basis for instrumentation and control design improvements in WWER-440/230 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-01-01

    Instrumentation and control (I and C) has been recognized as an area which requires substantial improvements in WWER NNPs, particularly for model 230 plants. Under contract with the IAEA the Spanish company Empresarios Agrupados (EA) developed a basic document proposing a technical basis for improvements related to the following most significant aspects of I and C: criteria for safety classification; remote shutdown panel; I and C support to operation and control room design; instrumentation set point margins; accident monitoring instrumentation. This publication is derived from the original report of EA which was circulated by the IAEA for review by staff members and experts from various Member States. It was finally agreed upon at a Consultants' meeting convened by the IAEA in Vienna in May 1994 with the participation of experts from France, Germany and Spain. The guidance expressed in this report is based on the IAEA/NUSS standards, safety guides and practices, and on regulations in use in various Member States. It is proposed as a way of carrying out the necessary studies to improve safety by upgrading the vital part of instrumentation an control in WWER-440 model 230 nuclear power plants. 28 refs, 3 figs

  6. A tax proposal for a cash flow corporate tax

    Directory of Open Access Journals (Sweden)

    Lourdes Jerez Barroso

    2013-12-01

    Full Text Available Purpose: Due to its advantages in terms of neutrality and simplicity, the aim of this paper is to design a tax base for corporation cash flows, as well as to develop its practical implementation.Design/Methodology: The conceptual aspects and the background of tax on corporation tax flows are reviewed and a tax base that levies a charge on the corporation’s economical activities’ cash flow is then proposed. In order to carry this out, a methodological procedure is developed on the basis of the accounting documents that companies must present and through which the stock variables and the accounting documents’ work flow is transformed into cash flow.Findings: An implementation on the basis of the accounting documents that Spanish companies must present. Practical Implications: This paper defines the procedure to follow in order to determine the tax base of a cash flow corporate income tax on the basis of its accounts, which would allow an estimation of this tax figure’s revenue impact.Originality/ Value: The design of a tax base of cash flows for companies. The accounting approximation carried out to determine the cash flows justifies the fact that the tax base proposal is technically possible.

  7. Optimization of technical specifications by use of probabilistic methods

    International Nuclear Information System (INIS)

    Laakso, K.

    1990-01-01

    The Technical Specifications of a nuclear power plant specify the limits for plant operation from the safety point of view. These operational safety rules were originally defined on the basis of deterministic analyses and engineering judgement. As experience has accumulated, it has proved necessary to consider problems and make specific modifications in these rules. Developments in probabilistic safety assessment have provided a new tool to analyse, present and compare the risk effects of proposed rule modificatons. The main areas covered in the project are operational decisions in failure situations, preventive maintenance during power operation and surveillance tests of standby safety systems. (author)

  8. Proposed goals for radioactive waste management

    International Nuclear Information System (INIS)

    Bishop, W.P.; Hoos, I.R.; McGrath, P.E.; Metlay, D.S.; Stoneman, W.C.

    1978-05-01

    A special, seven member, interdisciplinary task group of consultants was established in January 1976 to propose goals for the national waste management program. This is the report of that group. The proposed goals are intended as a basis for the NRC to establish a policy by which to guide and coordinate the activities of government, business, and academic organizations whose responsibility it will be to manage radioactive wastes. The report is based on findings, interpretations and analysis by the authors who examined selected primary literature and interviewed many individuals concerned with waste management. The authors extended the scope of their inquiry and proposed goals to cover 'all technical and societal aspects necessary to an operating waste management system, rather than dealing with the regulatory process alone.' The waste management goals as developed are simple statements of principles which appear to the authors to be important conditions to insure the proper establishment and operation of a system to manage radioactive wastes.' In brief, the goals are designed to protect people and things of value in an equitable manner

  9. Technical Basis for Radiological Emergency Plan Annex for WTD Emergency Response Plan: West Point Treatment Plant

    Energy Technology Data Exchange (ETDEWEB)

    Hickey, Eva E.; Strom, Daniel J.

    2005-08-01

    Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document, Volume 3 of PNNL-15163 is the technical basis for the Annex to the West Point Treatment Plant (WPTP) Emergency Response Plan related to responding to a radiological emergency at the WPTP. The plan primarily considers response to radioactive material that has been introduced in the other combined sanitary and storm sewer system from a radiological dispersion device, but is applicable to any accidental or deliberate introduction of materials into the system.

  10. TurboTech Technical Evaluation Automated System

    Science.gov (United States)

    Tiffany, Dorothy J.

    2009-01-01

    TurboTech software is a Web-based process that simplifies and semiautomates technical evaluation of NASA proposals for Contracting Officer's Technical Representatives (COTRs). At the time of this reporting, there have been no set standards or systems for training new COTRs in technical evaluations. This new process provides boilerplate text in response to interview style questions. This text is collected into a Microsoft Word document that can then be further edited to conform to specific cases. By providing technical language and a structured format, TurboTech allows the COTRs to concentrate more on the actual evaluation, and less on deciding what language would be most appropriate. Since the actual word choice is one of the more time-consuming parts of a COTRs job, this process should allow for an increase in quantity of proposals evaluated. TurboTech is applicable to composing technical evaluations of contractor proposals, task and delivery orders, change order modifications, requests for proposals, new work modifications, task assignments, as well as any changes to existing contracts.

  11. 77 FR 46658 - Proposed Priority; Technical Assistance To Improve State Data Capacity-National Technical...

    Science.gov (United States)

    2012-08-06

    ... Assistance To Improve State Data Capacity--National Technical Assistance Center To Improve State Capacity To... and later years. We take this action to focus attention on an identified national need to provide TA to improve the capacity of States to meet the data collection requirements of the Individuals with...

  12. Aspects of the role of scientific-technical expert knowledge in administrative court procedures on licensing of large technical projects

    International Nuclear Information System (INIS)

    Wagner, H.

    1983-01-01

    On the basis of atomic energy law, the author explains some specific problems associated with the respective roles of experts (or expert bodies) and courts of law. In legal theory, it is comparatively easy to draw the line between the two functions, but in practice this delimination meets with difficulties. Finally, the author proposes to improve the definitions of the respective functions of experts (expert bodies) and courts of law in procedures dealing with permits of large technical facilities as follows: A highly qualified, independent body of experts in a technically representative composition lays down, in a binding way, the main elements of the safety standard of a specific plant or type of plant. The responsible administrative authority, after having examined all other legal conditions, grants the permit for that plant. There are no objections to such a model in the light either of aspects of constitutional law or of legal policy or constitutional policy, not are there any practical reasons against this approach. The only doubtful aspect is the present political feasibility. (orig.) [de

  13. Application of Microprocessor-Based Equipment in Nuclear Power Plants - Technical Basis for a Qualification Methodology

    International Nuclear Information System (INIS)

    Korsah, K.

    2001-01-01

    This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instrumentation and Control (I and C) Systems'' program initiated by the Nuclear Regulatory Commission (NRC); (2) documents a comparative analysis of U.S. and European qualification standards; and (3) provides recommendations for enhancing regulatory guidance for environmental qualification of microprocessor-based safety-related systems. Safety-related I and C system upgrades of present-day nuclear power plants, as well as I and C systems of Advanced Light-Water Reactors (ALWRs), are expected to make increasing use of microprocessor-based technology. The Nuclear Regulatory Commission (NRC) recognized that the use of such technology may pose environmental qualification challenges different from current, analog-based I and C systems. Hence, it initiated the ''Qualification of Advanced Instrumentation and Control Systems'' program. The objectives of this confirmatory research project are to (1) identify any unique environmental-stress-related failure modes posed by digital technologies and their potential impact on the safety systems and (2) develop the technical basis for regulatory guidance using these findings. Previous findings from this study have been documented in several technical reports. This final report in the series documents a comparative analysis of two environmental qualification standards--Institute of Electrical and Electronics Engineers (IEEE) Std 323-1983 and International Electrotechnical Commission (IEC) 60780 (1998)--and provides recommendations for environmental qualification of microprocessor-based systems based on this analysis as well as on the findings documented in the previous reports. The two standards were chosen for this analysis because IEEE 323 is the standard used in the U.S. for the qualification of safety-related equipment in nuclear power plants, and IEC 60780 is its European counterpart. In addition, the IEC document was published in

  14. 75 FR 75453 - Proposed Information Collection; Comment Request; Technical Data Letter of Explanation

    Science.gov (United States)

    2010-12-03

    ... Request; Technical Data Letter of Explanation AGENCY: Bureau of Industry and Security. ACTION: Notice....gov . SUPPLEMENTARY INFORMATION: I. Abstract These technical data letters of explanation will assure the Bureau of Industry and Security that U.S.-origin technical data will be exported only for...

  15. Lowest Price, Technically Acceptable Evaluation Criteria Used in the November 2014 Request for Proposal for the Program Executive Office Soldier Systems Engineering and Technical Assistance (SETA) Contract

    Science.gov (United States)

    2017-09-01

    GS-0895-09 Industrial Engineering Technician 23.04 7.56 GS-0810-09 Civil Engineering Developmental (Programming) 23.04 7.56 GS-0810-11 Civil ... Engineering –Programming 27.88 9.14 GS-0810-12 Civil Engineering –Design 33.41 10.96 GS-2210-09 Info Tech Spec (Network Systems/Customer Support) 23.04...USED IN THE NOVEMBER 2014 REQUEST FOR PROPOSAL FOR THE PROGRAM EXECUTIVE OFFICE SOLDIER SYSTEMS ENGINEERING AND TECHNICAL ASSISTANCE (SETA) CONTRACT

  16. ITER technical advisory committee meeting

    International Nuclear Information System (INIS)

    Fujiwara, M.

    1999-01-01

    The ITER Technical Advisory Committee (TAC) meeting took place on December 20-22, 1999 at the Naka Joint Work Site. The objective of this meeting was to review the document 'Technical Basis for ITER-FEAT Outline Design (ODR)' issued by the Director on December 10. It was also aimed at providing the ITER Meeting scheduled for January 19-20, 2000 in Tokyo with a technical assessment of ODR and recommendations for the optimization of the anticipated plasma performance and engineering design, based on the guidelines approved by the Council in June 1998 and recommendations of the last TAC meeting

  17. A Technical Mode for Sharing and Utilizing Open Educational Resources in Chinese Universities

    Directory of Open Access Journals (Sweden)

    Juan Yang

    2011-09-01

    Full Text Available Open educational resources just supply potentials to help equalize the access to worldwide knowledge and education, but themselves alone do not cause effective learning or education. How to make effective use of the resources is still a big challenge. In this study, a technical mode is proposed to collect the open educational resources from different sources on the Internet into a campus-network-based resource management system. The system facilitates free and easy access to the resources for instructors and students in universities and integrates the resources into learning and teaching. The technical issues regarding the design the resource management system are examined, including the structure and functions of the system, metadata standard compatibility and scalability, metadata file format, and resource utilization assessment. Furthermore, the resource collecting, storage and utilization modes are also discussed so as to lay a technical basis for extensive and efficient sharing and utilization of the OER in Chinese universities.

  18. Technical Standards for Nursing Education Programs in the 21st Century.

    Science.gov (United States)

    Ailey, Sarah H; Marks, Beth

    The Institute of Medicine (2000, 2002) exposed serious safety problems in the health system and called for total qualitative system change. The Institute of Medicine (2011, 2015) also calls for improving the education of nurses to provide leadership for a redesigned health system. Intertwined with improving education is the need to recruit and retain diverse highly qualified students. Disability is part of diversity inclusion, but current technical standards (nonacademic requirements) for admission to many nursing programs are a barrier to the entry of persons with disabilities. Rehabilitation nurse leaders are in a unique position to improve disability diversity in nursing. The purpose of this paper is to discuss the importance of disability diversity in nursing. The history of existing technical standards used in many nursing programs is reviewed along with examples. On the basis of the concept that disability inclusion is a part of diversity inclusion, we propose a new model of technical standards for nursing education. Rehabilitation nurse leaders can lead in eliminating barriers to persons with disabilities entering nursing.

  19. 75 FR 6166 - Basis Reporting by Securities Brokers and Basis Determination for Stock

    Science.gov (United States)

    2010-02-08

    ... DEPARTMENT OF THE TREASURY Internal Revenue Service 26 CFR Parts, 1, 31, and 301 [REG-101896-09] RIN 1545-Bl66 Basis Reporting by Securities Brokers and Basis Determination for Stock Correction In proposed rule document E9-29855 beginning on page 67010 in the issue of Thursday, December 17, 2009, make...

  20. Technical basis and programmatic requirements for large block testing of coupled thermal-mechanical-hydrological-chemical processes

    International Nuclear Information System (INIS)

    Lin, Wunan.

    1993-09-01

    This document contains the technical basis and programmatic requirements for a scientific investigation plan that governs tests on a large block of tuff for understanding the coupled thermal- mechanical-hydrological-chemical processes. This study is part of the field testing described in Section 8.3.4.2.4.4.1 of the Site Characterization Plan (SCP) for the Yucca Mountain Project. The first, and most important objective is to understand the coupled TMHC processes in order to develop models that will predict the performance of a nuclear waste repository. The block and fracture properties (including hydrology and geochemistry) can be well characterized from at least five exposed surfaces, and the block can be dismantled for post-test examinations. The second objective is to provide preliminary data for development of models that will predict the quality and quantity of water in the near-field environment of a repository over the current 10,000 year regulatory period of radioactive decay. The third objective is to develop and evaluate the various measurement systems and techniques that will later be employed in the Engineered Barrier System Field Tests (EBSFT)

  1. Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility

    International Nuclear Information System (INIS)

    Gates, R.; Glukhov, A.; Markowski, F.

    1996-06-01

    This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes

  2. Nagra technical report 14-02, Geological basics - Dossier VI - Barrier properties of proposed host rock sediments and neighbouring rock

    International Nuclear Information System (INIS)

    Gautschi, A.; Deplazes, G.; Traber, D.; Marschall, P.; Mazurek, M.; Gimmi, T.; Maeder, U.

    2014-01-01

    This dossier is the sixth of a series of eight reports concerning the safety and technical aspects of locations for the disposal of radioactive wastes in Switzerland. It discusses the barrier properties of the proposed host rock sediments and neighbouring rock layers. The mineralogical composition of the host rocks are discussed as are their pore densities and hydrological properties. Diffusion aspects are discussed. The aquifer systems in the proposed depository areas and their classification are looked at. The barrier properties of the host rocks and those of neighbouring sediments are discussed. Finally, modelling concepts and parameters for the transport of radionuclides in the rocks are discussed

  3. Physical and technical basis of positron emission tomography (PET)

    International Nuclear Information System (INIS)

    Bauer, R.

    1994-01-01

    Positron emission tomography utilizes the annihilation of positrons, generating pairs of gamma quanta which are emitted in opposing directions. 'Electronic collimation' is performed by coincident detection of both quanta. Thus, there is no need for mechanical collimators and no limiting connection between sensitivity and spatial resolution. Transversal tomograms are reconstructed from the projection data by means of highly sophisticated data processing. The half life of the most positron emitters used in medical applications is short and of the order of some minutes. Therefore, many positron emitters have to be produced on-side by means of a cyclotron. PET is superior to SPECT with respect to physical and technical aspects, but the high costs of PET limit its wide-spread use up to now. (orig.) [de

  4. Voltage Spectral Structure as a Parameter of System Technical Diagnostics of Ship Diesel Engine-Synchronous Generators

    Directory of Open Access Journals (Sweden)

    Gasparjans Aleksandrs

    2015-07-01

    Full Text Available A method of technical diagnostics of ship diesel engine – generator installation – is proposed. Spectral-power diagnostic parameters of the synchronous generator voltage and currents are used. The electric machine in this case is the multipurpose sensor of diagnostic parameters. A judgment on the quality of the operational processes in diesel engine cylinders and its technical condition is possible on the basis of these parameters. This method is applicable to piston compressor installations with electric drive. On the basis of such parameters as rotating torque, angular speed and angular acceleration it is possible to estimate the quality of the operating process in the cylinders of a diesel engine, the condition of its cylinder-piston group and the crank gear mechanism. The investigation was realized on the basis of a diesel-generator with linear load. The generator operation was considered for the case of constant RL load. Together with the above mentioned, the condition of bearings of synchronous machines, uniformity of the air gap, windings of the electric machine were estimated during the experiments as well. The frequency spectrum of the stator current of the generator was researched and analyzed. In this case the synchronous machine is becoming a rather exact multipurpose diagnostic sensor. The signal of non-uniformity in the operation process of diesel engine cylinders and its technical condition is the increasing of the amplitudes of typical frequencies.

  5. Re-evaluation of the technical basis for the regulation of pressurized thermal shock in U.S. pressurized water reactor vessels

    Energy Technology Data Exchange (ETDEWEB)

    Malik, S.N.; Kirk, M.T.; Jackson, D.A.; Hackett, E.M.; Chokshi, N.C.; Siu, N.O.; Woods, H.W.; Bessette, D.E. [Office of Nuclear Regulatory Research, U.S. nuclear Regulatory Commission, Washington, D.C. (United States); Dickson, T.L. [Oak Ridge National Lab., Computational Physics and Engineering Div., Oak Ridge, TN (United States)

    2001-07-01

    The current federal regulation to insure that pressurized-water nuclear reactor pressure vessels (RPVs) maintain their structural integrity when subjected to potential pressurized thermal shock (PTS) events during the life of the plant were derived from computational models and technologies that were developed in the early-to-mid 1980's. Since that time, there have been several advancements and refinements to the relevant fracture technology, materials characterization methods, probabilistic risk assessment (PRA) and thermal-hydraulics (TH) computational methods. Preliminary studies performed in 1998 (that applied this new technology) indicated the potential that technical bases can be established to support a relaxation of the current federal regulation (10 CFR 50.61) for PTS. A revision of PTS regulation could have significant implications for plants reaching their end-of-license periods and future plant license-extension considerations. Based on the above, in 1999, the United States Nuclear Regulatory Commission initiated a comprehensive project, with the nuclear industry as a participant, to revisit the technical bases for the current regulations on PTS. This paper provides an overview and status of the methodology that has evolved over the last two years through interactions between experts in relevant disciplines (TH, PRA, materials and fracture mechanics, and non-destructive and destructive examination to predict distribution of fabrication induced flaws in the belt-line region of the PWR vessels) from the NRC staff, their contractors, and representatives from the nuclear industry. This updated methodology is currently being implemented into the FAVOR (Fracture Analysis of Vessels: Oak Ridge) computer code for application to re-examine the adequacy of the current regulations and to determine if technical basis can be established for relaxing the current regulation. It is anticipated that the effort will be completed in 2002. (authors)

  6. Re-evaluation of the technical basis for the regulation of pressurized thermal shock in U.S. pressurized water reactor vessels

    International Nuclear Information System (INIS)

    Malik, S.N.; Kirk, M.T.; Jackson, D.A.; Hackett, E.M.; Chokshi, N.C.; Siu, N.O.; Woods, H.W.; Bessette, D.E.; Dickson, T.L.

    2001-01-01

    The current federal regulation to insure that pressurized-water nuclear reactor pressure vessels (RPVs) maintain their structural integrity when subjected to potential pressurized thermal shock (PTS) events during the life of the plant were derived from computational models and technologies that were developed in the early-to-mid 1980's. Since that time, there have been several advancements and refinements to the relevant fracture technology, materials characterization methods, probabilistic risk assessment (PRA) and thermal-hydraulics (TH) computational methods. Preliminary studies performed in 1998 (that applied this new technology) indicated the potential that technical bases can be established to support a relaxation of the current federal regulation (10 CFR 50.61) for PTS. A revision of PTS regulation could have significant implications for plants reaching their end-of-license periods and future plant license-extension considerations. Based on the above, in 1999, the United States Nuclear Regulatory Commission initiated a comprehensive project, with the nuclear industry as a participant, to revisit the technical bases for the current regulations on PTS. This paper provides an overview and status of the methodology that has evolved over the last two years through interactions between experts in relevant disciplines (TH, PRA, materials and fracture mechanics, and non-destructive and destructive examination to predict distribution of fabrication induced flaws in the belt-line region of the PWR vessels) from the NRC staff, their contractors, and representatives from the nuclear industry. This updated methodology is currently being implemented into the FAVOR (Fracture Analysis of Vessels: Oak Ridge) computer code for application to re-examine the adequacy of the current regulations and to determine if technical basis can be established for relaxing the current regulation. It is anticipated that the effort will be completed in 2002. (authors)

  7. Spent Nuclear Fuel (SNF) Project Safety Basis Implementation Strategy

    International Nuclear Information System (INIS)

    TRAWINSKI, B.J.

    2000-01-01

    The objective of the Safety Basis Implementation is to ensure that implementation of activities is accomplished in order to support readiness to move spent fuel from K West Basin. Activities may be performed directly by the Safety Basis Implementation Team or they may be performed by other organizations and tracked by the Team. This strategy will focus on five key elements, (1) Administration of Safety Basis Implementation (general items), (2) Implementing documents, (3) Implementing equipment (including verification of operability), (4) Training, (5) SNF Project Technical Requirements (STRS) database system

  8. Towards technical interoperability in telemedicine.

    Energy Technology Data Exchange (ETDEWEB)

    Craft, Richard Layne, II

    2004-05-01

    For telemedicine to realize the vision of anywhere, anytime access to care, the question of how to create a fully interoperable technical infrastructure must be addressed. After briefly discussing how 'technical interoperability' compares with other types of interoperability being addressed in the telemedicine community today, this paper describes reasons for pursuing technical interoperability, presents a proposed framework for realizing technical interoperability, identifies key issues that will need to be addressed if technical interoperability is to be achieved, and suggests a course of action that the telemedicine community might follow to accomplish this goal.

  9. 76 FR 23641 - Proposed Information Collection: Export Declaration of Defense Technical Data or Services

    Science.gov (United States)

    2011-04-27

    ... Defense Technical Data or Services AGENCY: Department of State. ACTION: Notice of request for public... Declaration of Defense Technical Data or Services. OMB Control Number: 1405-0157. Type of Request: Extension... of defense technical data and defense services will be electronically reported directly to the...

  10. BWR NSSS design basis documentation

    International Nuclear Information System (INIS)

    Vij, R.S.; Bates, R.E.

    2004-01-01

    In 1985 an incident at Toledo Edison's Davis Besse plant caused the U.S. Nuclear Regulatory Commission (NRC) to re-evaluate the technical information that the utilities had readily available to support the design of their plants. The Design Basis programs, currently on going in most U.S. utilities, have been the nuclear industry's response to the needs identified by this re-evaluation. In order to understand the Design Basis programs which have been implemented by the U.S. nuclear utilities, it is necessary to understand the problem as it was perceived by the nuclear industry (the utilities, the original NSSS designers and the regulators) after the Davis-Besse incident, the subsequent programs undertaken by the industry under the leadership of INPO and NUMARC, the NRC's actions, and the overall evolution of the industry's vision in relation to this problem. This paper presents the history of the design basis efforts from the first recognition of the problem by the NRC after the Davis-Besse incident, describes the actions taken by the NRC, INPO, NUMARC, the U.S. utilities and the NSSS designers, and brings the problem statement up-to-date in relation to the vision presently held by the U.S. nuclear industry. It then presents a technical discussion to develop a detailed definition of design basis information to support the problem statement. The information originally supplied by the NSSS designers during the plant design and construction is discussed as well as its relationship to the previously defined design basis information. This section of the paper concludes by defining the additional information needed by nuclear utilities to satisfy the requirements developed from the problem statement. Having developed a definition of the additional information (i.e., information not originally supplied during design and construction) required to solve the design basis problem as it is presently perceived by the U.S. nuclear industry, the paper then discusses design basis

  11. Proposing a Technical Solution for Restoring Longitudinal Connectivity in the Brădeni/Retiş Accumulation Area on Hârtibaciu River

    Directory of Open Access Journals (Sweden)

    Voicu Răzvan

    2016-04-01

    Full Text Available The fish fauna of the Hârtibaciu River has experienced a disrupted connectivity due to the hydrotechnical works and the Brădeni/Retiş Dam located across the Hârtibaciu watercourse being one of this significant obstacles. The newly proposed constructed wetlands can improve the habitat quality for the fish species of conservative interest sampled in the Brădeni/Retiş Dam proximity Rhodeus amarus, and can increase the individuals’ number of this population. Also can benefit the local populations of Phoxinus phoxinus and Gobio obtusirostris. Using gravitational force and also the underground layout, a proposed technical solution gives maximum safety regarding the water supply for the newly proposed to be created wetlands.

  12. Human System Simulation in Support of Human Performance Technical Basis at NPPs

    Energy Technology Data Exchange (ETDEWEB)

    David Gertman; Katya Le Blanc; alan mecham; william phoenix; Magdy Tawfik; Jeffrey Joe

    2010-06-01

    This paper focuses on strategies and progress toward establishing the Idaho National Laboratory’s (INL’s) Human Systems Simulator Laboratory at the Center for Advanced Energy Studies (CAES), a consortium of Idaho State Universities. The INL is one of the National Laboratories of the US Department of Energy. One of the first planned applications for the Human Systems Simulator Laboratory is implementation of a dynamic nuclear power plant simulation (NPP) where studies of operator workload, situation awareness, performance and preference will be carried out in simulated control rooms including nuclear power plant control rooms. Simulation offers a means by which to review operational concepts, improve design practices and provide a technical basis for licensing decisions. In preparation for the next generation power plant and current government and industry efforts in support of light water reactor sustainability, human operators will be attached to a suite of physiological measurement instruments and, in combination with traditional Human Factors Measurement techniques, carry out control room tasks in simulated advanced digital and hybrid analog/digital control rooms. The current focus of the Human Systems Simulator Laboratory is building core competence in quantitative and qualitative measurements of situation awareness and workload. Of particular interest is whether introduction of digital systems including automated procedures has the potential to reduce workload and enhance safety while improving situation awareness or whether workload is merely shifted and situation awareness is modified in yet to be determined ways. Data analysis is carried out by engineers and scientists and includes measures of the physical and neurological correlates of human performance. The current approach supports a user-centered design philosophy (see ISO 13407 “Human Centered Design Process for Interactive Systems, 1999) wherein the context for task performance along with the

  13. Control and diagnostics of technical state of main electro technical and thermal equipment of NPP, TPS and HPS on the basis of thermovision technologies

    International Nuclear Information System (INIS)

    Banduryan, B.B.; Fedorenko, G.M.; Ostapchuk, L.B.; Saratov, V.O.

    2006-01-01

    The opportunity of using of thermovision technologies for detection of defects NPP, TPS and HPS electro technical and power equipment is shown. The results of thermovision monitoring of a turbine generator stator technical state are represented. The method for thermovision control of a technical state of a electrical machines and apparatus construction elements, for which the patent of Ukraine have been obtained, is described. he verification of the offered expedient thermovision control and diagnostics at 'Elektrovazhmash' factory was carried out

  14. Mixtures of truncated basis functions

    DEFF Research Database (Denmark)

    Langseth, Helge; Nielsen, Thomas Dyhre; Rumí, Rafael

    2012-01-01

    In this paper we propose a framework, called mixtures of truncated basis functions (MoTBFs), for representing general hybrid Bayesian networks. The proposed framework generalizes both the mixture of truncated exponentials (MTEs) framework and the mixture of polynomials (MoPs) framework. Similar t...

  15. Non-technical skills for scrub practitioners.

    Science.gov (United States)

    McClelland, Guy

    2012-12-01

    The non-technical skills of situational awareness and the formation of effective interpersonal relationships are essential to enhance surgical outcomes. However, most scrub practitioners demonstrate only tacit awareness of these skills and develop such qualities on an informal basis. Application of non-technical skills may be assessed formally, using a structured framework, to transform normative behaviour and to strengthen barriers against the latent threats that may result from fallible humans working in inadequate organisational systems.

  16. A technical basis to relax the dew point specification for the environment in the vapor space in DWPF canisters

    International Nuclear Information System (INIS)

    Louthan, M.R. Jr.

    1995-05-01

    This memorandum establishes the technical basis to conclude that relaxing, from 0 C to 20 C, the dew point specification for the atmosphere in the vapor space (free volume) of a DWPF canister will not provide an environment that will cause significant amounts of corrosion induced degradation of the canister wall. The conclusion is based on engineering analysis, experience and review of the corrosion literature. The basic assumptions underlying the conclusion are: (1) the canister was fabricated from Type 304L stainless steel; (2) the corrosion behavior of the canister material, including base metal, fusion zones and heat effected zones, is typified by literature data for, and industrial experience with, 300 series austenitic stainless steels; and (3) the glass-metal crevices created during the pouring operation will not alter the basic corrosion resistance of the steel although such crevices might serve as sites for the initiation of minor amounts of corrosion on the canister wall

  17. ATR Technical Specification Upgrade Program

    International Nuclear Information System (INIS)

    McCracken, R.T.; Durney, J.L.; Freund, G.A.

    1990-01-01

    The Advanced Test Reactor (ATR) is a 250 MW, uranium-aluminum fueled test reactor which began full power operation in 1969. The initial operation was controlled by an Operating Limits document based on the original Safety Analysis Report. Additional safety bases were later developed to support Technical Specifications which were approved and implemented in 1977. The Technical Specifications which were initially developed with content and format specified in ANSI/ANS--15.1, ''The Development of Technical Specifications for Research Reactors.'' The safety basis documentation and the Technical Specifications have been updated as required to maintain them current with the ATR facility configuration. All revisions have been made with a content, format and style consistent with the original. A major, two-phase program to upgrade the content, format and style is in progress. This paper describes the first phase of this program

  18. ON ASSESSMNENT OF PHYSICAL WEAR IN ELEMENTS OF TECHNICAL DEVICES

    Directory of Open Access Journals (Sweden)

    S. N. Osipov

    2015-01-01

    Full Text Available Real assessment of wear in technical devices, construction structures, minings, their elements and connections is of great importance for provision of operational security and efficiency. Natural properties of the overwhelming majority of materials follow to probabilistic (stochastic laws due to various reasons (external influence, processing technologies and others. An assessment of physical wear rate of buildings and structures and their elements is carried out in the former republics of the USSR mainly in accordance with external physical signs (deflections, cracks, layer separations, etc. but wear percentage is often calculated on the basis of replacement cost in comparison with the initial one even without taking into account inflation which did not officially exist in the USSR. In this case destruction or failure of structure or their elements are considered as 100 % wear.The paper proposes a new methodology for assessment of physical wear rate in accordance with probability ratio of nofailure operation (reliability, minimum ratio is assigned to admissible limit value in conformity with technical requirements for the technical devices, construction structures, minings in question, their elements and connections. In this context minimum permissible wear probability (reliability is taken as 100 % wear rate and its initial index is considered as 0 % wear rate. That is why wear intensity in time depends on type of value probability distribution while determining the rate of physical property. The proposed methodology is intended for probabilistic wear assessment in case of relatively simple changes in strength properties of materials (for example, within the elastic limit.

  19. EPR-technical codes - a common basis for the EPR

    International Nuclear Information System (INIS)

    Zaiss, W.; Appell, B.

    1997-01-01

    The design and construction of Nuclear Power Plants implies a full set of codes and standards to define the construction rules of components and equipment. Rules are existing and are currently implemented, respectively in France and Germany (mainly RCCs and KTA safety standards). In the frame of the EPR-project, the common objective requires an essential industrial work programme between engineers from both countries to elaborate a common set of codes and regulations. These new industrial rules are called the ETCs (EPR Technical Codes). In the hierarchy the ETCs are - in case of France - on the common level of basic safety rules (RFS), design and construction rules (RCC) and - in Germany - belonging to RSK guidelines and KTA safety standards. A set of six ETCs will be elaborated to cover: safety and process, mechanical components, electrical equipment, instrumentation and control, civil works, fire protection. (orig.)

  20. Radioactive Waste Management Basis

    International Nuclear Information System (INIS)

    Perkins, B.K.

    2009-01-01

    The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  1. Statement of Basis/Proposed Plan for the F-Area Burning/Rubble Pits (231-F, 231-1F, and 231-2F)

    International Nuclear Information System (INIS)

    Palmer, E.

    1996-08-01

    The purpose of this source unit Statement of Basis/Proposed Plan is to describe the preferred alternative for addressing the F-Area Burning/Rubble Pits (231-F and 231-1F) and Rubble Pit (231-2F) (FBRP) source unit located at SRS, in southwestern Aiken County, South Carolina and to provide an opportunity for public input into the remedial action selection process

  2. RBMK nuclear reactors: Proposals for instrumentation and control improvements to enhanced safety and availability. IEC technical report of type 3. Working material

    International Nuclear Information System (INIS)

    1995-01-01

    The present material presents a CD+V draft report ''RBMK nuclear reactors: Proposals for instrumentation and control improvements to enhance safety and availability'' prepared by the Joint IEC/IAEA team during 1993-1995. Experience has demonstrated the need to improve the safety instrumentation of the RBMK type reactors using well proven modern technology. The working group identified the upgrades and changes of the highest priority based on the evaluation of the RBMK systems and the events where the instrumentation was found to be inadequate for safe operation. The subjects discussed in this document were not selected on a systematic basis but were selected by the IEC and IAEA experts as considered to be appropriate to the activities of the IEC and for which technical experience was available. The items identified therefore do not reflect any ranking of the safety issues or any priority or impact on safety of any of the measures were they to be implemented. Many important safety issued and areas where physical measures are required to improve safety have been omitted and indeed not even acknowledged in this document. The recommendations presented in the document differ from those normally produced by the IEC in the form of standards as they are of a transitory nature and some have already been overtaken by the continuing process of improvements to plant safety. Figs and tabs

  3. Standard technical specifications combustion engineering plants

    International Nuclear Information System (INIS)

    1992-09-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS) for Combustion Engineering Plants. The improved STS wee developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Sections 3.4--3.9 of the improved STS

  4. Authorization basis requirements comparison report

    Energy Technology Data Exchange (ETDEWEB)

    Brantley, W.M.

    1997-08-18

    The TWRS Authorization Basis (AB) consists of a set of documents identified by TWRS management with the concurrence of DOE-RL. Upon implementation of the TWRS Basis for Interim Operation (BIO) and Technical Safety Requirements (TSRs), the AB list will be revised to include the BIO and TSRs. Some documents that currently form part of the AB will be removed from the list. This SD identifies each - requirement from those documents, and recommends a disposition for each to ensure that necessary requirements are retained when the AB is revised to incorporate the BIO and TSRs. This SD also identifies documents that will remain part of the AB after the BIO and TSRs are implemented. This document does not change the AB, but provides guidance for the preparation of change documentation.

  5. Authorization basis requirements comparison report

    International Nuclear Information System (INIS)

    Brantley, W.M.

    1997-01-01

    The TWRS Authorization Basis (AB) consists of a set of documents identified by TWRS management with the concurrence of DOE-RL. Upon implementation of the TWRS Basis for Interim Operation (BIO) and Technical Safety Requirements (TSRs), the AB list will be revised to include the BIO and TSRs. Some documents that currently form part of the AB will be removed from the list. This SD identifies each - requirement from those documents, and recommends a disposition for each to ensure that necessary requirements are retained when the AB is revised to incorporate the BIO and TSRs. This SD also identifies documents that will remain part of the AB after the BIO and TSRs are implemented. This document does not change the AB, but provides guidance for the preparation of change documentation

  6. Mathematical model for estimating of technical and technological indicators of railway stations operation

    Directory of Open Access Journals (Sweden)

    D.M. Kozachenko

    2013-06-01

    Full Text Available Purpose. The article aims to create a mathematical model of the railway station functioning for the solving of problems of station technology development on the plan-schedule basis. Methodology. The methods of graph theory and object-oriented analysis are used as research methods. The model of the station activity plan-schedule includes a model of technical equipment of the station (plan-schedule net and a model of the station functioning , which are formalized on the basis of parametric graphs. Findings. The presented model is implemented as an application to the graphics package AutoCAD. The software is developed in Visual LISP and Visual Basic. Taking into account that the construction of the plan-schedule is mostly a traditional process of adding, deleting, and modifying of icons, the developed interface is intuitively understandable for a technologist and practically does not require additional training. Originality. A mathematical model was created on the basis of the theory of graphs and object-oriented analysis in order to evaluate the technical and process of railway stations indicators; it is focused on solving problems of technology development of their work. Practical value. The proposed mathematical model is implemented as an application to the graphics package of AutoCAD. The presence of a mathematical model allows carrying out an automatic analysis of the plan-schedule and, thereby, reducing the period of its creation more than twice.

  7. Doubly stochastic radial basis function methods

    Science.gov (United States)

    Yang, Fenglian; Yan, Liang; Ling, Leevan

    2018-06-01

    We propose a doubly stochastic radial basis function (DSRBF) method for function recoveries. Instead of a constant, we treat the RBF shape parameters as stochastic variables whose distribution were determined by a stochastic leave-one-out cross validation (LOOCV) estimation. A careful operation count is provided in order to determine the ranges of all the parameters in our methods. The overhead cost for setting up the proposed DSRBF method is O (n2) for function recovery problems with n basis. Numerical experiments confirm that the proposed method not only outperforms constant shape parameter formulation (in terms of accuracy with comparable computational cost) but also the optimal LOOCV formulation (in terms of both accuracy and computational cost).

  8. A technical basis for meeting waste form stability requirements of 10 CFR 61

    International Nuclear Information System (INIS)

    Chang, W.Y.; Skoski, L.; Eng, R.; Tuite, P.T.

    1988-01-01

    To assure that solidified low level waste forms meet the stability requirements of 10 CFR 61 regulations, the US Nuclear Regulatory Commission (NRC) has published Branch Technical Positions (BTPs) and draft Regulatory Guide on waste form stability. These guidance documents describe the test procedures and acceptance criteria for six stability parameters: leachability, compressive strength, immersion effect, radiation effect, thermal stability and biodegradability. The most recent set of recommended tests and acceptance criteria are presented in the November 1986 Preliminary Draft Regulatory Guide Low Level Waste Form Stability. The objective of this study was to: (1) investigate the regulatory and technical bases for the required stability tests, (2) evaluate the relevance of these tests and acceptance criteria based on actual test results, and (3) recommended alternatives to the testing and acceptance criteria. The latter two objectives are discussed in this paper

  9. Composite Socio-Technical Systems: A Method for Social Energy Systems

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Yingchen [National Renewable Energy Laboratory (NREL), Golden, CO (United States); He, Fulin [Huazhong University of Science & Technology; Hao, Jun [University of Denver; Dai, Xiaoxiao [University of Denver; Zhang, Jun Jason [University of Denver; Wei, Jiaolong [Huazhong University of Science & Technology

    2017-12-01

    In order to model and study the interactions between social on technical systems, a systemic method, namely the composite socio-technical systems (CSTS), is proposed to incorporate social systems, technical systems and the interaction mechanism between them. A case study on University of Denver (DU) campus grid is presented in paper to demonstrate the application of the proposed method. In the case study, the social system, technical system, and the interaction mechanism are defined and modelled within the framework of CSTS. Distributed and centralized control and management schemes are investigated, respectively, and numerical results verifies the feasibility and performance of the proposed composite system method.

  10. Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

    International Nuclear Information System (INIS)

    Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L.

    1978-10-01

    The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems

  11. Improvements to Technical Specifications surveillance requirements

    International Nuclear Information System (INIS)

    Lobel, R.; Tjader, T.R.

    1992-12-01

    In August 1983 an NRC task group was formed to investigate problems with surveillance testing required by Technical Specifications, and to recommend approaches to effect improvements. NUREG-1024 (''Technical Specifications-Enhancing Safety Impact'') resulted, and it contained recommendations to review the basis for test frequencies; to ensure that the tests promote safety and do not degrade equipment; and to review surveillance tests so that they do not unnecessarily burden personnel. The Technical Specifications Improvement Program (TSIP) was established in December 1984 to provide the framework for rewriting and improving the Technical Specifications. As an element of the TSIP, all Technical Specifications surveillance requirements were comprehensively examined as recommended in NUREG-1024. The results of that effort are presented in this report. The study found that while some testing at power is essential to verify equipment and system operability, safety can be improved, equipment degradation decreased, and unnecessary personnel burden relaxed by reducing the amount of testing at power

  12. Radioactive Waste Management BasisApril 2006

    Energy Technology Data Exchange (ETDEWEB)

    Perkins, B K

    2011-08-31

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  13. Development of technical information basis of aging management for nuclear power plants

    International Nuclear Information System (INIS)

    Kanno, M.

    2007-01-01

    In order to implement effective safety regulations on aging management for reactor facilities etc., the information on important technology issues, the latest technical knowledge including evaluation technology, test and research outcomes, related codes and standards, regulation information, operation experiences such as accidents and trouble, etc. with respect to aging-induced deterioration in and outside Japan and in other industries, were collected, organized and evaluated. (author)

  14. Colonialism and Secondary Technical Education in Hong Kong: 1945-1997

    Science.gov (United States)

    Lau, Wai Wah; Kan, Flora

    2011-01-01

    This study examines the influence of the colonial experience (1945-1997) on the planning of secondary technical education in Hong Kong. Specifically, the origins of secondary technical institutions and their positioning in secondary education are examined. Primary source materials are used as the basis of investigation and analysis, supplemented…

  15. Technical and Technological Support of Agricultural Enterprises on the Basis of Association Interaction: a Methodical Approach

    Directory of Open Access Journals (Sweden)

    Pyvovar Petro V.

    2017-12-01

    Full Text Available The aim of the research is the development of a methodical approach to justifying directions of association interaction of agricultural enterprises for the most effective technical and technological support of their economic activities. It is substantiated that the decision-making regarding the directions of group interaction in the field of forming and using the machine and tractor fleet of agricultural enterprises should be based on results of a strategic analysis of the current level of and trends in the changes in indicators of their technical support. This includes several stages: 1 determining a scenario for the development of the technical base of the economic entity (matrix methods; 2 multifactor grouping taking into account the available equipment and resource potential; 3 identification of potential sources of financing and ways of attracting necessary funds, priority partners and types of equipment and technologies; 4 estimation of a current condition of the enterprise on financial, technical, economic and market criteria; 5 substantiation of directions of group interaction of the enterprise.

  16. Technical and economic viability of electric power plants on the basis of renewable energy resources regarding hierarchical structure

    Directory of Open Access Journals (Sweden)

    Balzannikov Mikhail

    2017-01-01

    Full Text Available The article deals with power stations working on the basis of non-renewable energy resources and finite resources which will inevitably come to depletion in the future. These installations produce considerable negative impact on the environment, including air pollution. It is noted that considerable amounts of emissions of harmful substances accounts for the share of small thermal installations which aren’t always considered in calculations of pollution. The author specifies that emission reduction of harmful substances should be achieved due to wider use of environmentally friendly renewable energy resources. It is recommended to use hierarchical structure with the priority of ecological and social conditions of the region for technical and economic viability of consumers’ power supply systems and installations, based on renewable energy resources use. At the same time the author suggests considering federal, regional and object levels of viability. It is recommended to consider the main stages of lifecycle of an object for object level: designing, construction, operation, reconstruction of an object and its preservation. The author shows the example of calculation of power plant efficiency, based on renewable energy resources during its reconstruction, followed by power generation increase.

  17. 78 FR 65695 - 30-Day Notice of Proposed Information Collection: Technical Processing Requirements for...

    Science.gov (United States)

    2013-11-01

    ... Information Collection: Technical Processing Requirements for Multifamily Project Mortgage Insurance AGENCY: Office of the Chief Information Officer, HUD. ACTION: Correction, notice. SUMMARY: On October 25, 2013 at... Collection Title of Information Collection: Technical Processing Requirements for Multifamily Project...

  18. Scientific and technical basis of safety increase measures at NPPs with WWER

    International Nuclear Information System (INIS)

    Skalozubov, V.I.; Klyuchnikov, A.A.; Komarov, Yu.A.; Shavlakov, A.V.

    2010-01-01

    This monograph presents the original development of the authors on scientific and technical substantiation of foreground modern measures on safety increase at nuclear power plants with water-water reactors: development and implementation of operative diagnostic system for thermo acoustical instability of reactor core, substantituation of performance capacity and reliability of fast-acting reducing units systems and regulation systems of reactor emergency cooling at control of dominant for safety accidents.

  19. Preventive maintenance basis: Volume 31 -- Relays -- timing. Final report

    International Nuclear Information System (INIS)

    Worledge, D.; Hinchcliffe, G.

    1998-07-01

    US nuclear power plants are implementing preventive maintenance (PM) tasks with little documented basis beyond fundamental vendor information to support the tasks or their intervals. The Preventive Maintenance Basis project provides utilities with the technical basis for PM tasks and task intervals associated with 40 specific components such as valves, electric motors, pumps, and HVAC equipment. This document provides a program of preventive maintenance tasks suitable for application to timing relays. The PM tasks that are recommended provide a cost-effective way to intercept the causes and mechanisms that lead to degradation and failure. They can be used in conjunction with material from other sources, to develop a complete PM program or to improve an existing program

  20. Preventive maintenance basis: Volume 30 -- Relays -- control. Final report

    International Nuclear Information System (INIS)

    Worledge, D.; Hinchcliffe, G.

    1998-07-01

    US nuclear power plants are implementing preventive maintenance (PM) tasks with little documented basis beyond fundamental vendor information to support the tasks or their intervals. The Preventive Maintenance Basis project provides utilities with the technical basis for PM tasks and task intervals associated with 40 specific components such as valves, electric motors, pumps, and HVAC equipment. This document provides a program of preventive maintenance tasks suitable for application to control relays. The PM tasks that are recommended provide a cost-effective way to intercept the causes and mechanisms that lead to degradation and failure. They can be used in conjunction with material from other sources, to develop a complete PM program or to improve an existing program

  1. The socio-technical system and nuclear safety

    International Nuclear Information System (INIS)

    Stefanescu, Petre; Mihailescu, Nicolae; Dragusin, Octavian

    1999-01-01

    In the field of nuclear safety there have been defined notions like 'technical factors' and 'human factors'. The technical factors depend on designing and manufacturing of components/equipment, actually depend on the people's work. The study of human factors consists in analyzing and recommending the terms that allow an individual to be a reliable and safety agent. Accordingly, he/she is placed in working conditions corresponding to human abilities, associating the means of three levels: - designing, i.e. the action upon the technical system and upon work organization; - correction, i.e. the action upon the evolution of the technical system and organizing; - formation/training, i.e. action upon operators. The paper presents a characterization of the socio-technical system and on this basis discusses the issue of individual adjustment to the socio-technical system and reciprocally, the issue of the socio-technical system adjustment to the individual. Concepts as: ergonomics, physical medium, man/machine interface and support of the operator, man/machine task sharing, the work organizing are put in relation with the central subject, the nuclear safety

  2. Technical review of the dispersion and dose models used in the MILDOS computer program

    International Nuclear Information System (INIS)

    Horst, T.W.; Soldat, J.K.; Bander, T.J.

    1982-05-01

    The MILDOS computer code is used to estimate impacts of radioactive emissions from uranium milling facilities. This report reviews the technical basis of the models used in the MILDOS computer code. The models were compared with state-of-the-art predictions, taking into account the intended uses of the MILDOS code. Several suggested modifications are presented and the technical basis for those changes are given

  3. The logic of Technical Standardisation

    DEFF Research Database (Denmark)

    Nedergaard, Peter

    In this paper technical standardisation is understood and explained in a model where economic analysis is coupled with an analysis of the political system as proposed in rational choice theory. The aim is to answer both the question why various countries (e.g. the United States versus European...... countries) let either the market or public intervention determine the mode of technical standardisation and the possible implications of these two ways of organizing technical standardisation from an economic and a political point of view. Based upon the analysis of the paper a couple of general policy...... recommendations are made concerning the mode of technical standardisation....

  4. Technical specification optimization program - engineered safety features

    International Nuclear Information System (INIS)

    Andre, G.R.; Jansen, R.L.

    1986-01-01

    The Westinghouse Technical Specification Program (TOP) was designed to evaluate on a quantitative basis revisions to Nuclear Power Plant Technical Specifications. The revisions are directed at simplifying plant operation, and reducing unnecessary transients, shutdowns, and manpower requirements. In conjunction with the Westinghouse Owners Group, Westinghouse initiated a program to develop a methodology to justify Technical Specification revisions; particularly revisions related to testing and maintenance requirements on plant operation for instrumentation systems. The methodology was originally developed and applied to the reactor trip features of the reactor protection system (RPS). The current study further refined the methodology and applied it to the engineered safety features of the RPS

  5. Branch technical position for performance assessment of low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Campbell, A.C.; Abramson, L.; Byrne, R.M.

    1994-01-01

    The U.S. Nuclear Regulatory Commission has developed a Draft Branch Technical Position on Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. The draft technical position addresses important issues in performance assessment modeling and provides a framework and technical basis for conducting and evaluating performance assessments in a disposal facility license application. The technical position also addresses specific technical policy issues and augments existing NRC guidance pertaining to LLW performance assessment

  6. DOE technical standards list: Department of Energy standards index

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    This Department of Energy (DOE) technical standards list (TSL) has been prepared by the Office of Nuclear Safety Policy and Standards (EH-31) on the basis of currently available technical information. Periodic updates of this TSL will be issued as additional information is received on standardization documents being issued, adopted, or canceled by DOE. This document was prepared for use by personnel involved in the selection and use of DOE technical standards and other Government and non-Government standards. This TSL provides listings of current DOE technical standards, non-Government standards that have been adopted by DOE, other standards-related documents in which DOE has a recorded interest, and canceled DOE technical standards. Information on new DOE technical standards projects, technical standards released for coordination, recently published DOE technical standards, and activities of non-Government standards bodies that may be of interest to DOE is published monthly in Standards Actions.

  7. Danglers in Patient Information Leaflets and Technical Manuals

    DEFF Research Database (Denmark)

    Køhler Simonsen, Henrik

    2014-01-01

    in fact been proved. The analysis and the discussion showed that dangling participles are not very frequent in PILs, but much more common in technical manuals. The data showed that there were no “ludicrous” danglers,(see Matthews and Matthews 2008:146), in PILcorp. However, the analysis showed that both......Dangling participles and other types of ambiguous or unclear sentence constructions in directive and informative medical and technical texts, such as patient information leaflets (PILs) and technical manuals, render instructions unclear and potentially dangerous for the layman reader, i......, and readability on the basis of two corpora: a corpus of PILs (PILcorp) and a corpus of technical manuals (TECHcorp). The hypothesis is that patient information leaflets will contain fewer dangling constructions than technical manuals because of the strict regulations on product information texts including PILs...

  8. Basis for NGNP Reactor Design Down-Selection

    Energy Technology Data Exchange (ETDEWEB)

    L.E. Demick

    2010-08-01

    The purpose of this paper is to identify the extent of technology development, design and licensing maturity anticipated to be required to credibly identify differences that could make a technical choice practical between the prismatic and pebble bed reactor designs. This paper does not address a business decision based on the economics, business model and resulting business case since these will vary based on the reactor application. The selection of the type of reactor, the module ratings, the number of modules, the configuration of the balance of plant and other design selections will be made on the basis of optimizing the Business Case for the application. These are not decisions that can be made on a generic basis.

  9. 45 CFR 1230.300 - Professional and technical services.

    Science.gov (United States)

    2010-10-01

    ... technical discipline. For example, drafting or a legal document accompanying a bid or proposal by a lawyer... 45 Public Welfare 4 2010-10-01 2010-10-01 false Professional and technical services. 1230.300....300 Professional and technical services. (a) The prohibition on the use of appropriated funds, in...

  10. 47 CFR 68.608 - Publication of technical criteria.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 3 2010-10-01 2010-10-01 false Publication of technical criteria. 68.608... Attachments § 68.608 Publication of technical criteria. The Administrative Council for Terminal Attachments shall place technical criteria proposed for publication on public notice for 30 days. At the end of the...

  11. Proposal for geological site selection for L/ILW and HLW repositories. Statement of requirements, procedure and results. Technical report 08-03

    International Nuclear Information System (INIS)

    2008-10-01

    Important steps in the process of managing radioactive wastes have already been implemented in Switzerland. These include the handing and packaging of the waste, waste characterisation and documentation of waste inventories and interim storage along with associated transport. In terms of preparing for deep geological disposal, the necessary scientific and technical work is well advanced and the feasibility of constructing geological repositories that provide the required long-term safety has been successfully demonstrated for all waste types arising in Switzerland. Sufficient knowledge is available to allow the next steps in the selection of repository sites to be defined. The legal framework is also in place and organisational measures have been provided that will allow the tasks to be performed in the coming years to be implemented efficiently. The selection of geological siting regions and sites for repositories in Switzerland will be conducted in three stages. Stage 1 ends with the definition of geological siting regions within which the repository projects will be elaborated in more detail in stages 2 and 3. This report documents and justifies the siting proposals prepared by Nagra for the repositories for low- and intermediate-level waste (L/ILW) and high-level waste (HLW). Formulation of these proposals is conducted in five steps: 1) The waste inventory, which includes reserves for future developments, is allocated to the L/ILW and HLW repositories; 2) Based on this waste allocation, the second step involves defining the barrier and safety concepts for the two repositories. With a view to evaluating the geological siting possibilities, quantitative and qualitative guidelines and requirements on the geology are derived on the basis of these concepts. These relate to the time period to be considered, the space requirements for the repository, the properties of the host rock (depth, thickness, lateral extent, hydraulic conductivity), long-term stability

  12. Linear accelerator-breeder (LAB): a preliminary analysis and proposal

    International Nuclear Information System (INIS)

    1976-01-01

    The development and demonstration of a Linear Accelerator-Breeder (LAB) is proposed. This would be a machine which would use a powerful linear accelerator to produce an intense beam of protons or deuterons impinging on a target of a heavy element, to produce spallation neutrons. These neutrons would in turn be absorbed in fertile 238 U or 232 Th to produce fissile 239 Pu or 233 U. Though a Linear Accelerator-Breeder is not visualized as competitive to a fast breeder such as the LMFBR, it would offer definite benefits in improved flexibility of options, and it could probably be developed more rapidly than the LMFBR if fuel cycle problems made this desirable. It is estimated that at a beam power of 300 MW a Linear Accelerator-Breeder could produce about 1100 kg/year of fissile 239 Pu or 233 U, which would be adequate to fuel from 2,650 to 15,000 MW(e) of fission reactor capacity depending on the fuel cycle used. A two-year design study is proposed, and various cost estimates are presented. The concept of the Linear Accelerator-Breeder is not new, having been the basis for a major AEC project (MTA) a number of years ago. It has also been pursued in Canada starting from the proposal for an Intense Neutron Generator (ING) several years ago. The technical basis for a reasonable design has only recently been achieved. The concept offers an opportunity to fill an important gap that may develop between the short-term and long-term energy options for energy security of the nation

  13. Speech/Nonspeech Detection Using Minimal Walsh Basis Functions

    Directory of Open Access Journals (Sweden)

    Pwint Moe

    2007-01-01

    Full Text Available This paper presents a new method to detect speech/nonspeech components of a given noisy signal. Employing the combination of binary Walsh basis functions and an analysis-synthesis scheme, the original noisy speech signal is modified first. From the modified signals, the speech components are distinguished from the nonspeech components by using a simple decision scheme. Minimal number of Walsh basis functions to be applied is determined using singular value decomposition (SVD. The main advantages of the proposed method are low computational complexity, less parameters to be adjusted, and simple implementation. It is observed that the use of Walsh basis functions makes the proposed algorithm efficiently applicable in real-world situations where processing time is crucial. Simulation results indicate that the proposed algorithm achieves high-speech and nonspeech detection rates while maintaining a low error rate for different noisy conditions.

  14. Spent nuclear fuel project technical databook

    Energy Technology Data Exchange (ETDEWEB)

    Reilly, M.A.

    1998-07-22

    The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values.

  15. Spent nuclear fuel project technical databook

    International Nuclear Information System (INIS)

    Reilly, M.A.

    1998-01-01

    The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values

  16. 15 CFR 28.300 - Professional and technical services.

    Science.gov (United States)

    2010-01-01

    ..., drafting or a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly, technical... 15 Commerce and Foreign Trade 1 2010-01-01 2010-01-01 false Professional and technical services... ON LOBBYING Activities by Other Than Own Employees § 28.300 Professional and technical services. (a...

  17. 24 CFR 87.205 - Professional and technical services.

    Science.gov (United States)

    2010-04-01

    ... professional or technical discipline. For example, drafting of a legal document accompanying a bid or proposal... 24 Housing and Urban Development 1 2010-04-01 2010-04-01 false Professional and technical services... and technical services. (a) The prohibition on the use of appropriated funds, in § 87.100 (a), does...

  18. 43 CFR 18.300 - Professional and technical services.

    Science.gov (United States)

    2010-10-01

    ..., drafting or a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly, technical... 43 Public Lands: Interior 1 2010-10-01 2010-10-01 false Professional and technical services. 18... LOBBYING Activities by Other Than Own Employees § 18.300 Professional and technical services. (a) The...

  19. 44 CFR 18.300 - Professional and technical services.

    Science.gov (United States)

    2010-10-01

    ... technical discipline. For example, drafting or a legal document accompanying a bid or proposal by a lawyer... 44 Emergency Management and Assistance 1 2010-10-01 2010-10-01 false Professional and technical... § 18.300 Professional and technical services. (a) The prohibition on the use of appropriated funds, in...

  20. 49 CFR 20.205 - Professional and technical services.

    Science.gov (United States)

    2010-10-01

    ..., drafting of a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly, technical... 49 Transportation 1 2010-10-01 2010-10-01 false Professional and technical services. 20.205... Activities by Own Employees § 20.205 Professional and technical services. (a) The prohibition on the use of...

  1. 22 CFR 519.205 - Professional and technical services.

    Science.gov (United States)

    2010-04-01

    ..., drafting of a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly, technical... 22 Foreign Relations 2 2010-04-01 2010-04-01 true Professional and technical services. 519.205... by Own Employees § 519.205 Professional and technical services. (a) The prohibition on the use of...

  2. 38 CFR 45.205 - Professional and technical services.

    Science.gov (United States)

    2010-07-01

    ... or technical discipline. For example, drafting of a legal document accompanying a bid or proposal by... technical services. 45.205 Section 45.205 Pensions, Bonuses, and Veterans' Relief DEPARTMENT OF VETERANS... technical services. (a) The prohibition on the use of appropriated funds, in § 45.100(a), does not apply in...

  3. 38 CFR 45.300 - Professional and technical services.

    Science.gov (United States)

    2010-07-01

    ... technical discipline. For example, drafting or a legal document accompanying a bid or proposal by a lawyer... technical services. 45.300 Section 45.300 Pensions, Bonuses, and Veterans' Relief DEPARTMENT OF VETERANS... Professional and technical services. (a) The prohibition on the use of appropriated funds, in § 45.100(a), does...

  4. 6 CFR 9.23 - Professional and technical services.

    Science.gov (United States)

    2010-01-01

    ..., drafting of a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly, technical... 6 Domestic Security 1 2010-01-01 2010-01-01 false Professional and technical services. 9.23... LOBBYING Activities by Other than Own Employees § 9.23 Professional and technical services. (a) The...

  5. Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

    1995-10-20

    The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ``stabilized`` form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision.

  6. Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1

    International Nuclear Information System (INIS)

    Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

    1995-01-01

    The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ''stabilized'' form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision

  7. Technical diagnostics of steam turbines

    International Nuclear Information System (INIS)

    Vlckova, B.; Drahy, J.

    1987-01-01

    This paper deals with practical experience in application of technical diagnostics methods to steam turbines, in particular using pedestal and shaft vibration measurements as well as estimation of bearing metal temperature and ultrasound emission signals. An estimation of effectiveness of the diagnostics methods used is given on the basis of experimental investigations made on a 30-MW turbine. (author)

  8. Discussion on enterprise technical standard management work

    International Nuclear Information System (INIS)

    Li Xinyou

    2010-01-01

    The technical standard management is an important part of enterprise information work, also the basis of enterprise standardization work. Only by rational and orderly management, can it exert maximum effectiveness, provide reliable support for the production and business of enterprise. (author)

  9. 10 CFR 601.205 - Professional and technical services.

    Science.gov (United States)

    2010-01-01

    ..., drafting of a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly, technical... 10 Energy 4 2010-01-01 2010-01-01 false Professional and technical services. 601.205 Section 601... Activities by Own Employees § 601.205 Professional and technical services. (a) The prohibition on the use of...

  10. 32 CFR 28.205 - Professional and technical services.

    Science.gov (United States)

    2010-07-01

    ... or technical discipline. For example, drafting of a legal document accompanying a bid or proposal by... 32 National Defense 1 2010-07-01 2010-07-01 false Professional and technical services. 28.205... technical services. (a) The prohibition on the use of appropriated funds, in § 28.100 (a), does not apply in...

  11. 45 CFR 1168.205 - Professional and technical services.

    Science.gov (United States)

    2010-10-01

    ..., drafting of a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly, technical... 45 Public Welfare 3 2010-10-01 2010-10-01 false Professional and technical services. 1168.205... Activities by Own Employees § 1168.205 Professional and technical services. (a) The prohibition on the use of...

  12. 22 CFR 138.205 - Professional and technical services.

    Science.gov (United States)

    2010-04-01

    ..., drafting of a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly, technical... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Professional and technical services. 138.205... Activities by Own Employees § 138.205 Professional and technical services. (a) The prohibition on the use of...

  13. 32 CFR 28.300 - Professional and technical services.

    Science.gov (United States)

    2010-07-01

    ... technical discipline. For example, drafting of a legal document accompanying a bid or proposal by a lawyer... 32 National Defense 1 2010-07-01 2010-07-01 false Professional and technical services. 28.300... Professional and technical services. (a) The prohibition on the use of appropriated funds, in § 28.100 (a...

  14. 34 CFR 82.205 - Professional and technical services.

    Science.gov (United States)

    2010-07-01

    ..., drafting of a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly, technical... 34 Education 1 2010-07-01 2010-07-01 false Professional and technical services. 82.205 Section 82... by Own Employees § 82.205 Professional and technical services. (a) The prohibition on the use of...

  15. 22 CFR 227.205 - Professional and technical services.

    Science.gov (United States)

    2010-04-01

    ..., drafting of a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly, technical... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Professional and technical services. 227.205... Activities by Own Employees § 227.205 Professional and technical services. (a) The prohibition on the use of...

  16. 29 CFR 93.205 - Professional and technical services.

    Science.gov (United States)

    2010-07-01

    ... professional or technical discipline. For example, drafting of a legal document accompanying a bid or proposal... 29 Labor 1 2010-07-01 2010-07-01 true Professional and technical services. 93.205 Section 93.205... Professional and technical services. (a) The prohibition on the use of appropriated funds, in § 93.100 (a...

  17. The technical need for food irradiation as a basis for approval

    International Nuclear Information System (INIS)

    Boegl, K.W.; Dehne, L.I.; Helle, N.; Schreiber, G.A.; Schuettler, C.; Zagon, J.

    1992-01-01

    The contribution deals with the development of legal regulations concerning irradiated food and the discussions during the last 35 years about the technical need, the different points of view about health consequences, and the behaviour and expectations of consumers. The attitudes of the German Research Society, the Federal Health Office, of Federal Parliament and Federal Council, of the Federal Government and of the governments of the states, and of international organizations are discussed in the light of three factors: - is there any need for action, - political determination, and - change of implementation. Legal restrictions and consumer behaviour may influence developments in the field of alternative techniques. To what extent is, exemplified by spices and dried vegetables. (orig.) [de

  18. Proceedings: EPRI Workshop 2 -- Technical basis for EPA HLW disposal criteria

    International Nuclear Information System (INIS)

    Rogers, V.

    1993-03-01

    The Electric Power Research Institute (EPRI) sponsored this workshop to address the scientific and technical issues underlying the regulatory criteria, or standard, for the disposal of spent nuclear fuel, high-level radioactive waste, and transuranic waste, commonly referred to collectively as high-level waste (HLW). These regulatory criteria were originally promulgated by the US Environmental Protection Agency (EPA) in 40 CFR Part 191 in 1985. However, significant portions of the regulation were remanded by the Ninth Circuit Court of Appeals in 1987. This is the second of two workshops. Topics discussed include: gas pathway; individual and groundwater protection; human intrusion; population protection; performance; TRU conversion factors and discussions. Individual projects re processed separately for the databases

  19. Proposal for a Co-operation Agreement between the European Organization for Nuclear Research (CERN) and the Vietnamese Academy of Science and Technology (VAST) concerning Scientific and Technical Co-o

    CERN Document Server

    2006-01-01

    Proposal for a Co-operation Agreement between the European Organization for Nuclear Research (CERN) and the Vietnamese Academy of Science and Technology (VAST) concerning Scientific and Technical Co-o

  20. 75 FR 33761 - Notice of Proposed Change to Section IV of the Virginia State Technical Guide

    Science.gov (United States)

    2010-06-15

    ... revisions made after enactment of the law to NRCS State technical guides used to carry out highly erodible... Section IV of the Virginia State Technical Guide AGENCY: Natural Resources Conservation Service (NRCS), U... NRCS State Technical Guide for review and comment. SUMMARY: It has been determined by the NRCS State...

  1. 75 FR 34974 - Notice of Proposed Change to Section IV of the Virginia State Technical Guide

    Science.gov (United States)

    2010-06-21

    ... revisions made after enactment of the law to NRCS State technical guides used to carry out highly erodible... Section IV of the Virginia State Technical Guide AGENCY: Natural Resources Conservation Service (NRCS), U... NRCS State Technical Guide for review and comment. SUMMARY: It has been determined by the NRCS State...

  2. 75 FR 62759 - Notice of Proposed Change to Section IV of the Virginia State Technical Guide

    Science.gov (United States)

    2010-10-13

    ... revisions made after enactment of the law to NRCS State technical guides used to carry out highly erodible... Section IV of the Virginia State Technical Guide AGENCY: Natural Resources Conservation Service (NRCS), U... NRCS State Technical Guide for review and comment. SUMMARY: It has been determined by the NRCS State...

  3. A convenient basis for the Izergin-Korepin model

    Science.gov (United States)

    Qiao, Yi; Zhang, Xin; Hao, Kun; Cao, Junpeng; Li, Guang-Liang; Yang, Wen-Li; Shi, Kangjie

    2018-05-01

    We propose a convenient orthogonal basis of the Hilbert space for the quantum spin chain associated with the A2(2) algebra (or the Izergin-Korepin model). It is shown that compared with the original basis the monodromy-matrix elements acting on this basis take relatively simple forms, which is quite similar as that for the quantum spin chain associated with An algebra in the so-called F-basis. As an application of our general results, we present the explicit recursive expressions of the Bethe states in this basis for the Izergin-Korepin model.

  4. Technical solutions for low-voltage microgrid concept

    Energy Technology Data Exchange (ETDEWEB)

    Laaksonen, H.

    2011-07-01

    investments in facilities and personnel. The developed technical solutions and findings for the microgrid concept presented in this thesis can be utilized as a basis when the grid codes for future low-voltage microgrids and the plans for real-life pilot installations are carried out. The proposed technical choices as well as operation and planning principles of the developed low-voltage microgrid concept can also be taken into account in the development of low-voltage microgrid compatible protection devices, distributed energy resource units, microgrid management systems and future market structures. In the future, real-life example cases are necessary to verify and test the functionality of the developed technical solutions. (orig.)

  5. A stock market forecasting model combining two-directional two-dimensional principal component analysis and radial basis function neural network.

    Science.gov (United States)

    Guo, Zhiqiang; Wang, Huaiqing; Yang, Jie; Miller, David J

    2015-01-01

    In this paper, we propose and implement a hybrid model combining two-directional two-dimensional principal component analysis ((2D)2PCA) and a Radial Basis Function Neural Network (RBFNN) to forecast stock market behavior. First, 36 stock market technical variables are selected as the input features, and a sliding window is used to obtain the input data of the model. Next, (2D)2PCA is utilized to reduce the dimension of the data and extract its intrinsic features. Finally, an RBFNN accepts the data processed by (2D)2PCA to forecast the next day's stock price or movement. The proposed model is used on the Shanghai stock market index, and the experiments show that the model achieves a good level of fitness. The proposed model is then compared with one that uses the traditional dimension reduction method principal component analysis (PCA) and independent component analysis (ICA). The empirical results show that the proposed model outperforms the PCA-based model, as well as alternative models based on ICA and on the multilayer perceptron.

  6. Using communication norms in socio-technical systems

    NARCIS (Netherlands)

    Weigand, H.; Whitworth, B.; de Moor, A.

    2009-01-01

    Often socio-technical systems are designed simply on the basis of what the user asks, and without considering explicitly whether the required process structure is right and wrong. However, poor communication may cause many problems. Therefore, a design cycle should always include diagnosis, and in

  7. DISPOWER. A socio-economic analysis of technical solutions and practices for the integration of distributed generation

    International Nuclear Information System (INIS)

    Ten Donkelaar, M.; Scheepers, M.J.J.

    2004-07-01

    Socio-economic impacts of technical solutions and approaches that are being developed for the integration of distributed generation (DG) in electricity distribution systems are analyzed. For this analysis an inventory was made of technical options, solutions and approaches on the basis of a questionnaire that has been distributed among DG (technical) experts. The questionnaire was not meant to give an exhaustive overview, but to gain insight in the possible technical solutions, options and approaches and the economic interactions between different actors in the electricity market. The different technical options and solutions have been divided into four main categories. Four technologies, one of each category, have been studied in more detail to analyse their impact on the financial relationships between the actors in the distribution network. The four technologies are: wind power prediction tool (planning tool), grid control unit (power quality device), power operation and power quality management system (ICT device), and power storage device. To assess the impact of the investments in the proposed technologies on all actors involved (and different from the actor investing), an assessment tool has been developed to qualitatively identify the economic impacts of a number of these options. This assessment tool takes into account the financial transactions between the parties on the distribution network. The analysis also discusses the allocation of the economic value of certain benefits through contracts and economic network regulation

  8. Customisation of an instrument to assess anaesthesiologists' non-technical skills.

    Science.gov (United States)

    Jepsen, Rikke M H G; Spanager, Lene; Lyk-Jensen, Helle T; Dieckmann, Peter; Østergaard, Doris

    2015-02-22

    The objectives of the study were to identify Danish anaesthesiologists' non-technical skills and to customise the Scottish-developed Anaesthetists' Non-Technical Skills instrument for Danish anaesthesiologists. Six semi-structured group interviews were conducted with 31 operating room team members: anaes-thesiologists, nurse anaesthetists, surgeons, and scrub nurses. Interviews were transcribed verbatim and analysed using directed content analysis. Anaesthesiologists' non-technical skills were identified, coded, and sorted using the original instrument as a basis. The resulting prototype instrument was discussed with anaesthesiologists from 17 centres to ensure face validity. Interviews lasted 46-67 minutes. Identified examples of anaesthesiologists' good or poor non-technical skills fit the four categories in the original instrument: situation awareness; decision making; team working; and task management. Anaesthesiologists' leadership role in the operating room was emphasised: the original 'Task Management' category was named 'Leadership'. One new element, 'Demonstrating self-awareness' was added under the category 'Situation Awareness'. Compared with the original instrument, half of the behavioural markers were new, which reflected that being aware of and communicating one's own abilities to the team; working systematically; and speaking up to avoid adverse events were important skills. The Anaesthetists' Non-Technical Skills instrument was customised to a Danish setting using the identified non-technical skills for anaesthesiologists and the original instrument as basis. The customised instrument comprises four categories and 16 underpinning elements supported by multiple behavioural markers. Identifying non-technical skills through semi-structured group interviews and analysing them using direct content analysis proved a useful method for customising an assessment instrument to another setting.

  9. Technical issues for WIPP

    International Nuclear Information System (INIS)

    Hunter, T.O.

    1979-01-01

    Emplacement of wastes in the WIPP will include experiments on various waste types which will provide essential data on waste-rock interaction and repository response. These experiments will include evolution of the synergistic effects of both heat production, radiation, and actual waste forms. While these studies will provide essential data on the validity of waste isolation in bedded salt, they will be preceded by a broad-based experimental program which will resolve many of the current technical issues providing not only an assessment of the safety of performing such experiments but also the technical basis for assurance that the appropriate experiments are performed. Data and predictive modeling techniques, which are currently available, can bound the consequences associated with these technical issues. Predictions of the impact on public safety based on these analyses indicate that safe waste disposal in WIPP salt beds is achievable; however, a major use of WIPP will be to conduct realistic experiments with HLW forms to address some of the unresolved details of these waste/salt interactions

  10. Proposal of a Technical Design of the ATLAS Forward Region Shielding

    CERN Document Server

    Leroy, C; Palla, J; Pospísil, S; Puchmajer, P; Sodomka, J; Stekl, I

    2002-01-01

    The aim of this note is to present a technical design of the ATLAS forward region. The concept is based on segmented shielding supported by the results of an experiment performed at CERN - PS and Monte Carlo simulations extending these results to ATLAS situation. This concept is translated into a practical engineering design.

  11. Technical Basis for Evaluating Software-Related Common-Cause Failures

    Energy Technology Data Exchange (ETDEWEB)

    Muhlheim, Michael David [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wood, Richard [Univ. of Tennessee, Knoxville, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-04-01

    The instrumentation and control (I&C) system architecture at a nuclear power plant (NPP) incorporates protections against common-cause failures (CCFs) through the use of diversity and defense-in-depth. Even for well-established analog-based I&C system designs, the potential for CCFs of multiple systems (or redundancies within a system) constitutes a credible threat to defeating the defense-in-depth provisions within the I&C system architectures. The integration of digital technologies into the I&C systems provides many advantages compared to the aging analog systems with respect to reliability, maintenance, operability, and cost effectiveness. However, maintaining the diversity and defense-in-depth for both the hardware and software within the digital system is challenging. In fact, the introduction of digital technologies may actually increase the potential for CCF vulnerabilities because of the introduction of undetected systematic faults. These systematic faults are defined as a “design fault located in a software component” and at a high level, are predominately the result of (1) errors in the requirement specification, (2) inadequate provisions to account for design limits (e.g., environmental stress), or (3) technical faults incorporated in the internal system (or architectural) design or implementation. Other technology-neutral CCF concerns include hardware design errors, equipment qualification deficiencies, installation or maintenance errors, instrument loop scaling and setpoint mistakes.

  12. Preventive maintenance basis: Volume 1 -- Air-operated valves. Final report

    International Nuclear Information System (INIS)

    Worledge, D.; Hinchcliffe, G.

    1997-07-01

    US nuclear plants are implementing preventive maintenance (PM) tasks with little documented basis beyond fundamental vendor information to support the tasks or their intervals. The Preventive Maintenance Basis project provides utilities with the technical basis for PM tasks and task intervals associated with 40 specific components such as valves, electric motors, pumps, and HVAC equipment. This report provides an overview of the PM Basis project and describes use of the PM Basis database. This document provides a program of PM tasks suitable for application to Air Operated Valves (AOV's) in nuclear power plants. The PM tasks that are recommended provide a cost-effective way to intercept the causes and mechanisms that lead to degradation and failure. They can be used, in conjunction with material from other sources, to develop a complete PM program or to improve an existing program. Users of this information will be utility managers, supervisors, craft technicians, and training instructors responsible for developing, optimizing, or fine-tuning PM programs

  13. Technical modifications and management innovations in exporting nuclear reactor projects

    International Nuclear Information System (INIS)

    Mao Xiaoming; Qin Xijiu; Ding Hu; Xue Zhaoqun; Wen Shengjun

    2009-01-01

    As a main channel for the foreign economic cooperation of China nuclear industry, China Zhongyuan Engineering Corporation (CZEC) has been constantly engaged in technical modifications and management innovations in its exporting nuclear reactor projects. In the implementation of heavy water research reactor contract in Algeria, CZEC had established a complete and adequate design standards system in compliance with the international standards, and made significant modifications to the reference reactor in the aspects of reactor power and reactor safety, solved quite some technical issues which-affected the reactor technical performance. The modifications and improvements enabled the technical parameters, safety features, reactor multipurpose application to attain to the advanced level in the world. In the 300 MWe PWR NPPs in Pakistan, safety features had been updated in line with upgrading regulatory requisites. The design philosophy and technology application demonstrated CZEC' s creation and innovation on basis of constant safety enhancement of nuclear power projects. Efforts had also been made by CZEC' s creation and innovation on basis of constant safety enhancement of nuclear power projects. Efforts had also been made by CZEC in promoting China made equipment items and components exportation. (authors)

  14. 41 CFR 105-69.300 - Professional and technical services.

    Science.gov (United States)

    2010-07-01

    ... or technical discipline. For example, drafting or a legal document accompanying a bid or proposal by... technical services. 105-69.300 Section 105-69.300 Public Contracts and Property Management Federal Property... and technical services. (a) The prohibition on the use of appropriated funds, in § 105-69.100 (a...

  15. Crew Transportation Technical Standards and Design Evaluation Criteria

    Science.gov (United States)

    Lueders, Kathryn L.; Thomas, Rayelle E. (Compiler)

    2015-01-01

    Crew Transportation Technical Standards and Design Evaluation Criteria contains descriptions of technical, safety, and crew health medical processes and specifications, and the criteria which will be used to evaluate the acceptability of the Commercial Providers' proposed processes and specifications.

  16. Significance of technical rules for environmental pollution control

    International Nuclear Information System (INIS)

    Grefen, K.

    1989-01-01

    Technical rules for environmental pollution control are very important in times of intensified technical progress and especially in view of the alterations of the legislative basis of the European Market in 1992. In the fields of jurisprudence, science and technology they serve as a decision-making aid for authorities, specialists in plant development and operation and the preparatory stages of international legislation. The topic is explained by the development of guidelines with the VDI-Commission on Air Pollution Prevention. (orig.) [de

  17. SENTINEL trademark technical basis report for Limerick. Final report

    International Nuclear Information System (INIS)

    Burns, E.T.; Lee, L.K.; Mitman, J.T.; Vanover, D.E.; Wilson, D.K.

    1997-12-01

    PECO Energy in cooperation with the Electric Power Research Institute (EPRI) installed the SENTINEL trademark software at its Limerick Generating Station. This software incorporates models of the safety and support systems which are used to display the defense in depth present in the plant and a quantitative assessment of the plant risks during proposed on-line maintenance. During the past year, PECO Energy personnel have used this display to evaluate the safety of proposed on-line maintenance schedules. The report describes the motivation for and the development of the SENTINEL software. It describes the generation of Safety Function Assessment Trees and Plant Transient Assessment Trees and their use in evaluating the level of defense-in-depth of key plant safety functions and the susceptibility of the plant to critical transient events. Their results are displayed by color indicators ranging from green, through yellow and orange to red to show increasingly hazardous conditions. The report describes the use of the Limerick Probabilistic Safety Assessment within the SENTINEL code to calculate an instantaneous core damage frequency and the criteria by which this frequency is translated to a color indicator. Finally, the report describes the Performance Criteria Assessment which tracks and trends system/train unavailability to document conformance to the requirements of the Maintenance Rule

  18. "You Will": Technology, Magic, and the Cultural Contexts of Technical Communication.

    Science.gov (United States)

    Kitalong, Karla Saari

    2000-01-01

    Provides some background on the use of magical language in technical contexts, gives examples of magical discourse in technology advertisements and newsmagazine articles, and proposes a technical communication pedagogy of media analysis. Notes that the proposed pedagogy involves students conducting diagnostic critiques of media texts and affords…

  19. The technical bases for government emergency plans

    International Nuclear Information System (INIS)

    Champion, D.; Herviou, K.

    2006-01-01

    Despite technical and organisational existing arrangements to prevent human and equipment failures, the occurrence of a severe accident inducing an important release of radioactive or toxic products could not be totally excluded. Public authorities are responsible for the development of emergency plans which main objective is the protection of the population in case of accident. The efficiency of emergency plans assumes they have been established before the occurrence of any accident, taking into account specificities of the installation and its environment. On the basis of the list of possible events likely to induce releases into the environment, some 'envelope' scenarios are selected and their consequences are assessed- The comparison of the consequences to reference levels for which protective actions are recommended gives the area where actions may be required. This approach is applied for the different nuclear facilities in France. Examples are given in the article on the definition of emergency plans technical basis for nuclear power plants, other nuclear facilities and transportation of radioactive materials. (authors)

  20. 76 FR 41293 - Solicitation of Proposals for Technical Assistance Funding From the Native American Business...

    Science.gov (United States)

    2011-07-13

    ... for NABDI Technical Assistance Funding D. Submission of Application in Digital Format E. Application.... The IEED has spent considerable time and expense in collecting digital land grids, geographic...: Marketing studies. 9. What the NABDI Technical Assistance Funding Cannot Fund As stated above, these funds...

  1. A proposed Regulatory Guide basis for spent fuel decay heat

    International Nuclear Information System (INIS)

    Hermann, O.W.; Parks, C.V.; Renier, J.P.

    1991-01-01

    A proposed revision to Regulatory Guide 3.54, ''Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation'' has been developed for the US Nuclear Regulatory Commission. The proposed revision includes a data base of decay heat rates calculated as a function of burnup, specific power, cooling time, initial fuel 235 U enrichment and assembly type (i.e., PWR or BWR). Validation of the calculational method was done by comparison with existing measured decay heat rates. Procedures for proper use of the data base, adjustment formulae accounting for effects due to differences in operating history and initial enrichment, and a defensible safety factor were derived. 15 refs., 6 tabs

  2. Radioactive sealed sources: Reasonable accountability, exemption, and licensing activity thresholds -- A technical basis

    International Nuclear Information System (INIS)

    Lee, D.W.; Shingleton, K.L.

    1996-01-01

    Perhaps owing to their small size and portability, some radiation accidents/incidents have involved radioactive sealed sources (RSSs). As a result, programs for the control and accountability of RSSs have come to be recommended and emplaced that essentially require RSSs to be controlled in a manner different from bulk, unsealed radioactive material. Crucially determining the total number of RSSs for which manpower-intensive radiation protection surveillance is provided is the individual RSS activity above which such surveillance is required and below which such effort is not considered cost effective. Individual RSS activity thresholds are typically determined through scenarios which impart a chosen internal or external limiting dose to Reference Man under specified exposure conditions. The resultant RSS threshold activity levels have meaning commensurate with the assumed scenario exposure parameters, i.e., if they are realistic and technically based. A review of how the Department of Energy (DOE), the International Atomic Energy Agency (IAEA), and the Nuclear Regulatory Commission (NRC) have determined their respective accountability, exemption, and licensing threshold activity values is provided. Finally, a fully explained method using references readily available to practicing health physicists is developed using realistic, technically-based calculation parameters by which RSS threshold activities may be locally generated

  3. Demand of authorization to create the 'Flamanville 3' Basis Nuclear Installation. Synthesis report of the technical examination

    International Nuclear Information System (INIS)

    2007-02-01

    The present report has for objective to present to the College of Asn a synthesis of the technical instruction piloted by the services of Asn and realized by their technical supports (I.R.S.N., G.P.R., S.P.N.) during the period 2001-2006. After a reminder of the conditions of the examination of the safety options of the project EPR made between 1993 and 2000, this report explains the progress and the modalities of the instruction realized from 2001 till 2006. It draws up then, besides a notice of the Asn services at request of creation authorization, a synthesis of the technical examination realized according to axes presented on the fig 1. Finally, it presents the main lines of the examination that it would stay to realize if the creation authorization was delivered. (N.C.)

  4. Technical bid evaluation

    International Nuclear Information System (INIS)

    Bruchhausen, E. v.

    1975-01-01

    It is shown which kind of problems arise for the owners of the project and what is the recommendable method of approach. A detailed description of the necessary working team, information in delegation of work and tasks of procedure, criteria of valuation and classification method. Examples of schemes are shown which are the basis of the technical bid evaluation: tables 'data of system/component' and 'scope of supply'. The procedure of normalization of the bids and of specifying the owners supplies are explained. The content of the final report is described. (HP) [de

  5. 78 FR 36012 - 30-Day Notice of Proposed Information Collection: Export Declaration of Defense Technical Data or...

    Science.gov (United States)

    2013-06-14

    ... Collection: Export Declaration of Defense Technical Data or Services. OMB Control Number: 1405-0157. Type of... Declaration of Defense Technical Data or Services ACTION: Notice of request for public comment and submission... and brokering of defense articles, defense services and related technical data are licensed by the...

  6. Complementarity of technical skills with art and culture: theoretical reflections, the Talent Show Project experiment at IFRJ – campus Realengo and a proposal for its expansion

    Directory of Open Access Journals (Sweden)

    Maria Célia Dantas Pollig

    2016-12-01

    Full Text Available This paper presents the theoretical basis I have used to better understand the dimension of the task I intend to accomplish. As Educational Advisor at the Federal Institute of Education, Science and Technology of Rio de Janeiro (IFRJ, campus Realengo, my plan is to develop and expand the so called Talent Show Project, by complementing technical training, and providing opportunities for artistic and cultural expression. The study also presents several reflections for achieving the expansion of the scope of the Project intervention, which can become an institutional program developed at IFRJ.

  7. Preventive maintenance basis: Volume 19 -- HVAC -- chillers and compressors. Final report

    International Nuclear Information System (INIS)

    Worledge, D.; Hinchcliffe, G.

    1997-12-01

    US nuclear power plants are implementing preventive maintenance (PM) tasks with little documented basis beyond fundamental vendor information to support the tasks or their intervals. The Preventive Maintenance Basis project provides utilities with the technical basis for PM tasks and task intervals associated with 40 specific components such as valves, electric motors, pumps, and HVAC equipment. This document provides a program of preventive maintenance tasks suitable for application to HVAC -- Chillers and Compressors. The PM tasks that are recommended provide a cost-effective way to intercept the causes and mechanisms that lead to degradation and failure. They can be used in conjunction with material from other sources, to develop a complete PM program or to improve an existing program

  8. Concept of the Cooling System of the ITS for ALICE: Technical Proposals, Theoretical Estimates, Experimental Results

    CERN Document Server

    Godisov, O N; Yudkin, M I; Gerasimov, S F; Feofilov, G A

    1994-01-01

    Contradictory demands raised by the application of different types of sensitive detectors in 5 layers of the Inner Tracking System (ITS) for ALICE stipulate the simultaneous use of different schemes of heat drain: gaseous cooling of the 1st layer (uniform heat production over the sensitive surface) and evaporative cooling for the 2nd-5th layers (localised heat production). The last system is also a must for the thermostabilization of Si-drift detectors within 0.1 degree C. Theoretical estimates of gaseous, evaporative and liquid cooling systems are done for all ITS layers. The results of the experiments done for evaporative and liquid heat drain systems are presented and discussed. The major technical problems of the evaporative systems' design are being considered: i) control of liquid supply; ii) vapour pressure control. Two concepts of the evaporative systems are proposed: 1) One channel system for joint transfer of two phases (liquid + gas); 2) Two channels system with separate transfer of phases. Both sy...

  9. Sustainable network of independent technical expertise for radioactive waste disposal

    International Nuclear Information System (INIS)

    Serres, Christophe; Rocher, Muriel; Lemy, Frank; Havlova, Vaclava; Mrskova, Adela; Heriard Dubreuil, Gilles

    2014-01-01

    been developed. For each of these issues, the needs of national safety authorities and of TSO for dialogue and/or guidance development and harmonisation were identified. A set of R and D activities was structured into main key safety issues related to the safety functions and components of the deep geological disposal. This will constitute the basis for the development and future implementation of a scientific research agenda (SRA) proper to expertise bodies and technical safety organisations. In parallel, an assessment of available technical means and scientific skills amongst SITEX partners is under consideration in order to identify areas for possible co-operation, exchange of staff and needs for improvement. This will contribute to assess how in practice this SRA could be implemented amongst organisation in close co-operation. Another objective of the elaboration of such SRA is to engage in scientific dialogue with IGD-TP, keeping in mind the context of the new EC H2020 programme and the identification of possible research projects of common interest for IGD-TP and SITEX. A tentative framework for deriving a harmonised safety review method is proposed mainly based on development of existing material produced by the former European Pilot Study and the IAEA GEOSAF project. As an integrated part of the technical and scientific review process, SITEX engaged with the identification of practical ways to interact with civil society in the expertise function on a durable process. For this purpose, a dedicated meeting was organised with actors of the civil society in Senec (Slovakia) in September 2013. Finally, a framework document describing the characterisation of the national expertise function and elaborating a reflection on what could be the missions and the role of the future European SITEX network will be issued on the basis on the above elements with the objective to establish the future terms of reference of the network. (authors)

  10. Technical evaluation report of the Fort St. Vrain final draft upgraded technical specifications

    International Nuclear Information System (INIS)

    Kimura, C.Y.

    1989-01-01

    This report is a technical evaluation of the final draft of the Fort St. Vrain (FSV) Upgraded Technical Specifications (UT/S) as issued by Public Service of Colorado (PSC) on May 27, 1988 with subsequent supplemental updates issued on June 15, 1988 and August 5, 1988. It has been compared for consistency, and safety conservatism with the Fort St. Vrain (FSV) Updated Final Safety Analysis Report (FSAR), the FSV Safety Evaluation Report (SER), the Facility Operating License, DPR-34, and all amendments to the Facility Operating License issued as of June 1, 1988, and Appendix A to the Operating License DPR-34, Technical Specifications. Because of the age of the plant, no supplements to the Fort St. Vrain SER have been issued since the original SER was not issued as a WASH or a NUREG report. This made it necessary to review all amendments to the Facility Operating License since they would contain the safety evaluations done to support changes to the Facility Operating License. The upgraded Fort St. Vrain Technical Specifications were also broadly compared with the latest Westinghouse Standard Technical Specifications (WSTS) to assure that what was proposed for Fort St. Vrain was consistent with the latest NRC staff practices for standard technical specifications

  11. MATHEMATICAL MODELS OF PROCESSES AND SYSTEMS OF TECHNICAL OPERATION FOR ONBOARD COMPLEXES AND FUNCTIONAL SYSTEMS OF AVIONICS

    Directory of Open Access Journals (Sweden)

    Sergey Viktorovich Kuznetsov

    2017-01-01

    Full Text Available Modern aircraft are equipped with complicated systems and complexes of avionics. Aircraft and its avionics tech- nical operation process is observed as a process with changing of operation states. Mathematical models of avionics pro- cesses and systems of technical operation are represented as Markov chains, Markov and semi-Markov processes. The pur- pose is to develop the graph-models of avionics technical operation processes, describing their work in flight, as well as during maintenance on the ground in the various systems of technical operation. The graph-models of processes and sys- tems of on-board complexes and functional avionics systems in flight are proposed. They are based on the state tables. The models are specified for the various technical operation systems: the system with control of the reliability level, the system with parameters control and the system with resource control. The events, which cause the avionics complexes and func- tional systems change their technical state, are failures and faults of built-in test equipment. Avionics system of technical operation with reliability level control is applicable for objects with constant or slowly varying in time failure rate. Avion- ics system of technical operation with resource control is mainly used for objects with increasing over time failure rate. Avionics system of technical operation with parameters control is used for objects with increasing over time failure rate and with generalized parameters, which can provide forecasting and assign the borders of before-fail technical states. The pro- posed formal graphical approach avionics complexes and systems models designing is the basis for models and complex systems and facilities construction, both for a single aircraft and for an airline aircraft fleet, or even for the entire aircraft fleet of some specific type. The ultimate graph-models for avionics in various systems of technical operation permit the beginning of

  12. Novel Polynomial Basis with Fast Fourier Transform and Its Application to Reed-Solomon Erasure Codes

    KAUST Repository

    Lin, Sian-Jheng

    2016-09-13

    In this paper, we present a fast Fourier transform (FFT) algorithm over extension binary fields, where the polynomial is represented in a non-standard basis. The proposed Fourier-like transform requires O(h lg(h)) field operations, where h is the number of evaluation points. Based on the proposed Fourier-like algorithm, we then develop the encoding/ decoding algorithms for (n = 2m; k) Reed-Solomon erasure codes. The proposed encoding/erasure decoding algorithm requires O(n lg(n)), in both additive and multiplicative complexities. As the complexity leading factor is small, the proposed algorithms are advantageous in practical applications. Finally, the approaches to convert the basis between the monomial basis and the new basis are proposed.

  13. Why there is a need to revise the design basis threat concept

    International Nuclear Information System (INIS)

    Kondratov, S.; Steinhaeusler, F.

    2005-01-01

    Full text: The coordinated terrorist attacks in the United States on September 11, 2001, necessitated the review of the proven concept of the Design Basis Threat (DBT) for nuclear installations. It is safe to assume that revised and upgraded DBT will result in costly technical solutions. Since infrastructure deficits and financial limitations in many countries have already limited the practical application of the DBT in many instances, the revised threat assessment is likely to worsen the current dissatisfactory situation further. Therefore, a new realism in the use of the DBT concept is proposed, based on a three-level approach. This will enable countries to tailor the design of their physical protection systems in accordance with their means by implementing either a minimum required security level protecting only against the most probable threat, or aiming for an intermediate protection level reflecting the newly introduced AHARA - as high as reasonably achievable - principle, or providing the optimum protection level based on an externally reviewed, fully comprehensive DBT. (author)

  14. Why there is a need to revise the Design Basis Threat concept

    International Nuclear Information System (INIS)

    Kondratov, S.; Steinhausler, F.

    2006-01-01

    The terrorist attacks in the USA on 11 September 2001 necessitated a review of the proven concept of the Design Basis Threat (DBT) for nuclear installations. It can be assumed that revised and upgraded DBT will result in costly technical solutions. Since infrastructure deficits and financial limitations in many countries have already limited the practical application of the DBT, the revised threat assessment is likely to worsen the current unsatisfactory situation. Therefore, a new realism in the use of the DBT concept is proposed based on a three-level approach. This will enable countries to tailor the design of their physical protection systems in accordance with their means by implementing either a minimum required security level protecting only against the most probable threat, or an intermediate protection level reflecting the newly introduced AHARA (As High As Reasonably Achievable) principle, or the optimum protection level based on an externally reviewed, fully comprehensive DBT. (author)

  15. Radiological Effluent Technical Specifications (RETS) implementation, Kewaunee Nuclear Power Plant

    International Nuclear Information System (INIS)

    Serrano, W.; Akers, D.W.

    1985-06-01

    A review of the Radiological Effluent Technical Specifications (RETS) for the Kewaunee Nuclear Power Plant was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7'' of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual and the Radiological Environmental Monitoring Manual were reviewed and generally found to be in compliance with the NRC review guidelines

  16. Development of non-destructive testing and technical diagnostics is a basis of safety

    International Nuclear Information System (INIS)

    Klyuev, V.V.

    1996-01-01

    It is evident that in the 21st century the diagnostics and inspection of quality will occupy a more significant area in solving safety problems. The corresponding inspection systems will become an inseparable part of the majority of installations in power engineering, engineering, metallurgy and other branches. On the other hand, the methods and means of nondestructive inspection and technical diagnostics are being converted together with modernization of the technological base, micro miniaturization, and will become more intellectualized and complex

  17. Preventive maintenance basis: Volume 21 -- HVAC, air handling equipment. Final report

    International Nuclear Information System (INIS)

    Worledge, D.; Hinchcliffe, G.

    1997-12-01

    US nuclear plants are implementing preventive maintenance (PM) tasks with little documented basis beyond fundamental vendor information to support the tasks or their intervals. The Preventive Maintenance Basis project provides utilities with the technical basis for PM tasks and task intervals associated with 40 specific components such as valves, electric motors, pumps, and HVAC equipment. This report provides an overview of the PM Basis project and describes use of the PM Basis database. Volume 21 of the report provides a program of PM tasks suitable for application to HVAC-Air Handling Equipment. The PM tasks that are recommended provide a cost-effective way to intercept the causes and mechanisms that lead to degradation and failure. They can be used, in conjunction with material from other sources, to develop a complete PM program or to improve an existing program. Users of this information will be utility managers, supervisors, craft technicians, and training instructors responsible for developing, optimizing, or fine-tuning PM programs

  18. Preventive maintenance basis: Volume 15 -- Rotary screw air compressors. Final report

    International Nuclear Information System (INIS)

    Worledge, D.; Hinchcliffe, G.

    1997-07-01

    US nuclear plants are implementing preventive maintenance (PM) tasks with little documented basis beyond fundamental vendor information to support the tasks or their intervals. The Preventive Maintenance Basis project provides utilities with the technical basis for PM tasks and task intervals associated with 40 specific components such as valves, electric motors, pumps, and HVAC equipment. This report provides an overview of the PM Basis project and describes use of the PM Basis database. Volume 15 of the report provides a program of PM tasks suitable for application to rotary screw air compressors in nuclear power plants. The PM tasks that are recommended provide a cost-effective way to intercept the causes and mechanisms that lead to degradation and failure. They can be used, in conjunction with material from other sources, to develop a complete PM program or to improve an existing program. Users of this information will be utility managers, supervisors, craft technicians, and training instructors responsible for developing, optimizing, or fine-tuning PM programs

  19. Proposing buffer zones and simple technical solutions for safeguarding river water quality and public health

    Science.gov (United States)

    Podimata, M. V.; Bekri, E. S.; Yannopoulos, P. C.

    2012-04-01

    Alfeios River Basin (ARB) constitutes one of the major hydrologic basins (≈3650km2) of Peloponnisos peninsula in Southern Greece. It is drained by Alfeios River and its tributaries, such as Lousios, Ladhon, Erymanthos, Kladheos, Selinous etc. The present manuscript takes a closer look at the importance of tributary basins and focuses on Erymanthos sub-basin that covers about 360 km2. Erymanthos River springs from Erymanthos Mountain that reaches altitudes of 2200 m and discharges 10 m3/sec, approximately, during the winter period, presenting a sound decrease from half to about an order of magnitude during summertime. Two factors stand out as reasons to select Erymanthos sub-basin as a case study. First, the sub-basin presents a significant variety of ecosystems and comprises a very important river system, since Erymanthos Tributary satisfies, among other uses, drinking water supply for a great majority of citizens in the region. Second, authors' experience of the study area in Research Program Pythagoras II, funded by the European Social Fund (ESF) and the Operational Program for Educational and Vocational Training II (EPEAEK II) of Greece, offers a basis for better understanding of the real problems in the area. Erymanthos watershed, in fact, faces a lot of pressures, in several levels, provoked by human activities and Erymanthos Tributary is vulnerable to pollution. Recognizing the importance of clean water for healthy people, a developing economy, and a sustainable environment, the challenge of the present paper is elaborating human-induced pressures in the study area, analyzing their effects, estimating pollution factors and proposing integrated solutions/tools and a number of methodologies/initiatives used to overcome the problem of contaminating water supply in a catchment that lacks of wastewater treatment and disposal systems. The preservation of a good ecological status in Erymanthos River is not only a necessity for achieving the goals of EU Water

  20. Tank Farms Technical Safety Requirements. Volume 1 and 2

    International Nuclear Information System (INIS)

    CASH, R.J.

    2000-01-01

    The Technical Safety Requirements (TSRs) define the acceptable conditions, safe boundaries, basis thereof, and controls to ensure safe operation during authorized activities, for facilities within the scope of the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR)

  1. Tank Farms Technical Safety Requirements [VOL 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    CASH, R.J.

    2000-12-28

    The Technical Safety Requirements (TSRs) define the acceptable conditions, safe boundaries, basis thereof, and controls to ensure safe operation during authorized activities, for facilities within the scope of the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR).

  2. The Journalism Agenda Guide (JAG: Proposal for Applied Research in Journalism (ARJ

    Directory of Open Access Journals (Sweden)

    Josenildo Luiz Guerra

    2016-12-01

    Full Text Available This article proposes the Journalism Agenda Guide (JAG, a technical tool for managing journalistic content. Developed from an Applied Research in Journalism (ARJ methodology, the Guide is based on articulating concepts of Agenda Setting, Journalistic Relevance (JR, organizational productivity and Semantic Resolution (SR. The basis of the Guide is the relation between the relevance of a theme and how much space it should occupy in the news, subject to a particular organization’s production capacity. Incorporating the Guide as a tool for editorial management means adopting practices of accountability which affect both the ethical conduct an organization and its professionals adhere to and the sustainability of companies, becoming an important ally in the efforts to consolidate the credibility in journalism.

  3. Preventive maintenance basis: Volume 37 -- Main turbine EHC hydraulics. Final report

    International Nuclear Information System (INIS)

    Worledge, D.; Hinchcliffe, G.

    1998-11-01

    US nuclear power plants are implementing preventive maintenance (PM) tasks with little documented basis beyond fundamental vendor information to support the tasks or their intervals. The Preventive Maintenance Basis project provides utilities with the technical basis for PM tasks and task intervals associated with 40 specific components such as valves, electric motors, pumps, and HVAC equipment. This document provides a program of preventive maintenance tasks suitable for application to the main turbine EHC hydraulic fluid and associated components. The PM tasks that are recommended provide a cost-effective way to intercept the causes and mechanisms that lead to degradation and failure. They can be used in conjunction with material from other sources, to develop a complete PM program or to improve an existing program

  4. Small wind turbines - Technical sheet

    International Nuclear Information System (INIS)

    2015-02-01

    This publication first proposes an overview of the technical context of small wind turbines (from less than 1 kW to 36 kW). It discusses issues related to mast height, indicates the various technologies in terms of machine geometry (vertical or horizontal axis), of mast and foundations, of mechanism of orientation with respect to the wind. It also outlines that power curves are not always reliable due to a lack of maturity of techniques and technologies. Other issues are discussed: wind characteristics, and the assessment of the national potential source. The next parts address the regulatory and economic context, environmental impacts (limited impact on landscape, noise), propose an overview of actors and market (supply and demand of small wind turbines in the USA and in France, actors involved in the chain value in France), and give some recommendations for the development of small wind turbines in France. The last part proposes a technical focus on self-consumption by professional in rural areas (production and consumption in farms)

  5. A Proposed Theoretical Model Using the Work of Thomas Kuhn, David Ausubel, and Mauritz Johnson as a Basis for Curriculum and Instruction Decisions in Science Education.

    Science.gov (United States)

    Bowen, Barbara Lynn

    This study presents a holistic framework which can be used as a basis for decision-making at various points in the curriculum-instruction development process as described by Johnson in a work published in 1967. The proposed framework has conceptual bases in the work of Thomas S. Kuhn and David P. Ausubel and utilizes the work of several perceptual…

  6. Technical Basis For Radiological Acceptance Criteria For Uranium At The Y-12 National Security Complex

    Energy Technology Data Exchange (ETDEWEB)

    Veinot, K. G.

    2009-07-22

    The purpose of this report is to establish radiological acceptance criteria for uranium. Other factors for acceptance not considered include criticality safety concerns, contaminants to the process stream, and impacts to the Safety Basis for the affected facilities. Three types of criteria were developed in this report. They include limits on external penetrating and non-penetrating radiation and on the internal hazard associated with inhalation of the material. These criteria are intended to alleviate the need for any special controls beyond what are normally utilized for worker protection from uranium hazards. Any proposed exceptions would require case-by-case evaluations to determine cost impacts and feasibility. Since Y-12 has set rigorous ALARA goals for worker doses, the external limits are based on assumptions of work time involved in the movement of accepted material plus the desire that external doses normally received are not exceeded, and set so that no special personnel monitoring would be required. Internal hazard controls were established so that dose contributions from non-uranium nuclides would not exceed 10% of that expected from the uranium component. This was performed using a Hazard Index (HI) previously established for work in areas contaminated with non-uranium nuclides. The radiological acceptance criteria for uranium are summarized in Table 1. Note that these limits are based on the assumption that radioactive daughter products have reached equilibrium.

  7. Coulomb interaction in the supermultiplet basis

    International Nuclear Information System (INIS)

    Ruzha, Ya.Kh.; Guseva, T.V.; Tamberg, Yu.Ya.; Vanagas, V.V.

    1989-01-01

    An approximate expression for the matrix elements of the Coulomb interaction operator in the supermultiplet basis has been derived with the account for the orbitally-nonsymmetric terms. From the general expression a simplified formula for the Coulomb interaction energy has been proposed. On the basis of the expression obtained the contribution of the Coulomb interaction to the framework of a strongly restricted dynamic model in the light (4≤A≤40) and heavy (158≤A≤196) nuclei region has been studied. 19 refs.; 4 tabs

  8. System Design and the Safety Basis

    International Nuclear Information System (INIS)

    Ellingson, Darrel

    2008-01-01

    The objective of this paper is to present the Bechtel Jacobs Company, LLC (BJC) Lessons Learned for system design as it relates to safety basis documentation. BJC has had to reconcile incomplete or outdated system description information with current facility safety basis for a number of situations in recent months. This paper has relevance in multiple topical areas including documented safety analysis, decontamination and decommissioning (D and D), safety basis (SB) implementation, safety and design integration, potential inadequacy of the safety analysis (PISA), technical safety requirements (TSR), and unreviewed safety questions. BJC learned that nuclear safety compliance relies on adequate and well documented system design information. A number of PIS As and TSR violations occurred due to inadequate or erroneous system design information. As a corrective action, BJC assessed the occurrences caused by systems design-safety basis interface problems. Safety systems reviewed included the Molten Salt Reactor Experiment (MSRE) Fluorination System, K-1065 fire alarm system, and the K-25 Radiation Criticality Accident Alarm System. The conclusion was that an inadequate knowledge of system design could result in continuous non-compliance issues relating to nuclear safety. This was especially true with older facilities that lacked current as-built drawings coupled with the loss of 'historical knowledge' as personnel retired or moved on in their careers. Walkdown of systems and the updating of drawings are imperative for nuclear safety compliance. System design integration with safety basis has relevance in the Department of Energy (DOE) complex. This paper presents the BJC Lessons Learned in this area. It will be of benefit to DOE contractors that manage and operate an aging population of nuclear facilities

  9. Management of technical documents: a projection at the University of Zulia

    Directory of Open Access Journals (Sweden)

    Ana Judith Paredes Chacin

    2015-11-01

    Full Text Available Objective. This paper analyze comprehensively and systematically the principles of organization and technical procedure, which support document management based on the use of information technologies. Method. We developed a study based on the documentary descriptive method in the context of the Dirección de Infraestructura (Dinfra from the Universidad del Zulia. Results. We find evidence of efficiency in the processes that support the management of technical documents: Plans, metrics and memories generated by the Dinfra. Conclusion. The conceptual basis of organizational and technical archives contribute to the systematization, shelter save and documental preservation, and ensure the timely retrieval of technical information for the management of the University of Zulia.

  10. Technical evaluation report on the proposed amendment to the technical specifications on the reactor protection system and the engineered safety features actuation system for Ft. Calhoun, Unit No. 1

    International Nuclear Information System (INIS)

    Selan, J.C.

    1982-01-01

    This report documents the technical evaluation of the application to amend the Technical Specifications for the Ft. Calhoun Unit No. 1 Nuclear Generating Plant. The review criteria are based on the Technical Specifications of St. Lucie and Calvert Cliffs, IEEE Standards, Combustion Engineering Standard Technical Specifications, and the Code of Federal Regulations. The evaluation compares the submittal made by the licensee with the NRC staff position and the review criteria and presents the reviewer's conclusion on the acceptability of the application to amend the Technical Specifications

  11. Nonlinear System Identification via Basis Functions Based Time Domain Volterra Model

    Directory of Open Access Journals (Sweden)

    Yazid Edwar

    2014-07-01

    Full Text Available This paper proposes basis functions based time domain Volterra model for nonlinear system identification. The Volterra kernels are expanded by using complex exponential basis functions and estimated via genetic algorithm (GA. The accuracy and practicability of the proposed method are then assessed experimentally from a scaled 1:100 model of a prototype truss spar platform. Identification results in time and frequency domain are presented and coherent functions are performed to check the quality of the identification results. It is shown that results between experimental data and proposed method are in good agreement.

  12. Technical note An investigation of the franchising option for water ...

    African Journals Online (AJOL)

    Technical note An investigation of the franchising option for water services operation ... of water services, and outlines the need to formulate a franchise model that ... made available to emerging entrepreneurs as the basis of a viable business.

  13. SENTINEL trademark technical basis report for Peach Bottom. Final report

    International Nuclear Information System (INIS)

    1998-04-01

    PECO Energy in cooperation with the Electric Power Research Institute (EPRI) installed the SENTINEL trademark software at its Peach Bottom Atomic Power Station (PBAPS). This software incorporates models of the safety and support systems which are used to display the defense in depth present in the plant and a quantitative assessment of the plant risks during proposed on-line maintenance. During the past nine months, PECO Energy personnel have used this display to evaluate the safety of proposed on-line maintenance schedules. The report describes the motivation for and the development of the SENTINEL software. It describes the generation of Safety Function Assessment Trees and Plant Transient Assessment Trees and their use in evaluating the level of defense-in-depth of key plant safety functions and the susceptibility of the plant to critical transient events. Their results are displayed by color indicators ranging from green, through yellow and orange, to red to show increasingly hazardous conditions. The report describes the use of the PBAPS Probabilistic Safety Assessment within the SENTINEL code to calculate an instantaneous core damage frequency and the criteria by which this frequency is translated to a color indicator

  14. Shift technical advisors: in the eyes of the NRC

    International Nuclear Information System (INIS)

    Crocker, L.P.

    1981-01-01

    Since January 1, 1980, the NRC has required that Shift Technical Advisors be on-shift at all operating nuclear power plants. The objective of the requirement is to assure that technical expertise is immediately available to each operating shift to assess off-normal events and to provide advice to control room personnel. Further, this advice and assistance is to be provided by an individual not responsible for control manipulations or for directing the activities of reactor operators. The long-term requirement for on-shift technical expertise is firm. However, the exact manner in which this expertise must be furnished has not been determined. Licensees have proposed various alternatives to meet this requirement. These proposals still are being reviewed by the NRC staff

  15. Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 2: Technical basis and discussion of results

    International Nuclear Information System (INIS)

    Waters, R.D.; Gruebel, M.M.; Hospelhorn, M.B.

    1996-03-01

    A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 first describes the screening process used to determine the sites to be considered in the PEs. This volume then provides the technical details of the methodology for conducting the performance evaluations. It also provides a comparison and analysis of the overall results for all sites that were evaluated. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site

  16. Competition and safety as reflected in the legislation concerning technical supervision - are they incompatible

    International Nuclear Information System (INIS)

    Roth, H.A.

    1986-01-01

    The author discusses the conflicts between competition and safety in the legislation on technical supervision, the requirements on specific sectors, and the consequences of the concentration of the functions of technical supervision in the hands of the Technical Supervisory Board (TUEV). The demand to give more room for competition is found to have no legal basis in fundamental law. It therefore rests with the legislator to concert the one with the other. (orig./HP) [de

  17. Composite fermion basis for two-component Bose gases

    Science.gov (United States)

    Meyer, Marius; Liabotro, Ola

    The composite fermion (CF) construction is known to produce wave functions that are not necessarily orthogonal, or even linearly independent, after projection. While usually not a practical issue in the quantum Hall regime, we have previously shown that it presents a technical challenge for rotating Bose gases with low angular momentum. These are systems where the CF approach yield surprisingly good approximations to the exact eigenstates of weak short-range interactions, and so solving the problem of linearly dependent wave functions is of interest. It can also be useful for studying CF excitations for fermions. Here we present several ways of constructing a basis for the space of ``simple CF states'' for two-component rotating Bose gases in the lowest Landau level, and prove that they all give a basis. Using the basis, we study the structure of the lowest-lying state using so-called restricted wave functions. We also examine the scaling of the overlap between the exact and CF wave functions at the maximal possible angular momentum for simple states. This work was financially supported by the Research Council of Norway.

  18. [Flexible ENT endoscopy--video technic].

    Science.gov (United States)

    Rasinger, G A; Horak, F

    1985-02-01

    This study discusses the solutions to the problem of documenting moving processes in the field of otolaryngology. A flexible bronchoscope and video equipment connected to it are presented as a specific solution of the problem, with ample of observations. A technical comparison is used as the basis for a discussion of the pros and cons of the video and film techniques. A successful arrangement of examination facilities illustrates the future of flexible-endoscope techniques in the field of otolaryngology.

  19. Working group 1A - basis for the standard-safety

    International Nuclear Information System (INIS)

    Whipple, C.

    1993-01-01

    This paper presents a summary of the progress made by working group 1A (Basis for the Safety Standard) during the Electric Power Research Institute's EPRI Workshop on the technical basis of EPA HLW Disposal Criteria, March 1993. This group discussed the semantics of terms within the standard 40 CFR Part 191, the implementation of this standard, the advanced notice of rulemaking, the issue of emitting carbon-14 through a gaseous pathway, the strategy of dealing with standards for contamination of drinking water and groundwater, the 100,000 year time frame, and the analysis of specific comments. The specific comments dealt with the cost effectiveness of the standard, the dose histogram for populations and individuals, groundwater definition and the underlying technology driver for this standard

  20. Research on technical trading and market efficiency : a trader's perspective

    OpenAIRE

    Vico-Ivanina, Julianna V.

    2012-01-01

    Research on the predictive power of technical analysis is a matter of controversy. The objective of this thesis is to look at the empirical research done on technical trading and see how the results can be used from a trader’s perspective. Some results provide strong support for the technical trading and propose useful trading strategies. However, there are some limitations regarding transaction costs, risk adjustment, and statistical tests. Technical research has developed new methodology ap...

  1. Technical writing versus technical writing

    Science.gov (United States)

    Dillingham, J. W.

    1981-01-01

    Two terms, two job categories, 'technical writer' and 'technical author' are discussed in terms of industrial and business requirements and standards. A distinction between 'technical writing' and technical 'writing' is made. The term 'technical editor' is also considered. Problems inherent in the design of programs to prepare and train students for these jobs are discussed. A closer alliance between industry and academia is suggested as a means of preparing students with competent technical communication skills (especially writing and editing skills) and good technical skills.

  2. Technical Notes: Notes and Proposed Guidelines on Updated ...

    African Journals Online (AJOL)

    In light of recent expansion in the planning and construction of major building structures as well as other infrastructures such as railways, masshousing, dams, bridges, etc, this paper reviews the extent of seismic hazard in Ethiopia and proposes a review and update of the current out-dated and - in most cases ...

  3. Production of biosolid fuels from municipal sewage sludge: Technical and economic optimisation.

    Science.gov (United States)

    Wzorek, Małgorzata; Tańczuk, Mariusz

    2015-08-01

    The article presents the technical and economic analysis of the production of fuels from municipal sewage sludge. The analysis involved the production of two types of fuel compositions: sewage sludge with sawdust (PBT fuel) and sewage sludge with meat and bone meal (PBM fuel). The technology of the production line of these sewage fuels was proposed and analysed. The main objective of the study is to find the optimal production capacity. The optimisation analysis was performed for the adopted technical and economic parameters under Polish conditions. The objective function was set as a maximum of the net present value index and the optimisation procedure was carried out for the fuel production line input capacity from 0.5 to 3 t h(-1), using the search step 0.5 t h(-1). On the basis of technical and economic assumptions, economic efficiency indexes of the investment were determined for the case of optimal line productivity. The results of the optimisation analysis show that under appropriate conditions, such as prices of components and prices of produced fuels, the production of fuels from sewage sludge can be profitable. In the case of PBT fuel, calculated economic indexes show the best profitability for the capacity of a plant over 1.5 t h(-1) output, while production of PBM fuel is beneficial for a plant with the maximum of searched capacities: 3.0 t h(-1). Sensitivity analyses carried out during the investigation show that influence of both technical and economic assessments on the location of maximum of objective function (net present value) is significant. © The Author(s) 2015.

  4. An Intelligent technical analysis using neural network

    Directory of Open Access Journals (Sweden)

    Reza Raei

    2011-07-01

    Full Text Available Technical analysis has been one of the most popular methods for stock market predictions for the past few decades. There have been enormous technical analysis methods to study the behavior of stock market for different kinds of trading markets such as currency, commodity or stock. In this paper, we propose two different methods based on volume adjusted moving average and ease of movement for stock trading. These methods are used with and without generalized regression neural network methods and the results are compared with each other. The preliminary results on historical stock price of 20 firms indicate that there is no meaningful difference between various proposed models of this paper.

  5. Pedagogical characteristics of the systems for assessing the technical and tactical skills of qualified volleyball players

    Directory of Open Access Journals (Sweden)

    Мykhailo Oliinyk

    2017-12-01

    Full Text Available Purpose: on the basis of the analysis of the special literature and their own experimental studies, to determine the characteristics of the systems for assessing the technical and tactical skills of qualified volleyball players. Material & Methods: study was conducted on the basis of the material of the national team of Zaporozhye State Medical University on volleyball. Analysis and generalization of the data of scientific and methodical literature are used; registration, analysis and interpretation of indicators of technical and tactical actions of qualified volleyball players in training and competitive processes; pedagogical observations; algorithms for calculating the quantitative and qualitative indicators of technical and tactical skill in volleyball; methods of mathematical statistics. Results: data on the existence of a strong statistical relationship between the systems of assessment of technical and tactical skills of qualified volleyball players, taking into account the specificity of the game role. Conclusion: shows the specifics of the application of various systems for assessing the technical and tactical skills of qualified volleyball players, taking into account the factors of the game role, noted the methodological features of special analysis and interpretation of indicators of technical and tactical actions in the adversarial process.

  6. Diffusion Forecasting Model with Basis Functions from QR-Decomposition

    Science.gov (United States)

    Harlim, John; Yang, Haizhao

    2017-12-01

    The diffusion forecasting is a nonparametric approach that provably solves the Fokker-Planck PDE corresponding to Itô diffusion without knowing the underlying equation. The key idea of this method is to approximate the solution of the Fokker-Planck equation with a discrete representation of the shift (Koopman) operator on a set of basis functions generated via the diffusion maps algorithm. While the choice of these basis functions is provably optimal under appropriate conditions, computing these basis functions is quite expensive since it requires the eigendecomposition of an N× N diffusion matrix, where N denotes the data size and could be very large. For large-scale forecasting problems, only a few leading eigenvectors are computationally achievable. To overcome this computational bottleneck, a new set of basis functions constructed by orthonormalizing selected columns of the diffusion matrix and its leading eigenvectors is proposed. This computation can be carried out efficiently via the unpivoted Householder QR factorization. The efficiency and effectiveness of the proposed algorithm will be shown in both deterministically chaotic and stochastic dynamical systems; in the former case, the superiority of the proposed basis functions over purely eigenvectors is significant, while in the latter case forecasting accuracy is improved relative to using a purely small number of eigenvectors. Supporting arguments will be provided on three- and six-dimensional chaotic ODEs, a three-dimensional SDE that mimics turbulent systems, and also on the two spatial modes associated with the boreal winter Madden-Julian Oscillation obtained from applying the Nonlinear Laplacian Spectral Analysis on the measured Outgoing Longwave Radiation.

  7. 76 FR 35864 - Proposed Priority; Special Demonstration Programs-National Technical Assistance Projects To...

    Science.gov (United States)

    2011-06-20

    ... have national significance and improve the performance of State vocational rehabilitation (VR) agencies... Centers, the American Indian Vocational Rehabilitation Technical Assistance Center, and the Independent... of each priority as absolute, competitive preference, or invitational through a notice in the Federal...

  8. Physical-technical quality control for medical x-ray apparatus

    International Nuclear Information System (INIS)

    Aalbers, A.H.L.

    1989-01-01

    The technical aspects of quality control in medial x-ray diagnostics are discussed. It is recommended to hurry, also in the Netherlands, on the basis of already existing starting-up's abroad, with drawing up quality standards and judgement criteria. (author). 6 refs.; 2 figs.; 1 tab

  9. Optimization of the variational basis in the three body problem

    International Nuclear Information System (INIS)

    Simenog, I.V.; Pushkash, O.M.; Bestuzheva, A.B.

    1995-01-01

    The procedure of variational oscillator basis optimization is proposed to the calculation the energy spectra of three body systems. The hierarchy of basis functions is derived and energies of ground and excited states for three gravitating particles is obtained with high accuracy. 12 refs

  10. Collaborating for Success: Team Teaching the Engineering Technical Thesis

    Science.gov (United States)

    Keating, Terrence; Long, Mike

    2012-01-01

    This paper will examine the collaborative teaching process undertaken at College of the North Atlantic-Qatar (CNA-Q) by Engineering and the Communication faculties to improve the overall quality of engineering students' capstone projects known as the Technical Thesis. The Technical Thesis is divided into two separate components: a proposal stage…

  11. Technical and economic assessment of energy conversion technologies for MSW

    Energy Technology Data Exchange (ETDEWEB)

    Livingston, W.R.

    2002-07-01

    Thermal processes for municipal solid wastes (MSW) based on pyrolysis and/or gasification that have relevance to the emerging UK market are described in this report, and the results of the technical and economical assessment of these processes are presented. The Mitsui R21 Technology, the Thermoselect Process, the Nippon Steel Waste Melting Process, the Pyropleq Process, and the Compact Power Process are selected for detailed comparison on the basis of the overall technical concept, the energy balance and the requirements for consumables, environmental performance, and the technical and commercial status of the technology. Details are also given of a comparison of the novel thermal technologies with conventional mass burn incineration for MSW.

  12. Technical and economic assessment of energy conversion technologies for MSW

    International Nuclear Information System (INIS)

    Livingston, W.R.

    2002-01-01

    Thermal processes for municipal solid wastes (MSW) based on pyrolysis and/or gasification that have relevance to the emerging UK market are described in this report, and the results of the technical and economical assessment of these processes are presented. The Mitsui R21 Technology, the Thermoselect Process, the Nippon Steel Waste Melting Process, the Pyropleq Process, and the Compact Power Process are selected for detailed comparison on the basis of the overall technical concept, the energy balance and the requirements for consumables, environmental performance, and the technical and commercial status of the technology. Details are also given of a comparison of the novel thermal technologies with conventional mass burn incineration for MSW

  13. Requirements on the provisional safety analyses and technical comparison of safety measures

    International Nuclear Information System (INIS)

    2010-04-01

    The concept of a Geological Underground Repository (SGT) was adopted by the Swiss Federal Council on April 2 nd , 2008. It fixes the goals and the safety technical criteria as well as the procedures for the choice of the site for an underground repository. Those responsible for waste management evaluate possible site regions according to the present status of geological knowledge and based on the safety criteria defined in SGT as well as on technical feasibility. In a first step, they propose geological repository sites for high level (HAA) and for low and intermediate level (SMA) radioactive wastes and justify their choice in a report delivered to the Swiss Federal Office of Energy. The Swiss Federal Council reviews the choices presented and, in the case of positive evaluation, approves them and considers them as an initial orientation. In a second step, based on the possible sites according to step 1, the waste management institution responsible has to reduce the repositories chosen for HAA and SMA by taking into account safety aspects, technical feasibility as well as space planning and socio-economical aspects. In making this choice, safety aspects have the highest priority. The criteria used for the evaluation in the first step have to be defined using provisional quantitative safety analyses. On the basis of the whole appraisal, including space planning and socio-economical aspects, those responsible for waste management propose at least two repository sites for HAA- and SMA-waste. Their selection is then reviewed by the authorities and, in the case of a positive assesment, the selection is taken as an intermediate result. The remaining sites are further studied to examine site choice and the delivery of a request for a design license. If necessary, the requested geological knowledge has to be confirmed by new investigations. Based on the results of the choosing process and a positive evaluation by the safety authorities, the Swiss Federal Council has to

  14. Neuromorphic elements and systems as the basis for the physical implementation of artificial intelligence technologies

    Science.gov (United States)

    Demin, V. A.; Emelyanov, A. V.; Lapkin, D. A.; Erokhin, V. V.; Kashkarov, P. K.; Kovalchuk, M. V.

    2016-11-01

    The instrumental realization of neuromorphic systems may form the basis of a radically new social and economic setup, redistributing roles between humans and complex technical aggregates. The basic elements of any neuromorphic system are neurons and synapses. New memristive elements based on both organic (polymer) and inorganic materials have been formed, and the possibilities of instrumental implementation of very simple neuromorphic systems with different architectures on the basis of these elements have been demonstrated.

  15. Mark III LOCA-related hydrodynamic load definition. Generic technical activity B-10

    International Nuclear Information System (INIS)

    1984-02-01

    This report, prepared by the staff of the Office of Nuclear Reactor Regulation and its consultants at the Brookhaven National Laboratory, provides a discussion of LOCA-related suppression pool hydrodynamic loads in boiling water reactor (BWR) facilities with the Mark III pressure-suppression containment design. Its issuance completes NRC Generic Technical Activity B-10, Behavior of BWR Mark III Containment. On the basis of certain large-scale tests conducted between 1973 and 1979, the General Electric Company developed LOCA-related hydrodynamic load definitions for use in the design of the standard Mark III containment. The staff and its consultants have reviewed these load definitions and their bases conclude that, with a few specified changes, the proposed load definitions provide conservative loading conditions. The staff-approved acceptance criteria for LOCA-related hydrodynamic loads are provided in Appendix C of this report

  16. Proposal strategy and policy on nuclear safety for no-more severe accidents

    International Nuclear Information System (INIS)

    2013-01-01

    Following the outspoken advice saying 'scientists and engineers concerning with nuclear power promotion and safety should be responsible for clarifying how preventable or what measures should be needed to prevent severe accidents occurring at Fukushima Daiichi nuclear power plants (NPPs)', committee on prevention of severe accidents at NPPs was established by relevant nuclear scientists and engineers involved so as to discuss basic issues to be solved from scientific and technical viewpoints. Based on the review of 'defense in depth' concept and accident analysis at Fukushima nuclear accident, four major proposals and six supplements to be established were identified such as: (1) finding mechanism of beyond imagination events for natural disaster, terrorism, and internal events, (2) reform of comprehensive safety standards and guidelines with performance basis easy to reflect latest knowledge and technology as 'back-fitting', (3) severe accidents measures, their validation, and drilling on accident management to advance procedures and develop human resources, and (4) risk communications and public disclosure of information. This article described backgrounds of committee's proposals on nuclear safety for no-more severe accidents. (T. Tanaka)

  17. 7 CFR 1728.50 - Removal of an item from listing or technical acceptance.

    Science.gov (United States)

    2010-01-01

    ... equipment will be notified in writing of a proposal to remove such item from the listing or technical... unanimous, the item will be referred to Technical Standards Committee “B.” Written notice of Technical...” decision, a sponsor may appeal in writing to Technical Standards Committee “B” to review Committee “A's...

  18. Basis set construction for molecular electronic structure theory: natural orbital and Gauss-Slater basis for smooth pseudopotentials.

    Science.gov (United States)

    Petruzielo, F R; Toulouse, Julien; Umrigar, C J

    2011-02-14

    A simple yet general method for constructing basis sets for molecular electronic structure calculations is presented. These basis sets consist of atomic natural orbitals from a multiconfigurational self-consistent field calculation supplemented with primitive functions, chosen such that the asymptotics are appropriate for the potential of the system. Primitives are optimized for the homonuclear diatomic molecule to produce a balanced basis set. Two general features that facilitate this basis construction are demonstrated. First, weak coupling exists between the optimal exponents of primitives with different angular momenta. Second, the optimal primitive exponents for a chosen system depend weakly on the particular level of theory employed for optimization. The explicit case considered here is a basis set appropriate for the Burkatzki-Filippi-Dolg pseudopotentials. Since these pseudopotentials are finite at nuclei and have a Coulomb tail, the recently proposed Gauss-Slater functions are the appropriate primitives. Double- and triple-zeta bases are developed for elements hydrogen through argon. These new bases offer significant gains over the corresponding Burkatzki-Filippi-Dolg bases at various levels of theory. Using a Gaussian expansion of the basis functions, these bases can be employed in any electronic structure method. Quantum Monte Carlo provides an added benefit: expansions are unnecessary since the integrals are evaluated numerically.

  19. Technical Support Document for Version 3.6.1 of the COMcheck Software

    Energy Technology Data Exchange (ETDEWEB)

    Bartlett, Rosemarie; Connell, Linda M.; Gowri, Krishnan; Halverson, Mark A.; Lucas, Robert G.; Richman, Eric E.; Schultz, Robert W.; Winiarski, David W.

    2009-09-29

    This technical support document (TSD) is designed to explain the technical basis for the COMcheck software as originally developed based on the ANSI/ASHRAE/IES Standard 90.1-1989 (Standard 90.1-1989). Documentation for other national model codes and standards and specific state energy codes supported in COMcheck has been added to this report as appendices. These appendices are intended to provide technical documentation for features specific to the supported codes and for any changes made for state-specific codes that differ from the standard features that support compliance with the national model codes and standards.

  20. Advisory panel on the proposed New Brunswick - Quebec electricity transaction

    International Nuclear Information System (INIS)

    Ganong, D.A.

    2010-01-01

    NB Power was faced with major financial and technical challenges in generation that would lead to significant rate increases over several years to come. In 2009, the governments of New Brunswick and Quebec proposed an agreement whereby Hydro-Quebec would acquire most of the assets of NB Power and provide a guaranteed electricity supply at a set price to the province. The proposal involved the sale of NB Power's hydro generation facilities, 2 diesel peaking plants and the Point Lepreau nuclear generating facility. It also included a guaranteed bulk electricity supply of 14 Terawatt-hours per year by Hydro-Quebec at a blended rate of 7.35 cents per kilowatt-hour. The new Brunswick government would retain ownership of the fossil-fuelled power plants, the NB Power transmission assets and the NB Power distribution assets and customer sales. A 6-person independent panel was asked to examine the proposal. This report addresses the proposed agreement as presented to the Panel up to January 26, 2010. The panel conducted an independent and objective examination of the financial implications; long-term effects on electricity rates; New Brunswick's control of energy policies; environmental impacts; short-and long-term risks and avoided risks; and benefits and costs to the provincial economy. The Panel drew its conclusions and recommendations on the basis of available information. The Panel concluded that the benefits to New Brunswick contribute to real and positive value to New Brunswick over business as usual. tabs., figs.

  1. Point Set Denoising Using Bootstrap-Based Radial Basis Function.

    Science.gov (United States)

    Liew, Khang Jie; Ramli, Ahmad; Abd Majid, Ahmad

    2016-01-01

    This paper examines the application of a bootstrap test error estimation of radial basis functions, specifically thin-plate spline fitting, in surface smoothing. The presence of noisy data is a common issue of the point set model that is generated from 3D scanning devices, and hence, point set denoising is one of the main concerns in point set modelling. Bootstrap test error estimation, which is applied when searching for the smoothing parameters of radial basis functions, is revisited. The main contribution of this paper is a smoothing algorithm that relies on a bootstrap-based radial basis function. The proposed method incorporates a k-nearest neighbour search and then projects the point set to the approximated thin-plate spline surface. Therefore, the denoising process is achieved, and the features are well preserved. A comparison of the proposed method with other smoothing methods is also carried out in this study.

  2. CERN Technical training: Available places in forthcoming courses

    CERN Multimedia

    HR Department

    2010-01-01

    The following course sessions are scheduled in the framework of the 2010 CERN Technical Training Programme and places are still available. You can find the full updated Technical Training course programme in our web catalogue. Software and system technologies ITIL Foundations (version 3) EXAMINATION\t13-DEC-10\t13-DEC-10\tEnglish\t1 hour Electronic design Cours de base Automation du bâtiment\t15-DEC-10\t17-DEC-10\tFrench\t3 jours Office software Sharepoint Collaboration Workspace\t13-DEC-10\t14-DEC-10\tEnglish\t2 days If you are interested in attending any of the above course sessions, please talk to your supervisor and/or your DTO, and apply electronically via EDH from the course description pages that can be found here under ‘Technical Training’ with the detailed course program. Registration for all courses is always open – sessions for the less-requested courses are organized on a demand-basis only. CERN Technical Training courses are open only to members of the CERN per...

  3. 31 CFR 21.205 - Professional and technical services.

    Science.gov (United States)

    2010-07-01

    ... technical services rendered directly in the preparation, submission, or negotiation of any bid, proposal, or... imposed by or pursuant to law as a condition for receiving that Federal contract, grant, loan, or... example, drafting of a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly...

  4. 14 CFR 1271.205 - Professional and technical services.

    Science.gov (United States)

    2010-01-01

    ... technical services rendered directly in the preparation, submission, or negotiation of any bid, proposal, or... imposed by or pursuant to law as a condition for receiving that Federal contract, grant, loan, or... example, drafting of a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly...

  5. 28 CFR 69.300 - Professional and technical services.

    Science.gov (United States)

    2010-07-01

    ... preparation, submission, or negotiation of any bid, proposal, or application for that Federal contract, grant, loan, or cooperative agreement or for meeting requirements imposed by or pursuant to law as a condition..., drafting or a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly, technical...

  6. Proposal of an ISO Standard: Classification of Transients and Accidents for Pressurized Water Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Jo, Jong Chull [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Chung, Bub Dong; Lee, Doo-Jeong; Kim, Jong In; Yoon, Ju Hyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Jeong, Jae Jun [Pusan National Univ., Busan (Korea, Republic of); Kim, An Sup; Lee, Sang Yoon [Korea Electric Association, Seoul (Korea, Republic of)

    2016-05-15

    Classification of the events for a nuclear power plant is a fundamental basis for defining nuclear safety functions, safety systems performing those functions, and specific acceptance criteria for safety analyses. Presently, the approaches for the event classification adopted by the nuclear suppliers are different, which makes a nuclear technology trade barrier. The IAEA and WENRA are making efforts to establish general requirements or guidelines on the classification of either plant states or defence-in-depth levels for the design of nuclear power plants. However, the requirements and guidelines do not provide the details for practical application to various types of commercial PWRs. Recently, Korea proposed a new ISO standardisation project to develop a harmonized or consolidated international standard for classifying the events in PWRs and for defining (or imposing) the acceptance criteria for reactor design and/or radiation protection corresponding to each event class. This paper briefs the method with strategies for developing the standard, the current various practices of the PWR event classification and acceptance criteria developed or adopted by several organizations in USA and Europe, and a draft of the proposed standard. The proposed standard will affect all the relevant stakeholders such as reactor designers, vendors, suppliers, utilities, regulatory bodies, and publics of the leading countries in the area of nuclear industry as well as utilities, regulatory bodies, and publics of the newly entering (starting) countries. It is expected that all of the stakeholders will benefit from the proposed deliverable which provides an internationally harmonized standard for classifying the PWR events as follows: The reactor design bases for assuring safety and related technical information can be effectively communicated and shared among them resulting in enhancement of the global nuclear safety and fosterage of the global nuclear trade. The countries starting

  7. A study on technical efficiency of a DMU (review of literature)

    Science.gov (United States)

    Venkateswarlu, B.; Mahaboob, B.; Subbarami Reddy, C.; Sankar, J. Ravi

    2017-11-01

    In this research paper the concept of technical efficiency (due to Farell) [1] of a decision making unit (DMU) has been introduced and the measure of technical and cost efficiencies are derived. Timmer’s [2] deterministic approach to estimate the Cobb-Douglas production frontier has been proposed. The idea of extension of Timmer’s [2] method to any production frontier which is linear in parameters has been presented here. The estimation of parameters of Cobb-Douglas production frontier by linear programming approach has been discussed in this paper. Mark et al. [3] proposed a non-parametric method to assess efficiency. Nuti et al. [4] investigated the relationships among technical efficiency scores, weighted per capita cost and overall performance Gahe Zing Samuel Yank et al. [5] used Data envelopment analysis to assess technical assessment in banking sectors.

  8. Closed fringe demodulation using phase decomposition by Fourier basis functions.

    Science.gov (United States)

    Kulkarni, Rishikesh; Rastogi, Pramod

    2016-06-01

    We report a new technique for the demodulation of a closed fringe pattern by representing the phase as a weighted linear combination of a certain number of linearly independent Fourier basis functions in a given row/column at a time. A state space model is developed with the weights of the basis functions as the elements of the state vector. The iterative extended Kalman filter is effectively utilized for the robust estimation of the weights. A coarse estimate of the fringe density based on the fringe frequency map is used to determine the initial row/column to start with and subsequently the optimal number of basis functions. The performance of the proposed method is evaluated with several noisy fringe patterns. Experimental results are also reported to support the practical applicability of the proposed method.

  9. Preventive maintenance basis: Volume 16 -- Power operated relief valves, solenoid actuated. Final report

    International Nuclear Information System (INIS)

    Worledge, D.; Hinchcliffe, G.

    1997-07-01

    US nuclear plants are implementing preventive maintenance (PM) tasks with little documented basis beyond fundamental vendor information to support the tasks or their intervals. The Preventive Maintenance Basis project provides utilities with the technical basis for PM tasks and task intervals associated with 40 specific components such as valves, electric motors, pumps, and HVAC equipment. This report provides an overview of the PM Basis project and describes use of the PM Basis database. This volume 16 of the report provides a program of PM tasks suitable for application to power operated relief valves (PORV's) that are solenoid actuated. The PM tasks that are recommended provide a cost-effective way to intercept the causes and mechanisms that lead to degradation and failure. They can be used, in conjunction with material from other sources, to develop a complete PM program or to improve an existing program. Users of this information will be utility managers, supervisors, craft technicians, and training instructors responsible for developing, optimizing, or fine-tuning PM programs

  10. Outcome indicators for the evaluation of energy policy instruments and technical change

    International Nuclear Information System (INIS)

    Neij, Lena; Astrand, Kerstin

    2006-01-01

    The aim of this paper is to propose a framework for the evaluation of policy instruments designed to affect development and dissemination of new energy technologies. The evaluation approach is based on the analysis of selected outcome indicators describing the process of technical change, i.e. the development and dissemination of new energy technologies, on the basis of a socio-technical systems approach. The outcome indicators are used to analyse the effect, in terms of outcome, and outcome scope of the policy instruments as well as the extent to which the policy instruments support diversity, learning and institutional change. The analysis of two cases of evaluations, of energy efficiency policy and wind energy policy in Sweden, shows that the approach has several advantages, allowing continuous evaluation and providing important information for the redesign of policy instruments. There are also disadvantages associated with the approach, such as complexity, possible high cost and the requirement of qualified evaluators. Nevertheless, it is concluded that the information on the continuous performance of different policy instruments and their effects on the introduction and dissemination of new energy technologies, provided by this evaluation approach, is essential for an improved adaptation and implementation of energy and climate policy

  11. Technical basis of radiation therapy. Practical clinical applications. 5. ed.

    Energy Technology Data Exchange (ETDEWEB)

    Levitt, Seymour H. [Karolinska Institutet Stockholm (Sweden). Dept. of Oncol-Pathol; Perez, Carlos A. [Washington Univ. Medical Center, St. Louis, MO (United States). Dept. of Radiation Oncology; Purdy, James A. [California Univ., Sacramento, CA (United States). Dept. of Radiation Oncology; Poortmans, Philip [Institute Verbeeten, Tilburg (Netherlands). Dept. of Radiation Oncology

    2012-07-01

    This well-received book, now in its fifth edition, is unique in providing a detailed description of the technological basis of radiation therapy. Another novel feature is the collaborative writing of the chapters by North American and European authors. This considerably broadens the book's perspective and increases its applicability in daily practice throughout the world. The book is divided into two sections. The first covers basic concepts in treatment planning, including essential physics and biological principles related to time-dose-fractionation, and explains the various technological approaches to radiation therapy, such as intensity-modulated radiation therapy, tomotherapy, stereotactic radiotherapy, and high and low dose rate brachytherapy. Issues relating to quality assurance, technology assessment, and cost-benefit analysis are also reviewed. The second part of the book discusses in depth the practical clinical applications of the different radiation therapy techniques in a wide range of cancer sites. All of the chapters have been written by leaders in the field. This book will serve to instruct and acquaint teachers, students, and practitioners in the various fields of oncology with the basic technological factors and approaches in radiation therapy. (orig.)

  12. Technical Demand of Commercial Paddy Farmers in the Context of Labor Transfer

    OpenAIRE

    Feng, Liang-xuan; Qi, Zhen-hong; Tian, Yun; Zhou, Hui

    2012-01-01

    On the basis of document research, we summed up factors of technical demand of commercial paddy farmers to four aspects: individual characteristics of farmers, natural endowment of resources, factors related to risks, and information factor. Then, we put forward relevant hypotheses. From survey results of 241 farmer households in 4 southwestern provinces (regions), by the binary logistic regression analysis method, we empirically studied influences of the above four factors on technical deman...

  13. Technical evaluation of the proposed deletion of a reactor trip on a turbine trip below 50-percent power for the Beaver Valley nuclear power plant, Unit 1

    International Nuclear Information System (INIS)

    Reeves, W.E.

    1979-12-01

    This report documents the technical evaluation of the Duquesne Light Company's proposed license amendment for the deletion of a reactor trip on a turbine trip below 50% power for the Beaver Valley nuclear power plant, Unit 1. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Program being conducted for the US Nuclear Regulatory Commission by Lawrence Livermore Laboratory

  14. Social-technical design for evaluation of student's behaviour and expectations

    DEFF Research Database (Denmark)

    John, Claudette; Kampf, Constance Elizabeth; Briollet, Alexandra

    2015-01-01

    . So, we focus here on the evaluation process based on socio-technical design that allows integrating student’s behaviour and expectations. A Web App has been constructed and tested on an exploratory basis to get real-time insights about the combination of theory, course and practical applications......This paper focuses on the usability of new technologies and real-time socio-technical features for evaluation issues in student’s courses. The evaluation of content and forms of knowledge taught within a course are directly linked to behaviour, perception and expectations from the student’s side...

  15. Establishment of Technical Collaboration basis between Korea and France for the development of severe accident assessment computer code under high burnup condition

    International Nuclear Information System (INIS)

    Kim, H. D.; Kim, D. H.; Park, S. Y.; Park, J. H.

    2005-10-01

    This project was performed by KAERI in the frame of construction of the international cooperative basis on the nuclear energy. This was supported from MOST under the title of 'Establishment of Technical Collaboration basis between Korea and France for the development of severe accident assessment computer code under high burn up condition'. The current operating NPP are converting the burned fuel to the wasted fuel after burn up of 40 GWD/MTU. But in Korea, burn up of more than 60 GWD/MTU will be expected because of the high fuel efficiency but also cost saving for storing the wasted fuel safely. The domestic research for the purpose of developing the fuel and the cladding that can be used under the high burn up condition up to 100 GWD/MTU is in progress now. But the current computer code adopts the model and the data that are valid only up to the 40 GWD/MTU at most. Therefore the current model could not take into account the phenomena that may cause differences in the fission product release behavior or in the core damage process due to the high burn up operation (more than 40 GWD/MTU). To evaluate the safety of the NPP with the high burn up fuel, the improvement of current severe accident code against the high burn up condition is an important research item. Also it should start without any delay. Therefore, in this study, an expert group was constructed to establish the research basis for the severe accident under high burn up conditions. From this expert group, the research items regarding the high burn up condition were selected and identified through discussion and technical seminars. Based on these selected items, the meeting between IRSN and KAERI to find out the cooperative research items on the severe accident under the high burn up condition was held in the IRSN headquater in Paris. After the meeting, KAERI and IRSN agreed to cooperate with each other on the selected items, and to co-host the international seminar, and to develop the model and to

  16. Hanford Tank Farm Vapors Abatement Technology and Vendor Proposals Assessment

    International Nuclear Information System (INIS)

    Burns, H. H.; Farrar, M. E.; Fink, S. D.

    2016-01-01

    Suspected chemical vapor releases from the Hanford nuclear waste tank system pose concerns for worker exposure. Washington River Protection Solutions (WRPS) contracted the Savannah River National Laboratory (SRNL) to explore abatement technologies and strategies to remediate the vapors emitted through the ventilation system. In response, SRNL conducted an evaluation of technologies to abate, or reduce, vapor emissions to below 10% of the recognized occupational exposure limits (OELs). The evaluation included a review of published literature and a broadly communicated Request for Information to commercial vendors through a Federal Business Opportunities (Fed Biz Opps) web posting. In addition, SRNL conducted a workshop and post-workshop conference calls with interested suppliers (vendors) to assess proposals of relevant technologies. This report reviews applicable technologies and summarizes the approaches proposed by the vendors who participated in the workshop and teleconference interviews. In addition, the report evaluates the estimated performance of the individual technologies for the various classes of chemical compounds present in the Hanford Chemicals of Potential Concern (COPCs) list. Similarly, the report provides a relative evaluation of the vendor proposed approaches against criteria of: technical feasibility (and maturity), design features, operational considerations, secondary waste generation, safety/regulatory, and cost / schedule. These rough order-of-magnitude (ROM) cost estimates are intended to provide a comparison basis between technologies and are not intended to be actual project estimates.

  17. Hanford Tank Farm Vapors Abatement Technology and Vendor Proposals Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Burns, H. H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Farrar, M. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Fink, S. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-09-20

    Suspected chemical vapor releases from the Hanford nuclear waste tank system pose concerns for worker exposure. Washington River Protection Solutions (WRPS) contracted the Savannah River National Laboratory (SRNL) to explore abatement technologies and strategies to remediate the vapors emitted through the ventilation system. In response, SRNL conducted an evaluation of technologies to abate, or reduce, vapor emissions to below 10% of the recognized occupational exposure limits (OELs). The evaluation included a review of published literature and a broadly communicated Request for Information to commercial vendors through a Federal Business Opportunities (Fed Biz Opps) web posting. In addition, SRNL conducted a workshop and post-workshop conference calls with interested suppliers (vendors) to assess proposals of relevant technologies. This report reviews applicable technologies and summarizes the approaches proposed by the vendors who participated in the workshop and teleconference interviews. In addition, the report evaluates the estimated performance of the individual technologies for the various classes of chemical compounds present in the Hanford Chemicals of Potential Concern (COPCs) list. Similarly, the report provides a relative evaluation of the vendor proposed approaches against criteria of: technical feasibility (and maturity), design features, operational considerations, secondary waste generation, safety/regulatory, and cost / schedule. These rough order-of-magnitude (ROM) cost estimates are intended to provide a comparison basis between technologies and are not intended to be actual project estimates.

  18. SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747

    Energy Technology Data Exchange (ETDEWEB)

    RYAN GW

    2007-09-24

    'Designing in Safety' is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation IOCFR830, Nuclear Safety Management. IOCFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses 'Safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE's Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, (1) flashing spray leaks and (2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents.

  19. SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747

    International Nuclear Information System (INIS)

    RYAN GW

    2007-01-01

    'Designing in Safety' is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation IOCFR830, Nuclear Safety Management. IOCFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses 'Safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE's Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, (1) flashing spray leaks and (2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents

  20. Solar Power Tower Design Basis Document, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    ZAVOICO,ALEXIS B.

    2001-07-01

    This report contains the design basis for a generic molten-salt solar power tower. A solar power tower uses a field of tracking mirrors (heliostats) that redirect sunlight on to a centrally located receiver mounted on top a tower, which absorbs the concentrated sunlight. Molten nitrate salt, pumped from a tank at ground level, absorbs the sunlight, heating it up to 565 C. The heated salt flows back to ground level into another tank where it is stored, then pumped through a steam generator to produce steam and make electricity. This report establishes a set of criteria upon which the next generation of solar power towers will be designed. The report contains detailed criteria for each of the major systems: Collector System, Receiver System, Thermal Storage System, Steam Generator System, Master Control System, and Electric Heat Tracing System. The Electric Power Generation System and Balance of Plant discussions are limited to interface requirements. This design basis builds on the extensive experience gained from the Solar Two project and includes potential design innovations that will improve reliability and lower technical risk. This design basis document is a living document and contains several areas that require trade-studies and design analysis to fully complete the design basis. Project- and site-specific conditions and requirements will also resolve open To Be Determined issues.

  1. Food Safety and Sanitary Practices of Selected Hotels in Batangas Province, Philippines: Basis of Proposed Enhancement Measures

    Directory of Open Access Journals (Sweden)

    April M. Perez

    2017-02-01

    Full Text Available This study assessed the extent of food safety and sanitary practices of selected hotels in Batangas province as basis of proposed enhancement measures. The study utilized descriptive method to describe food safety and sanitary practices of selected hotels in Batangas province with a total of 8 hotels (256 respondents. Purposive sampling was used in the study. The questionnaires were designed using the provision of the Sanitation Code of the Philippines, validated and finalized to come up with legitimate results. The study showed that there were eight (8 hotel respondents classified as two, three, four star with considerable years of experience and adequate number of employees. The hotels demonstrated the food safety and sanitary practices always in the areas of restaurant, bar service, catering and banquet and room service. The significant pair-wise comparison for restaurant, bar service, catering and banquet and room service shows that 2 star hotels greatly differs. The researcher recommends that the management should maintain high standard of food safety and sanitary practices among its staff, upgrade the food safety and sanitary practices for food safety accreditation, continuous training of the hotel managers/employees on food safety and sanitary practices.

  2. Technical basis for the ITER final design report, cost review and safety analysis (FDR)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

    The ITER final design report, cost review and safety analysis (FDR) is the 4th major milestone, representing the progress made in the ITER Engineering Design Activities. With the approval of the Detailed Design Report (DDR), the design work was concentrated on the requirements of operation, with only relatively minor changes to design concepts of major components. The FDR is the culmination of almost 6 years collaborative design and supporting technical work by the ITER Joint Central Team and Home Teams under the terms of the ITER EDA Agreement. Refs, figs, tabs

  3. Technical basis for the ITER final design report, cost review and safety analysis (FDR)

    International Nuclear Information System (INIS)

    1998-01-01

    The ITER final design report, cost review and safety analysis (FDR) is the 4th major milestone, representing the progress made in the ITER Engineering Design Activities. With the approval of the Detailed Design Report (DDR), the design work was concentrated on the requirements of operation, with only relatively minor changes to design concepts of major components. The FDR is the culmination of almost 6 years collaborative design and supporting technical work by the ITER Joint Central Team and Home Teams under the terms of the ITER EDA Agreement

  4. 78 FR 16447 - Rehabilitation Continuing Education Program (RCEP) for the Technical Assistance and Continuing...

    Science.gov (United States)

    2013-03-15

    ... (RCEP) for the Technical Assistance and Continuing Education Centers (TACE Centers); Proposed Extension... (RCEP) for the Technical Assistance and Continuing Education Centers (TACE Centers), the Secretary... with disabilities through enhanced technical assistance (TA) and continuing education (CE) for State...

  5. Exploratory Shaft Facility design basis study report

    International Nuclear Information System (INIS)

    Langstaff, A.L.

    1987-01-01

    The Design Basis Study is a scoping/sizing study that evaluated the items concerning the Exploratory Shaft Facility Design including design basis values for water and methane inflow; flexibility of the design to support potential changes in program direction; cost and schedule impacts that could result if the design were changed to comply with gassy mine regulations; and cost, schedule, advantages and disadvantages of a larger second shaft. Recommendations are proposed concerning water and methane inflow values, facility layout, second shaft size, ventilation, and gassy mine requirements. 75 refs., 3 figs., 7 tabs

  6. Do technical skills correlate with non-technical skills in crisis resource management: a simulation study.

    Science.gov (United States)

    Riem, N; Boet, S; Bould, M D; Tavares, W; Naik, V N

    2012-11-01

    Both technical skills (TS) and non-technical skills (NTS) are key to ensuring patient safety in acute care practice and effective crisis management. These skills are often taught and assessed separately. We hypothesized that TS and NTS are not independent of each other, and we aimed to evaluate the relationship between TS and NTS during a simulated intraoperative crisis scenario. This study was a retrospective analysis of performances from a previously published work. After institutional ethics approval, 50 anaesthesiology residents managed a simulated crisis scenario of an intraoperative cardiac arrest secondary to a malignant arrhythmia. We used a modified Delphi approach to design a TS checklist, specific for the management of a malignant arrhythmia requiring defibrillation. All scenarios were recorded. Each performance was analysed by four independent experts. For each performance, two experts independently rated the technical performance using the TS checklist, and two other experts independently rated NTS using the Anaesthetists' Non-Technical Skills score. TS and NTS were significantly correlated to each other (r=0.45, P<0.05). During a simulated 5 min resuscitation requiring crisis resource management, our results indicate that TS and NTS are related to one another. This research provides the basis for future studies evaluating the nature of this relationship, the influence of NTS training on the performance of TS, and to determine whether NTS are generic and transferrable between crises that require different TS.

  7. Feasibility study and technical proposal for long-term observations of bedrock stability with gps

    International Nuclear Information System (INIS)

    Ruizhi Chen; Kakkuri, J.

    1994-01-01

    In order to study the regional crustal deformation pattern in the territory of Finland, the Finnish Geodetic Institute is establishing the Finnish Permanent GPS Network, which is part of the Fennoscandian Permanent GPS Network. The Finnish GPS Network consists of a 12 stations located in different geological structures. The operation procedure of the network is described in the report. Feasibility study for monitoring the bedrock stability at local scale was performed. The study was carried out on the basis of an experiment on a baseline of 1041 metres. Twelve artificial movements ranging from 1 mm to 22 mm were generated with a precision-manufactured screw drive (with an accuracy of better than +-0.05 mm). The artificial movements were then detected with the GPS measurements. A preliminary analysis of the GPS data shows that the maximum difference between the GPS detected movements and the artificial movements is 0.9 mm with a standard deviation of +-0.46 mm. The observation time for reaching such accuracy is about 55 minutes. Three GPS networks were preliminarily designed for the radioactive waste disposal investigation sites of Olkiluoto, Kivetty and Romuvaara. Detailed research plan for achieving the best possible result from GPS measurements was proposed. (58 refs., 25 figs., 1 tab.)

  8. HFBR: Review of the technical specifications against the FSAR

    International Nuclear Information System (INIS)

    Rao, D.V.; Boss, S.B.; Claiborne, E.R.; Darby, J.L.; Clark, R.A.

    1990-01-01

    The purpose of this review is to determine the adequacy of the High Flux Beam Reactor (HFBR) Technical Specifications for 40 MW operation by comparison with the HFBR Final Safety Analysis Report, particularly the accident analyses chapter. Specifically, the Technical Specifications were compared against the Design Basis Accident (DBA) Analyses presented in the Addendum to the HFBR FSAR for 60 MW Operation. The 60 MW DBA analyses was used since it is more current and complete than the analyses presented in the original FSAR which is considered obsolete. A listing of the required systems and equipment was made for each of the accidents analyzed. Additionally, the Technical Specification instrument setpoints were compared to the DBA analyses parametric values. Also included in this review was a comparison of the Technical Specification Bases against the FSAR and the identification of any differences. The HFBR Operations Procedures Manual (OPM) was also reviewed for any inconsistencies between the FSAR or the Technical Specifications. Upon completion of this review it was determined that the Technical Specifications are well written and the items commented on should not delay the low power restart (40 MW). Additionally, the OPM is also well written and does not require further modification before restart

  9. Subsurface Fire Hazards Technical Report

    International Nuclear Information System (INIS)

    Logan, R.C.

    1999-01-01

    The results from this report are preliminary and cannot be used as input into documents supporting procurement, fabrication, or construction. This technical report identifies fire hazards and proposes their mitigation for the subsurface repository fire protection system. The proposed mitigation establishes the minimum level of fire protection to meet NRC regulations, DOE fire protection orders, that ensure fire containment, adequate life safety provisions, and minimize property loss. Equipment requiring automatic fire suppression systems is identified. The subsurface fire hazards that are identified can be adequately mitigated

  10. Technical Stability and Biological Variability in MicroRNAs from Dried Blood Spots: A Lung Cancer Therapy-Monitoring Showcase.

    Science.gov (United States)

    Kahraman, Mustafa; Laufer, Thomas; Backes, Christina; Schrörs, Hannah; Fehlmann, Tobias; Ludwig, Nicole; Kohlhaas, Jochen; Meese, Eckart; Wehler, Thomas; Bals, Robert; Keller, Andreas

    2017-09-01

    Different work flows have been proposed to use miRNAs as blood-borne biomarkers. In particular, the method used for collecting blood from patients can considerably influence the diagnostic results. We explored whether dried blood spots (DBSs) facilitate stable miRNA measurements and compared its technical stability with biological variability. First, we tested the stability of DBS samples by generating from 1 person 18 whole-genome-wide miRNA profiles of DBS samples that were exposed to different temperature and humidity conditions. Second, we investigated technical reproducibility by performing 7 replicates of DBS again from 1 person. Third, we investigated DBS samples from 53 patients with lung cancer undergoing different therapies. Across these 3 stages, 108 genome-wide miRNA profiles from DBS were generated and evaluated biostatistically. In the stability analysis, we observed that temperature and humidity had an overall limited influence on the miRNomes (average correlation between the different conditions of 0.993). Usage of a silica gel slightly diminished DBS' technical reproducibility. The 7 technical replicates had an average correlation of 0.996. The correlation with whole-blood PAXGene miRNomes of the same individual was remarkable (correlation of 0.88). Finally, evaluation of the samples from the 53 patients with lung cancer exposed to different therapies showed that the biological variations exceeded the technical variability significantly ( P work flow for profiling of whole miRNomes on the basis of samples collected from DBS. Biological variations exceeded technical variations significantly. DBS-based miRNA profiles will potentially further the translational character of miRNA biomarker studies. © 2017 American Association for Clinical Chemistry.

  11. Point Set Denoising Using Bootstrap-Based Radial Basis Function.

    Directory of Open Access Journals (Sweden)

    Khang Jie Liew

    Full Text Available This paper examines the application of a bootstrap test error estimation of radial basis functions, specifically thin-plate spline fitting, in surface smoothing. The presence of noisy data is a common issue of the point set model that is generated from 3D scanning devices, and hence, point set denoising is one of the main concerns in point set modelling. Bootstrap test error estimation, which is applied when searching for the smoothing parameters of radial basis functions, is revisited. The main contribution of this paper is a smoothing algorithm that relies on a bootstrap-based radial basis function. The proposed method incorporates a k-nearest neighbour search and then projects the point set to the approximated thin-plate spline surface. Therefore, the denoising process is achieved, and the features are well preserved. A comparison of the proposed method with other smoothing methods is also carried out in this study.

  12. Integral Monitored Retrievable Storage (MRS) Facility conceptual basis for design

    International Nuclear Information System (INIS)

    1985-10-01

    The purpose of the Conceptual Basis for Design is to provide a control document that establishes the basis for executing the conceptual design of the Integral Monitored Retrievable Storage (MRS) Facility. This conceptual design shall provide the basis for preparation of a proposal to Congress by the Department of Energy (DOE) for construction of one or more MRS Facilities for storage of spent nuclear fuel, high-level radioactive waste, and transuranic (TRU) waste. 4 figs., 25 tabs

  13. Assessment of the technical viability of reactor options for plutonium disposition

    International Nuclear Information System (INIS)

    Primm, R.T. III.

    1996-01-01

    Various reactor concepts for the disposition of surplus Pu have been proposed by reactor vendors; not all have attained the same level of technical viability. Studies were performed to differentiate between reactor concepts by devising a quantitative index for technical viability. For a quantitative assessment, three issues required resolution: the definition of a technical maturity scale, the treatment of ''subjective'' factors which cannot be easily represented in a quantitative format, and the protocol for producing a single technical viability figure-of-merit for each alternative. Alternatives involving the use of foreign facilities were found to be the most technically viable

  14. Intrinsic stability of technical superconductors

    International Nuclear Information System (INIS)

    Veringa, H.J.

    1981-10-01

    For the operation of technical superconductors under high current density conditions, the superconducting wires composing high current cables should be intrinsically stabilized. In this report the various important stability criteria are derived and investigated on their validity. An experimental set up is made to check the occurrence of magnetic instabilities if the different applicable criteria are violated. It is found that the observed instabilities can be predicted on the basis of the model given in this report. Production of high current cables based upon composites made by the ECN technique seems to be possible. (Auth.)

  15. 10 CFR 72.94 - Design basis external man-induced events.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Design basis external man-induced events. 72.94 Section 72... WASTE Siting Evaluation Factors § 72.94 Design basis external man-induced events. (a) The region must be examined for both past and present man-made facilities and activities that might endanger the proposed...

  16. 40 CFR 227.17 - Basis for determination.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Basis for determination. 227.17 Section 227.17 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) OCEAN DUMPING... living marine resources. (b) For all proposed dumping, full consideration will be given to such...

  17. Current technical issues in international safeguards

    International Nuclear Information System (INIS)

    Bennett, C.A.

    1977-01-01

    Safeguards systems, and the associated need for technical and systems development, reflect changing conditions and concerns associated with the nuclear fuel cycle and the safety and security of nuclear materials and facilities. In particular, the implementation of international safeguards has led to the recognition of certain technical issues, both old and new, which are in need of resolution. These are: 1. The grading of nuclear materials and facilities with respect to their relative safeguards significance. 2. The extension and upgrading of safeguards techniques to maintain adequate protection in view of constantly increasing amounts of material to be safeguarded. 3. The balance between safeguards mechanisms based on physical protection and material accounting, and the role of surveillance and containment in each case. 4. The role of information systems as a basis for both analytical feedback and the determination of the factors affecting system effectiveness and their interrelationship. 5. A determination of the degree to which the overall technical effectiveness of international inspection activities can be quantified. Each of these technical issues must be considered in light of the specific objectives of international safeguards, which differ from domestic safeguards in terms of the level of the threat, the safeguards mechanisms available, and the diversion strategies assumed. Their resolution in this international context is essential if the effectiveness and viability of international safeguards are to be maintained

  18. Independent Technical Review Of The Focused Feasibility Study And Proposed Plan For Designated Solid Waste Management Units Contributing To The Southwest Groundwater Plume At The Paducah Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Looney, B.; Eddy-Dilek, C.; Amidon, M.; Rossabi, J.; Stewart, L.

    2011-01-01

    The U. S. Department of Energy (DOE) is currently developing a Proposed Plan (PP) for remediation of designated sources of chlorinated solvents that contribute contamination to the Southwest (SW) Groundwater Plume at the Paducah Gaseous Diffusion Plant (PGDP), in Paducah, KY. The principal contaminants in the SW Plume are trichloroethene (TCE) and other volatile organic compounds (VOCs); these industrial solvents were used and disposed in various facilities and locations at PGDP. In the SW plume area, residual TCE sources are primarily in the fine-grained sediments of the Upper Continental Recharge System (UCRS), a partially saturated zone that delivers contaminants downward into the coarse-grained Regional Gravel Aquifer (RGA). The RGA serves as the significant lateral groundwater transport pathway for the plume. In the SW Plume area, the four main contributing TCE source units are: (1) Solid Waste Management Unit (SWMU) 1 / Oil Landfarm; (2) C-720 Building TCE Northeast Spill Site (SWMU 211A); (3) C-720 Building TCE Southeast Spill Site (SWMU 211B); and (4) C-747 Contaminated Burial Yard (SWMU 4). The PP presents the Preferred Alternatives for remediation of VOCs in the UCRS at the Oil Landfarm and the C-720 Building spill sites. The basis for the PP is documented in a Focused Feasibility Study (FFS) (DOE, 2011) and a Site Investigation Report (SI) (DOE, 2007). The SW plume is currently within the boundaries of PGDP (i.e., does not extend off-site). Nonetheless, reasonable mitigation of the multiple contaminant sources contributing to the SW plume is one of the necessary components identified in the PGDP End State Vision (DOE, 2005). Because of the importance of the proposed actions DOE assembled an Independent Technical Review (ITR) team to provide input and assistance in finalizing the PP.

  19. INDEPENDENT TECHNICAL REVIEW OF THE FOCUSED FEASIBILITY STUDY AND PROPOSED PLAN FOR DESIGNATED SOLID WASTE MANAGEMENT UNITS CONTRIBUTING TO THE SOUTHWEST GROUNDWATER PLUME AT THE PADUCAH GASEOUS DIFFUSION PLANT

    Energy Technology Data Exchange (ETDEWEB)

    Looney, B.; Eddy-Dilek, C.; Amidon, M.; Rossabi, J.; Stewart, L.

    2011-05-31

    The U. S. Department of Energy (DOE) is currently developing a Proposed Plan (PP) for remediation of designated sources of chlorinated solvents that contribute contamination to the Southwest (SW) Groundwater Plume at the Paducah Gaseous Diffusion Plant (PGDP), in Paducah, KY. The principal contaminants in the SW Plume are trichloroethene (TCE) and other volatile organic compounds (VOCs); these industrial solvents were used and disposed in various facilities and locations at PGDP. In the SW plume area, residual TCE sources are primarily in the fine-grained sediments of the Upper Continental Recharge System (UCRS), a partially saturated zone that delivers contaminants downward into the coarse-grained Regional Gravel Aquifer (RGA). The RGA serves as the significant lateral groundwater transport pathway for the plume. In the SW Plume area, the four main contributing TCE source units are: (1) Solid Waste Management Unit (SWMU) 1 / Oil Landfarm; (2) C-720 Building TCE Northeast Spill Site (SWMU 211A); (3) C-720 Building TCE Southeast Spill Site (SWMU 211B); and (4) C-747 Contaminated Burial Yard (SWMU 4). The PP presents the Preferred Alternatives for remediation of VOCs in the UCRS at the Oil Landfarm and the C-720 Building spill sites. The basis for the PP is documented in a Focused Feasibility Study (FFS) (DOE, 2011) and a Site Investigation Report (SI) (DOE, 2007). The SW plume is currently within the boundaries of PGDP (i.e., does not extend off-site). Nonetheless, reasonable mitigation of the multiple contaminant sources contributing to the SW plume is one of the necessary components identified in the PGDP End State Vision (DOE, 2005). Because of the importance of the proposed actions DOE assembled an Independent Technical Review (ITR) team to provide input and assistance in finalizing the PP.

  20. Single-particle basis and translational invariance in microscopic nuclear calculations

    International Nuclear Information System (INIS)

    Ehfros, V.D.

    1977-01-01

    The approach to the few-body problem is considered which allows to use the simple single-particle basis without violation of the translation invariance. A method is proposed to solve the nuclear reaction problems in the single-particle basis. The method satisfies the Pauli principle and the translation invariance. Calculation of the matrix elements of operators is treated

  1. Functional imaging in oncology. Biophysical basis and technical approaches. Vol. 1

    Energy Technology Data Exchange (ETDEWEB)

    Luna, Antonio [Health Time Group, Jaen (Spain); University Hospitals, Case Western Reserve Univ., Cleveland, OH (United States). Dept. of Radiology; Vilanova, Joan C. [Clinica Girona - Hospital Sta. Caterina, Girona (Spain); Hygino da Cruz, L. Celso Jr. [CDPI and IRM, Rio de Janeiro, RJ (Brazil). Dept. of Radiology; Rossi, Santiago E. (ed.) [Centro de Diagnostico, Buenos Aires (Argentina)

    2014-07-01

    Easy-to-read manual on new functional imaging techniques in oncology. Explains current clinical applications and outlines future avenues. Includes numerous high-quality illustrations to highlight the major teaching points. In the new era of functional and molecular imaging, both currently available imaging biomarkers and biomarkers under development are expected to lead to major changes in the management of oncological patients. This well-illustrated two-volume book is a practical manual on the various imaging techniques capable of delivering functional information on cancer, including preclinical and clinical imaging techniques, based on US, CT, MRI, PET and hybrid modalities. This first volume explains the biophysical basis for these functional imaging techniques and describes the techniques themselves. Detailed information is provided on the imaging of cancer hallmarks, including angiogenesis, tumor metabolism, and hypoxia. The techniques and their roles are then discussed individually, covering the full range of modalities in clinical use as well as new molecular and functional techniques. The value of a multiparametric approach is also carefully considered.

  2. Functional imaging in oncology. Biophysical basis and technical approaches. Vol. 1

    International Nuclear Information System (INIS)

    Luna, Antonio; Hygino da Cruz, L. Celso Jr.

    2014-01-01

    Easy-to-read manual on new functional imaging techniques in oncology. Explains current clinical applications and outlines future avenues. Includes numerous high-quality illustrations to highlight the major teaching points. In the new era of functional and molecular imaging, both currently available imaging biomarkers and biomarkers under development are expected to lead to major changes in the management of oncological patients. This well-illustrated two-volume book is a practical manual on the various imaging techniques capable of delivering functional information on cancer, including preclinical and clinical imaging techniques, based on US, CT, MRI, PET and hybrid modalities. This first volume explains the biophysical basis for these functional imaging techniques and describes the techniques themselves. Detailed information is provided on the imaging of cancer hallmarks, including angiogenesis, tumor metabolism, and hypoxia. The techniques and their roles are then discussed individually, covering the full range of modalities in clinical use as well as new molecular and functional techniques. The value of a multiparametric approach is also carefully considered.

  3. Analysis and evaluation of the ASTEC model basis on plant simulations. 2. Technical report

    International Nuclear Information System (INIS)

    Koppers, Vera; Braehler, Thimo; Koch, Marco K.

    2015-06-01

    The present report is the 2 nd Technical Report of the research project ''Analysis and Evaluation of the ASTEC model basis'' funded by the Federal Ministry for Economic Affairs and Energy (BMWi 1501433) and conducted at the Reactor Simulation and Safety Group, Chair of Energy Systems and Energy Economics (LEE) at Ruhr-Universitaet Bochum. Within this report, the quality of a nuclear power plant simulation with ASTEC is investigated. Different parameters are varied to analyze the simulation stability within the dataset, which describes a generic German Konvoi power plant and is deposit in the program set of ASTEC. Firstly, plant specifications in the data set are checked for plausibility. In addition, the compliance of the data set with the nodalization rules is verified. After that, the stationary phase, in which no accident is calculated, is analyzed and parametric studies are performed in the transient phase, focusing on the primary and secondary circuit as well as on the containment behavior. The performed calculations focusing the primary and secondary circuit indicate a high dependency of the simulation results on the user's input in the data set. There are significant deviations between each simulations results, for example in the different calculated point of time of the reactor pressure vessel failure. Already changes in the stationary phase cause a significantly earlier reactor pressure vessel failure compared to the simulation with the original data. Beyond that, the location of the leakage of the reactor pressure vessel lower head varied and therefore cannot be clearly determined, although there have been no changes by the user on the accident course. A reliable indication of the plant behavior under severe accident conditions is therefore difficult using ASTEC. The results of the parametric studies within the Containment show the same significant influence of certain parameter changes on the simulation results. By using the

  4. ETSON proposal on the European operational experience feedback system

    International Nuclear Information System (INIS)

    Maqua, Michael; Bertrand, Remy; Gelder, Pieter de

    2007-01-01

    The new IAEA Safety Fundamentals states regarding the operating experience feedback: The feedback of operating experience from facilities and activities - and, where relevant, from elsewhere - is a key means of enhancing safety. Processes must be put in place for the feedback and analysis of operating experience, including initiating events, accident precursors, near misses, accidents and unauthorized acts, so that lessons may be learned, shared and acted upon. This presentation deals with the proposal of the ETSON (European TSO Network) to optimize the European operating experiences feedback (OEF). It is generally recognized that the efficiency of nuclear safety supervision by public authorities is based on two key requirements: - the existence of a competent authority at national level, benefiting from an appropriate legislative and regulatory basis, from adequate (quantitatively and qualitatively) human resources, particularly for inspection purposes, - the availability of resources devoted to highly specialised independent technical expertise, in order to provide competent authorities with pertinent technical opinions on: -- the safety files provided by operators, for the purpose of licensing corresponding activities, -- the exploitation for regulatory purposes of the operating experience feed back from licensed nuclear installations. There are two worldwide systems intended to learn lessons from experience: the WANO (World Association of Nuclear Operators) system established by the licensees with access restricted to operating organizations and the IRS system jointly operated by IAEA and OECD/NEA accessible to regulators and to some other users nominated by the regulators in their countries. The IRS itself is dedicated to the analysis of safety significant operating events. NEA/CNRA runs a permanent working group on operating experience (WGOE). WGOE provides among other things also generic reports on safety concerns related to operating experiences and

  5. [Evaluation of technical skills in surgical training].

    Science.gov (United States)

    Kasparian, Andres C; Martinez, A C; JoverClos, R J; Chércoles, R A

    2014-01-01

    technical skills acquisition is considered to be of paramount importance in surgical training. Yet, formal assessment of technical skills is the weakest and less developed area. Currently available resources to evaluate technical skills are largely subjective, and lack of validity and reliability. Direct observation, one of the most frequently used methods, is largely biased by interpersonal subjectivity and personality traits. We propose the creation and use of a new procedure-specific tool for objective assessment of technical skills in surgery to evaluate validity and reliability. laparoscopic cholecystectomy and Lichstenstein's inguinal hernia repair were the chosen procedures. Three groups of comparison were defined according to surgical expertise: initial, intermediate, and experts. Surgeries were videorecorded in real time without identification of the patient or the surgeon. Tapes without any posterior edition were assigned to two expert surgeons in a blind and randomized sequence. A newly proposed procedure-specific rating scale was used for evaluation, as well as Reznick's OSATS global scale. Kruskal-Wallis non-parametric test was used to assess validity. p 0.8 granted reliability. from April 2010 to December 2012 36 laparoscopic cholecystectomies and 31 inguinal hernia repairs were recorded. Significant difference was found among groups of comparison for every item (ptechnical skills in surgery is feasible and useful. The tool we proposed showed construct validity and reliability. Video recording of surgical procedures grants durability over time to an ephemeral phenomenon. The objectivity is based on the explicit statements and quantification of every step to be evaluated, and the blind randomization and anonymous treatment of the sample. Sharing the same quality criteria between evaluators is of paramount importance to reach satisfactory results. The process of evaluation always implies a shortened view of the reality.

  6. Technical Work Plan for: Fracture and Lithophysal Studies

    International Nuclear Information System (INIS)

    2006-01-01

    The primary objective of the work scope described in this technical work plan (TWP) is to enhance the descriptions of fracture and lithophysal parameters for the repository host horizon (RHH) over the repository footprint utilizing a predictive model. This work is planned to address U.S. Nuclear Regulatory Commission (NRC) additional information needs (AINs) associated with the Structural Deformation and Seismicity (SDS) Key Technical Issues (KTI) agreement SDS 3.03 (Schlueter 2000 [DIRS 166615]). The results of the planned work are expected to enhance the technical basis and confirm the results of the fracture analyses presented in ''Drift Degradation Analysis'' (BSC 2004 [DIRS 166107], Section 6.1.6). This model is not intended to provide an alternative for the unsaturated zone and saturated zone flow and transport models currently used by the Yucca Mountain Project (YMP). Nor are the outputs of this model intended to address the SDS 3.03 AINs related to the unsaturated zone and saturated zone flow and transport models

  7. Technical Work Plan for: Fracture and Lithophysal Studies

    Energy Technology Data Exchange (ETDEWEB)

    n

    2006-09-11

    The primary objective of the work scope described in this technical work plan (TWP) is to enhance the descriptions of fracture and lithophysal parameters for the repository host horizon (RHH) over the repository footprint utilizing a predictive model. This work is planned to address U.S. Nuclear Regulatory Commission (NRC) additional information needs (AINs) associated with the Structural Deformation and Seismicity (SDS) Key Technical Issues (KTI) agreement SDS 3.03 (Schlueter 2000 [DIRS 166615]). The results of the planned work are expected to enhance the technical basis and confirm the results of the fracture analyses presented in ''Drift Degradation Analysis'' (BSC 2004 [DIRS 166107], Section 6.1.6). This model is not intended to provide an alternative for the unsaturated zone and saturated zone flow and transport models currently used by the Yucca Mountain Project (YMP). Nor are the outputs of this model intended to address the SDS 3.03 AINs related to the unsaturated zone and saturated zone flow and transport models.

  8. Radioactive Waste Management BasisSept 2001

    International Nuclear Information System (INIS)

    Goodwin, S.S.

    2011-01-01

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this RWMB is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  9. A Proposed Conceptual Model of Military Medical Readiness

    National Research Council Canada - National Science Library

    Van Hall, Brian M

    2007-01-01

    .... The basis for the proposed conceptual model builds on common and accepted latent variable and theoretical modeling techniques proposed by healthcare scholars, organizational theorists, mathematical...

  10. CERN Technical Training: available Places in forthcoming Courses

    CERN Multimedia

    2008-01-01

    The following course sessions are scheduled in the framework of the 2008 CERN Technical Training Programme and places are still available. You will find the full updated Technical Training course programme in our web-catalogue (http://cta.cern.ch/cta2/f?p=110:9). OFFICE SOFTWARE Windows Vista\t(Français)\t11.07\t½ journée SOFTWARE AND SYSTEM TECHNOLOGIES Advanced Python-Hands-on\t(English)\t07-09.07\t3 days MECHANICAL DESIGN ANSYS CFX\t(Français)\t28-31.07\t4 jours If you are interested in attending any of the above course sessions, please talk to your supervisor and/or your DTO, and apply electronically via EDH from the course description pages that can be found at: http://cta.cern.ch/cta2/f?p=110:9 under ‘Technical Training’ with the detailed course program. Registration for all courses is always open – sessions for the less-requested courses are organized on a demand-basis only. CERN Technical Training courses are open only to members of the CERN personnel (staff members and fellows; associates, stude...

  11. Representation and Metrics Extraction from Feature Basis: An Object Oriented Approach

    Directory of Open Access Journals (Sweden)

    Fausto Neri da Silva Vanin

    2010-10-01

    Full Text Available This tutorial presents an object oriented approach to data reading and metrics extraction from feature basis. Structural issues about basis are discussed first, then the Object Oriented Programming (OOP is aplied to modeling the main elements in this context. The model implementation is then discussed using C++ as programing language. To validate the proposed model, we apply on some feature basis from the University of Carolina, Irvine Machine Learning Database.

  12. Radiological Effluent Technical Specifications (RETS) implementation: Zion Generating Station Units 1 and 2

    International Nuclear Information System (INIS)

    Serrano, W.; Akers, D.W.; Duce, S.W.; Mandler, J.W.; Simpson, F.B.; Young, T.E.

    1985-06-01

    A review of the Radiological Effluent Technical Specifications (RETS) of the Zion Generating Station Units 1 and 2 was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7 of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by both EG and G and the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual was reviewed and generally found to be consistent with the NRC review guidelines. 35 refs., 2 figs., 1 tab

  13. CLOUD TECHNOLOGIES IN MANAGEMENT AND EDUCATIONAL PROCESS OF UKRAINIAN TECHNICAL UNIVERSITIES

    Directory of Open Access Journals (Sweden)

    Yu. Tryus

    2014-06-01

    Full Text Available This study analyzes opportunities for using cloud technologies in higher education in Ukraine. On the basis of principles of the system approach, it examines the main task of cloud technologies, strategic and tactical goals of cloud computing at the technical universities, as well as problems that arise in their implementation in the educational process. The paper discusses the main trends in the use of cloud technologies in higher technical education, analyzes cloud services used by leading technical universities in Ukraine in management and learning. The typical structure of a Technical University is considered with public, private, and hybrid clouds. The experience of Cherkasy State Technological University in the use of cloud technologies at management and learning is presented. Considerations are particularly given to distance support, mobile, and blending learning, virtualization mechanism to support the students learning at natural, mathematical sciences and engineering through the utilization of individual desktops.

  14. Physico technical conditions of X-ray study on the Russian X-ray diagnostic complexes Medics-R and Telemedics-R

    International Nuclear Information System (INIS)

    Blinov, N.N.; Blinov, N.M. ml

    1999-01-01

    The exposure tables developed on the basis of technical tests and experience in applying new foreign X-ray films in combination with the national calcium-tungstate (TIS) and yttrium (YIS) intensification screens are proposed for the purpose of establishing the image electrical parameters (voltage and the X-ray tube current, exposure time) by certain geometry of the roentgenological study at the Medics-R and Telemedics-R complexes (focus, focal distance, raster-, screen- and film type). The difference in the screens sensitivity by work with the green-sensitive films depending on the anode voltage applied constitutes 2.5 (40-60 kV) up to 1.8 (above 60 kV). Attention is also paid to application of automatic means [ru

  15. The legal basis of natural gas distribution technology. 2. rev. ed.

    International Nuclear Information System (INIS)

    Ambos, G.; Bramkamp, F.B.; Rienen, W. van

    1993-01-01

    The body of legal regulations reaches from general power economy laws to technical safety and environmental laws as well as to laws on construction regulations. The legal regulations laid down by the European Community in regard to the creation of a European single market are of increasing significance. The book wants to give basic information on the relevant legal areas and makes it easier to understand the structure and the systematics of the laws on power supply technology. It does so by differentiating three areas: - Survey of the legal regulatory framework: - Depiction of the basis of energy laws and the questions which arise from the practical work of the energy control board: - Survey of the technical safety and emission control laws in regard to natural-gas distribution by public utilities. (orig.) [de

  16. Hypoplasia of the basi-occipital bone and persistance of the spheno-occipital synchondrosis in a patient with transitory supplementary fissure of the basi-occipital

    International Nuclear Information System (INIS)

    Wackenheim, A.

    1985-01-01

    The author had the opportunity to observe the progressive development of a special form of basilar impression characterized by transitory supplementary fissure of the basi-occipital bone, persistance of the spheno-occipital synchondrosis and hypoplasia of the basi-occipital. He proposes to dissociate the general concept of basilar impression and to consider anatomo-clinical entities such as the example described in this paper. (orig.)

  17. Mark III LOCA-related hydrodynamic load definition. Generic technical activity B-10. Final report

    International Nuclear Information System (INIS)

    Fields, M.B.; Kudrick, J.A.

    1984-08-01

    This report, prepared by the staff of the Office of Nuclear Reactor Regulation and its consultants at the Brookhaven National Laboratory, provides a discussion of LOCA-related suppression pool hydrodynamic loads in boiling water reactor (BWR) facilities with the Mark III pressure-suppression containment design. Its issuance completes NRC Generic Technical Activity B-10, Behavior of BWR Mark III Containment. On the basis of certain large-scale tests conducted between 1973 and 1979, the General Electric Company developed LOCA-related hydrodynamic load definitions for use in the design of the standard Mark III containment. The staff and its consultants have reviewed these load definitions and their bases and conclude that, with a few specified changes, the proposed load definitions provide conservative loading conditions. The staff approved acceptance criteria for LOCA-related hydrodynamic loads are provided in an appendix

  18. TECHNICAL EFFICIENCY AND TECHNICAL LEVEL INDICATORS APPLICATION FOR CIVIL AIRCRAFT FUNCTIONAL PROPERTIES ANALYSIS

    Directory of Open Access Journals (Sweden)

    Vadim V. Efimov

    2018-01-01

    Full Text Available Functional properties characterize the purpose of the aircraft and are described by its flight performance characteristics such as range and cruising speed, payload, runway characteristics, etc. Functional properties also characterize the aircraft efficiency that determines the objective need for their analysis by both aircraft designers and operators in conditions of permanent and systematic efficiency increase necessity. When choosing the aircraft, it is important for the operator to make sure that a selected aircraft type has a high level of functional properties, which will allow it to provide high operational efficiency without obsolescence in the long term. However, when choosing from several aircraft types the operator has to face the fact that some characteristics of considered aircraft variants are better and the others are worse that does not allow to definitely determine what aircraft type has a higher level of functional properties.The possibility of applying technical efficiency indicators and a generalized technical level indicator for analyzing the functional properties of civil aviation aircraft is explored in this article. Fuel, weight and target efficiency values as well as the previously improved technical level indicator value were calculated for the different generations and modifications of Boeing 737 and Airbus A320 families of medium-range airplanes, which was followed by the results interpretation within one airplane generation and when moving historically from one airplane generation to another. According to analysis results it is concluded that it is impossible to define the change of the aircraft functional properties level by the change in the values of separate technical efficiency indicators. Thus, it is proposed to use a generalized technical level indicator that determines the level of aircraft technical perfection for purpose and to use efficiency indicators to analyze the cost of providing this level of

  19. Translating PI observing proposals into ALMA observing scripts

    Science.gov (United States)

    Liszt, Harvey S.

    2014-08-01

    The ALMA telescope is a complex 66-antenna array working in the specialized domain of mm- and sub-mm aperture synthesis imaging. To make ALMA accessible to technically inexperienced but scientifically expert users, the ALMA Observing Tool (OT) has been developed. Using the OT, scientifically oriented user input is formatted as observing proposals that are packaged for peer-review and assessment of technical feasibility. If accepted, the proposal's scientifically oriented inputs are translated by the OT into scheduling blocks, which function as input to observing scripts for the telescope's online control system. Here I describe the processes and practices by which this translation from PI scientific goals to online control input and schedule block execution actually occurs.

  20. Technical Basis for Physical Fidelity of NRC Control Room Training Simulators for Advanced Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Minsk, Brian S.; Branch, Kristi M.; Bates, Edward K.; Mitchell, Mark R.; Gore, Bryan F.; Faris, Drury K.

    2009-10-09

    The objective of this study is to determine how simulator physical fidelity influences the effectiveness of training the regulatory personnel responsible for examination and oversight of operating personnel and inspection of technical systems at nuclear power reactors. It seeks to contribute to the U.S. Nuclear Regulatory Commission’s (NRC’s) understanding of the physical fidelity requirements of training simulators. The goal of the study is to provide an analytic framework, data, and analyses that inform NRC decisions about the physical fidelity requirements of the simulators it will need to train its staff for assignment at advanced reactors. These staff are expected to come from increasingly diverse educational and experiential backgrounds.

  1. Vehicle Systems Analysis Technical Team Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-06-01

    The mission of the Vehicle Systems Analysis Technical Team (VSATT) is to evaluate the performance and interactions of proposed advanced automotive powertrain components and subsystems, in a vehicle systems context, to inform ongoing research and development activities and maximize the potential for fuel efficiency improvements and emission reduction.

  2. Study of the technical specifications for the diesels generator of Juragua NPP

    International Nuclear Information System (INIS)

    Vilaragut Llanes, J.J.

    1996-01-01

    The Technical Specifications of a nuclear power plant specify the limits for plant operation from the safety point of view. These operational safety rules were originally defined on the basis of deterministic analysis and engineering judgement. The Probabilistic safety Assessment, constitutes a tool to analyze of the risk effect in the Technical Specifications Rules, and makes possible a relative comparison of the rules from the risk point of view. This paper studies the technical specifications for the diesels generators of Juragua Nuclear Power Plant and for that was used the probabilistic methodology . It is presented the evaluation of the some parameters as surveillance testing, test interval, repairs time, diesel degradation and AOT

  3. Geologic disposal of radioactive waste: Ethical and technical issues

    International Nuclear Information System (INIS)

    Pigford, T.H.

    1999-01-01

    Ethical goals that future people should be protected and should not have to protect themselves from our radioactive waste are claimed by geologic repository projects. The best test of sufficient protection is to show that the calculated individual doses to future farming families are well below a regulatory limit. That limit should be no greater than what is now adopted to protect the public from operating licensed facilities. Present US calculations show doses, at times well beyond 10,000 years, that exceed current accepted limits by at least three orders of magnitude. Notwithstanding, there is a good chance that the goals can still be achieved by careful technical design of the geologic confinement system. But many in the US now propose ways that would allow greater individual exposures from radionuclides that eventually leak from a geologic repository. Examples include: (a) the 10,000-year cutoff proposed by industry, the US Congress, EPA, and DOE, thus obscuring the later times when higher doses are certain to result; (b) the vicinity-average dose proposed by industry and the US Congress; (c) the probabilistic critical groups proposed by EPRI and by the National Research Council's TYMS committee; (d) proposals to rely on future humans to detect and cleanup excessive amounts of radioactivity that may escape from a repository, and (e) the move to base compliance on calculated doses from well water drawn at considerable distance from Yucca Mountain. Each of these proposals would lead to a far more lenient radiation protection standard than current standards. Each of these proposals is without sufficient scientific basis for its use as a protector of public health. Each of these proposals would violate one or more of the ethical goals. Each is made without adequate discussion and explanation and without explaining how and why it would violate one or more of the ethical goals. What if serious work on alternatives fails to produce conservatively calculated and

  4. Technical aspects of atomic and molecular data processing and exchange. 19. meeting of the A+M Data Centres and ALADDIN Network. Summary report of an IAEA technical meeting

    International Nuclear Information System (INIS)

    Humbert, D.

    2008-05-01

    The proceedings of the IAEA Technical Meeting on Technical Aspects of Atomic and Molecular Data Processing and Exchange (19th Meeting of A+M Data Centres and ALADDIN Network), held on 3-5 October, 2007 in Vienna, Austria, are briefly described. Conclusions and recommendations are presented concerning various proposed projects and their priorities involving A+M data compilation and evaluation and technical aspects of data processing, exchange, and distribution. (author)

  5. A Socio-technical Approach for Transient SME Alliances

    Science.gov (United States)

    Rezgui, Yacine

    The paper discusses technical requirements to promote the adoption of alliance modes of operation by SMEs in the construction sector. These requirements have provided a basis for specifying a set of functionality to support the collaboration and cooperation needs of SMEs. While service-oriented architectures and semantic web services provide the middleware technology to implement the identified functionality, a number of key technical limitations have been identified, including lack of support for the dynamic and non-functional characteristics of SME alliances distributed business processes, lack of execution monitoring functionality to manage running business processes, and lack of support for semantic reasoning to enable SME business process service composition. The paper examines these issues and provides key directions for supporting SME alliances effectively.

  6. A Technical Basis for Employing Facility Ventilation Air Exchange Rates in the Decision to Downpost

    CERN Document Server

    Mantooth, D S

    2001-01-01

    Utilizing the ventilation exchange rate as a basis for the decision to downpost a location within a facility from an airborne radiation area (ARA) based on initial air count(DAC). Not used in the case of a confirmed or suspected contamination release.

  7. Study to paraphrase nuclear technical terms with clear and brief explanations

    International Nuclear Information System (INIS)

    Shobu, Nobuhiro; Takashita, Hirofumi; Horikoshi, Hidehiko; Osawa, Yukiko

    2010-01-01

    This report summarizes the review work to paraphrase nuclear technical terms with clear and brief explanations. Explanation with nuclear technical terms was not very acceptable to the public in a variety of contexts. The objective of this study is not to paraphrase with the expert's ideas but to paraphrase from the public point of view. Japan Atomic Energy Agency (hereafter abbreviated as 'JAEA') has conducted a survey on public attitudes toward fifty-nine nuclear technical terms by using an online questionnaire. Most of them were frequently used in the brochures of Nuclear fuel Cycle Engineering Laboratories of JAEA. The survey clarified the public awareness and comprehension of each term. Thirty-two terms, which was subject to paraphrase on a priority basis, were selected from fifty-nine nuclear technical terms based on our importance rating. At the work to paraphrase thirty-two terms, emphasis was placed more on clearness and briefness than on scientific/technical accuracy. They are reviewed through focus group interviews. This study brought results on recognizable style and thirty-two well-polished paraphrases. (author)

  8. A socio-technical system framework for risk-informed performance-based building regulation

    NARCIS (Netherlands)

    Meacham, B.J.; Straalen, IJ.J. van

    2017-01-01

    Building regulatory systems have been evolving in recent decades, first with a transition to a functional or performance basis, and more recently with the introduction of new societal objectives, including those related to sustainability and climate change resiliency. Various policy and technical

  9. Comprehensive Deployment Method for Technical Characteristics Base on Multi-failure Modes Correlation Analysis

    Science.gov (United States)

    Zheng, W.; Gao, J. M.; Wang, R. X.; Chen, K.; Jiang, Y.

    2017-12-01

    This paper put forward a new method of technical characteristics deployment based on Reliability Function Deployment (RFD) by analysing the advantages and shortages of related research works on mechanical reliability design. The matrix decomposition structure of RFD was used to describe the correlative relation between failure mechanisms, soft failures and hard failures. By considering the correlation of multiple failure modes, the reliability loss of one failure mode to the whole part was defined, and a calculation and analysis model for reliability loss was presented. According to the reliability loss, the reliability index value of the whole part was allocated to each failure mode. On the basis of the deployment of reliability index value, the inverse reliability method was employed to acquire the values of technology characteristics. The feasibility and validity of proposed method were illustrated by a development case of machining centre’s transmission system.

  10. Standard technical specifications: Babcock and Wilcox Plants. Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Babcock ampersand Wilcox Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  11. F/H effluent treatment facility. Technical data summary

    International Nuclear Information System (INIS)

    Ryan, J.P.; Stimson, R.E.

    1984-12-01

    This document provides the technical basis for the design of the facility. Some of the sections are described with options to permit simplification of the process, depending on the effluent quality criteria that the facility will have to meet. Each part of the F/HETF process is reviewed with respect to decontamination and concentration efficiency, operability, additional waste generation, energy efficiency, and compatability with the rest of the process

  12. E-Wallet. A New Technical Approach

    OpenAIRE

    Octavian Dospinescu

    2012-01-01

    The goal of this article is to propose a new technical approach regarding the “e-wallet” concept. Although the “e-wallet” concept has many implementations, we consider that we can improve the present level of knowledge by joining the Near Field Communication technology and the “classic” concepts about money. In order to develop a new architecture, we studied the present level of knowledge in the scientific literature and in the industry and we proposed new elements for e-transfers. Also, we m...

  13. A technical basis for the flux corrected local conditions critical heat flux correlation

    International Nuclear Information System (INIS)

    Luxat, J.C.

    2008-01-01

    The so-called 'flux-corrected' local conditions CHF correlation was developed at Ontario Hydro in the 1980's and was demonstrated to successfully correlate the Onset of Intermittent Dryout (OID) CHF data for 37-element fuel with a downstream-skewed axial heat flux distribution. However, because the heat flux correction factor appeared to be an ad-hoc, albeit a successful modifying factor in the correlation, there was reluctance to accept the correlation more generally. This paper presents a thermalhydraulic basis, derived from two-phase flow considerations, that supports the appropriateness of the heat flux correction as a local effects modifying factor. (author)

  14. ''RESURS'' - The Russian scientific-technical programme for NPP equipment lifetime monitoring, estimation, prediction and management

    International Nuclear Information System (INIS)

    Emelyanov, V.

    1994-01-01

    RESURS programme is described implementation of which will allow to work out regulatory-methodological basis providing legal and technical solution of NPP equipment lifetime management, prediction, monitoring and estimation problems

  15. epsilon : A tool to find a canonical basis of master integrals

    Science.gov (United States)

    Prausa, Mario

    2017-10-01

    In 2013, Henn proposed a special basis for a certain class of master integrals, which are expressible in terms of iterated integrals. In this basis, the master integrals obey a differential equation, where the right hand side is proportional to ɛ in d = 4 - 2 ɛ space-time dimensions. An algorithmic approach to find such a basis was found by Lee. We present the tool epsilon, an efficient implementation of Lee's algorithm based on the Fermat computer algebra system as computational back end.

  16. Endogenous induced technical change and the costs of Kyoto

    International Nuclear Information System (INIS)

    Buonanno, Paolo; Carraro, Carlo; Galeotti, M.

    2001-09-01

    Many predictions and conclusions in the climate change literature have been made and drawn on the basis of theoretical analyses and quantitative models that are either static or that allow for simple forms of changes in technology, often along exogenously given time paths. It is therefore not clear a priori whether those conclusions and policy recipes still hold in the more realistic case of endogenously evolving technologies. In this paper, a quantitative tool with the features of an endogenous growth model is presented, which also accounts for the possibility that technical change can be induced by environmental policy measures. Both the output production technology and the emission-output ratio depend upon the stock of knowledge, which accumulates through R and D activities. R and D is thus an additional policy variable that comes into play along with pollution abatement and capital investment. Two versions of this climate model are studied, one with endogenous technical change but exogenous environmental technical change (i.e. no induced technical change) and the other with both endogenous and induced technical change. Hence, in both models technical change evolves endogenously as far as the production technology is concerned, but endogenous environmental (or induced) technical change is only accounted for in the second version. Finally, a third version of the model also captures technological spillover effects. As an application, the three versions of the model are simulated allowing for trade of pollution permits as specified in the Kyoto Protocol and assessing the implications in terms of cost efficiency, economic growth and R and D efforts of the three different specifications of technical change

  17. Technical approach document

    International Nuclear Information System (INIS)

    1989-12-01

    The Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law 95-604 (PL95-604), grants the Secretary of Energy the authority and responsibility to perform such actions as are necessary to minimize radiation health hazards and other environmental hazards caused by inactive uranium mill sites. This Technical Approach Document (TAD) describes the general technical approaches and design criteria adopted by the US Department of Energy (DOE) in order to implement remedial action plans (RAPS) and final designs that comply with EPA standards. It does not address the technical approaches necessary for aquifer restoration at processing sites; a guidance document, currently in preparation, will describe aquifer restoration concerns and technical protocols. This document is a second revision to the original document issued in May 1986; the revision has been made in response to changes to the groundwater standards of 40 CFR 192, Subparts A--C, proposed by EPA as draft standards. New sections were added to define the design approaches and designs necessary to comply with the groundwater standards. These new sections are in addition to changes made throughout the document to reflect current procedures, especially in cover design, water resources protection, and alternate site selection; only minor revisions were made to some of the sections. Sections 3.0 is a new section defining the approach taken in the design of disposal cells; Section 4.0 has been revised to include design of vegetated covers; Section 8.0 discusses design approaches necessary for compliance with the groundwater standards; and Section 9.0 is a new section dealing with nonradiological hazardous constituents. 203 refs., 18 figs., 26 tabs

  18. Feasibility study and technical proposal for seismic monitoring of tunnel boring machine in Olkiluoto

    Energy Technology Data Exchange (ETDEWEB)

    Saari, J.; Lakio, A. (AF-Consult Ltd, Vantaa (Finland))

    2009-01-15

    In Olkiluoto, Posiva Oy has operated a local seismic network since February 2002. The purpose of the microearthquake measurements at Olkiluoto is to improve understanding of the structure, behaviour and long term stability of the bedrock. The studies include both tectonic and excavation-induced microearthquakes. An additional task of monitoring is related to safeguarding of the ONKALO. The possibility to excavate an illegal access to the ONKALO, have been concerned when the safeguards are discussed. Therefore all recorded explosions in the Olkiluoto area and in the ONKALO are located. If a concentration of explosions is observed, the origin of that is found out. Also a concept of hidden illegal explosions, detonated at the same time as the real excavation blasts, has been examined. According to the experience gained in Olkiluoto, it can be concluded that, as long the seismic network is in operation and the results are analysed by a skilled person, it is practically impossible to do illegal excavation by blasts. In this report a possibility of seismic monitoring of illegal excavation done by tunnel boring machine (TBM) has been investigated. Characteristics of the seismic signal generated by the raise boring machine are described. According to this study, it can be concluded that the generated seismic signal can be detected and the source of the signal can be located. However, this task calls for different kind of monitoring system than that, which is currently used for monitoring microearthquakes and explosions. The presented technical proposal for seismic monitoring of TBM in Olkiluoto is capable to detect and locate TBM coming outside the ONKALO area about two months before it would reach the ONKALO. (orig.)

  19. Feasibility study and technical proposal for seismic monitoring of tunnel boring machine in Olkiluoto

    International Nuclear Information System (INIS)

    Saari, J.; Lakio, A.

    2009-01-01

    In Olkiluoto, Posiva Oy has operated a local seismic network since February 2002. The purpose of the microearthquake measurements at Olkiluoto is to improve understanding of the structure, behaviour and long term stability of the bedrock. The studies include both tectonic and excavation-induced microearthquakes. An additional task of monitoring is related to safeguarding of the ONKALO. The possibility to excavate an illegal access to the ONKALO, have been concerned when the safeguards are discussed. Therefore all recorded explosions in the Olkiluoto area and in the ONKALO are located. If a concentration of explosions is observed, the origin of that is found out. Also a concept of hidden illegal explosions, detonated at the same time as the real excavation blasts, has been examined. According to the experience gained in Olkiluoto, it can be concluded that, as long the seismic network is in operation and the results are analysed by a skilled person, it is practically impossible to do illegal excavation by blasts. In this report a possibility of seismic monitoring of illegal excavation done by tunnel boring machine (TBM) has been investigated. Characteristics of the seismic signal generated by the raise boring machine are described. According to this study, it can be concluded that the generated seismic signal can be detected and the source of the signal can be located. However, this task calls for different kind of monitoring system than that, which is currently used for monitoring microearthquakes and explosions. The presented technical proposal for seismic monitoring of TBM in Olkiluoto is capable to detect and locate TBM coming outside the ONKALO area about two months before it would reach the ONKALO. (orig.)

  20. Technical and economic analysis of hydrogen refuelling

    International Nuclear Information System (INIS)

    Nistor, Silviu; Dave, Saraansh; Fan, Zhong; Sooriyabandara, Mahesh

    2016-01-01

    Highlights: • Technical and economic models of a hydrogen station for vehicles refuelling. • Hydrogen demand from fuel cell electric vehicles modelled stochastically. • Study case based on a UK pilot project. • Operation of the H_2 station using combined energy from wind and power grid is preferred. • Return on investment of 5–10 years is possible for the hydrogen station. - Abstract: This paper focuses on technical and economic analysis of a hydrogen refilling station to provide operational insight through tight coupling of technical models of physical processes and economic models. This allows the dynamic relationships of the system to be captured and analysed to provide short/medium term analytical capability to support system design, planning, and financing. The modelling developed here highlights the need to closely link technical and economic models for technology led projects where technical capability and commercial feasibility are important. The results show that hydrogen fuel can be competitive with petrol on a GBP/KG basis if the return on investment period is over 10 years for PEM electrolysers and 5 for Alkaline electrolysers. We also show that subsidies on capital costs (as reflected by some R&D funding programs) make both PEM and Alkaline technologies cheaper than the equivalent price of petrol, which suggests more emphasis should be put on commercialising R&D funded projects as they have commercial advantages. The paper also shows that a combined wind and grid connected station is preferable so that a higher number of customers are served (i.e. minimum shortage of hydrogen).

  1. Compliance with technical codes becomes obligatory for receipt of feed-in tariff and ancillary services bonus for wind power plants in Germany

    Energy Technology Data Exchange (ETDEWEB)

    Boemer, Jens. C. [Ecofys Germany GmbH, Berlin (Germany). Power Systems and Markets Group; Delft Univ. of Technology (Netherlands). Electrical Power Systems Group; Burges, Karsten [Ecofys Germany GmbH, Berlin (Germany). Power Systems and Markets Group; Kumm, Thomas [VDE, Network Technology and Operation Forum (FNN), Berlin (Germany); Poeller, Markus [DIgSILENT GmbH, Gomaringen (Germany)

    2009-07-01

    The German government aims at a share of electricity generation based on renewable sources (RES-E) of more than 30% by 2020. A major part of this share will be reached by the use of wind power plants (WPP). Therefore, when amending the Renewable Energy Sources Act (EEG) in June 2008, the German government acknowledged the importance of enhanced technical requirements for WPP and announced the development of a respective technical ordinance. For all WPP that go into operation after June 2010, full grid code-compliance becomes a precondition for privileged network access, receipt of feed-in tariff, and extra payments (''ancillary services bonus''). The basis for the technical requirements in the EEG has been laid down by Medium-Voltage (MV)-Directive 2008 and the TransmissionCode 2007. However, the work of the authors - consulting the German government during the development of the technical ordinance - showed that the TransmissionCode 2007 needed careful review and some clarifying specifications were proposed. Eventually, the so called ''Ancillary Services Ordinance'' for wind power plants went into power in July 2009. The interrelation between all three grid codes as well as their specifications and implications for renewable energy sources generators, with special regard to wind power plants, are presented in this paper. (orig.)

  2. METHODOLOGICAL PROPOSAL FOR CONTAMINATED SOIL RECOVERY

    Directory of Open Access Journals (Sweden)

    José Antonio Fabelo Falcón

    2017-01-01

    Full Text Available The contamination of soils, by different substances and / or products is becoming more extensive throughout the world, its determination, minimization and treatment to reach the recovery of them is a necessity, even though it is not granted the level of importance required by the countries concerned. The objective of this work is to propose a methodology for the recovery of soils with a high degree of efficiency and effectiveness in the selection of procedures, regardless of the types of pollutants and land use once recovered. The methodological proposal involves the stages of diagnosis, characterization, selection of the technology and its technical and economic validation at the laboratory and pilot plant level. Subsequently, the technology of the treatment is designed, along with the elaboration of an objective study of each particular case and an essential economic and technical feasibility analysis for the different scales of the development of the technological process.

  3. Quality Concerns in Technical Education in India: A Quantifiable Quality Enabled Model

    Science.gov (United States)

    Gambhir, Victor; Wadhwa, N. C.; Grover, Sandeep

    2016-01-01

    Purpose: The paper aims to discuss current Technical Education scenarios in India. It proposes modelling the factors affecting quality in a technical institute and then applying a suitable technique for assessment, comparison and ranking. Design/methodology/approach: The paper chose graph theoretic approach for quantification of quality-enabled…

  4. Technical and economic guidelines

    International Nuclear Information System (INIS)

    1978-01-01

    This paper proposes technical and economic data and analysis for use in comparing the nuclear systems considered in INFCE. It suggests that a relatively detailed set of characteristics be developed for each system. An alternative to this approach is to concentrate on comparing the characteristic of most interest to INFCE, using a differential comparison to established systems (such as the LWR and HWR) where possible. This would avoid the repetitive analysis of design characteristics that are common to many systems. In making the INFCE comparisons it would still be appropriate that a selected set of information, pertinent to the primary assessment factors under consideration, be developed for each nuclear system. This selected set, much more limited than that set forth in the body of this paper, would include overall descriptions of the reactor and fuel cycle facilities, as well as specific information on resource utilization, flow of nuclear materials, and other areas to be determined by the Working Group. On the other hand, in areas such as costs, nuclear safety, and environmental impacts, it would not be intended that information be developed at a level of detail comparable to that resulting from a detailed design of each system being compared. Instead, the detailed set of data identified in this paper can serve as a check list to assure that all pertinent characteristics are considered, at least on a differential basis; more detailed assessments would be needed only where the differences have substantial impact. Thus this paper asks for more detail than will probably be appropriate for many contributed papers

  5. Proposals to overcome limitations in the EU chemical risk assessment scheme

    DEFF Research Database (Denmark)

    Trapp, Stefan; Schwartz, S.

    2000-01-01

    The noti®cation of new chemicals in the European Union requires a risk assessment. A Technical Guidance Document (TGD) was prepared for assistance. The TGD proposes QSARs, regressions and models from various sources. Each method has its own range of applicability and its own restrictions. Regress......The noti®cation of new chemicals in the European Union requires a risk assessment. A Technical Guidance Document (TGD) was prepared for assistance. The TGD proposes QSARs, regressions and models from various sources. Each method has its own range of applicability and its own restrictions...

  6. Technical evaluation of bids for nuclear power stations

    International Nuclear Information System (INIS)

    Zijl, N.A. van

    1976-01-01

    A bid evaluation method is described which, it is claimed, facilitates a distinct and objective judgement of bids, taking into account the importance of the components, systems, and technical aspects evaluated with regard to the operation and safety of a nuclear power station. The evaluation basically consists of a cost assessment of the scope of supply deviations and a numerical evaluation of the technical design, the latter being a particularly novel feature of the method. The logic applied in both processes is shown. Main evaluation criteria which are applied for most components and systems are given as reliability, function and performance, safety, operation and maintenance, and materials. The judgements given to these evaluation criteria form the basis of the numerical bid evaluation described, which is carried out with the aid of computer programs. (U.K.)

  7. Technical-economic study of electricity storage

    International Nuclear Information System (INIS)

    Harriche, Farah; Souletis, Romain; Carrette, Bertille; Jarry, Gregory; Dereuddre, Antoine

    2013-01-01

    This study first reports an analysis of all services which could be provided by storage to the French electric power system. It proposes an overview of existing technologies, a comparison of their technical characteristics, and a synthesis of technologies which are the most suited to the main services. The author then discusses some regulatory evolutions which are necessary for a good development of the power storage sector in France. An economic scenario is then proposed for the development of storage by 2030. The author indicates expected capacities for each technologies and possible valorisations

  8. TECHNICAL BASIS FOR EVALUATING SURFACE BARRIERS TO PROTECT GROUNDWATER FROM DEEP VADOSE ZONE CONTAMINATION

    International Nuclear Information System (INIS)

    Fayer, J.M.; Freedman, V.L.; Ward, A.L.; Chronister, G.B.

    2010-01-01

    tasks to achieve those outcomes. Full understanding of contaminant behavior in the deep vadose zone is constrained by four key data gaps: limited access; limited data; limited time; and the lack of an accepted predictive capability for determining whether surface barriers can effectively isolate deep vadose zone contaminants. Activities designed to fill these data gaps need to have these outcomes: (1) common evaluation methodology that provides a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination; (2) deep vadose zone data that characterize the lithology, the spatial distribution of moisture and contaminants, the physical, chemical, and biological process that affect the mobility of each contaminant, and the impacts to the contaminants following placement of a surface barrier; (3) subsurface monitoring to provide subsurface characterization of initial conditions and changes that occur during and following remediation activities; and (4) field observations that span years to decades to validate the evaluation methodology. A set of six proposed tasks was identified to provide information needed to address the above outcomes. The proposed tasks are: (1) Evaluation Methodology - Develop common evaluation methodology that will provide a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination. (2) Case Studies - Conduct case studies to demonstrate the applicability ofthe common evaluation methodology and provide templates for subsequent use elsewhere. Three sites expected to have conditions that would yield valuable information and experience pertinent to deep vadose zone contamination were chosen to cover a range of conditions. The sites are BC Cribs and Trenches, U Plant Cribs, and the T Farm Interim Cover. (3) Subsurface Monitoring Technologies - Evaluate minimally invasive

  9. 76 FR 45589 - Notice of Submission of Proposed Information Collection to OMB; Application for Technical...

    Science.gov (United States)

    2011-07-29

    ... grantees will engage providers to supply expertise to shape their resources into effective, coordinated...: Application for technical assistance funds with which CPD grantees will engage providers to supply expertise to shape their resources into effective, coordinated, neighborhood and community development...

  10. Measurable Control System Security through Ideal Driven Technical Metrics

    Energy Technology Data Exchange (ETDEWEB)

    Miles McQueen; Wayne Boyer; Sean McBride; Marie Farrar; Zachary Tudor

    2008-01-01

    The Department of Homeland Security National Cyber Security Division supported development of a small set of security ideals as a framework to establish measurable control systems security. Based on these ideals, a draft set of proposed technical metrics was developed to allow control systems owner-operators to track improvements or degradations in their individual control systems security posture. The technical metrics development effort included review and evaluation of over thirty metrics-related documents. On the bases of complexity, ambiguity, or misleading and distorting effects the metrics identified during the reviews were determined to be weaker than necessary to aid defense against the myriad threats posed by cyber-terrorism to human safety, as well as to economic prosperity. Using the results of our metrics review and the set of security ideals as a starting point for metrics development, we identified thirteen potential technical metrics - with at least one metric supporting each ideal. Two case study applications of the ideals and thirteen metrics to control systems were then performed to establish potential difficulties in applying both the ideals and the metrics. The case studies resulted in no changes to the ideals, and only a few deletions and refinements to the thirteen potential metrics. This led to a final proposed set of ten core technical metrics. To further validate the security ideals, the modifications made to the original thirteen potential metrics, and the final proposed set of ten core metrics, seven separate control systems security assessments performed over the past three years were reviewed for findings and recommended mitigations. These findings and mitigations were then mapped to the security ideals and metrics to assess gaps in their coverage. The mappings indicated that there are no gaps in the security ideals and that the ten core technical metrics provide significant coverage of standard security issues with 87% coverage. Based

  11. Annotated bibliography of structural equation modelling: technical work.

    Science.gov (United States)

    Austin, J T; Wolfle, L M

    1991-05-01

    Researchers must be familiar with a variety of source literature to facilitate the informed use of structural equation modelling. Knowledge can be acquired through the study of an expanding literature found in a diverse set of publishing forums. We propose that structural equation modelling publications can be roughly classified into two groups: (a) technical and (b) substantive applications. Technical materials focus on the procedures rather than substantive conclusions derived from applications. The focus of this article is the former category; included are foundational/major contributions, minor contributions, critical and evaluative reviews, integrations, simulations and computer applications, precursor and historical material, and pedagogical textbooks. After a brief introduction, we annotate 294 articles in the technical category dating back to Sewall Wright (1921).

  12. Analysis Method of Combine Harvesters Technical Level by Functional and Structural Parameters

    Directory of Open Access Journals (Sweden)

    E. V. Zhalnin

    2018-01-01

    Full Text Available The analysis of modern methods of evaluation of the grain harvesters technical level revealed a discrepancy in various criteria: comparative parameters, dimensionless series, the names of firms, the power of the motor, the width of the capture of the harvester, the capacity at the location of the manufacturer plant, advertising brands. (Purpose of research This led to a variety in the name of harvester models, which significantly complicates the assessment of their technical level, complicates the choice of agricultural necessary to him fashion, does not give the perception of the continuity of the change of generations of combines, makes it impossible to analyze trends in their development, does not disclose the technological essence of a model, but - most importantly - combines can not be compared with each other. The figures in the name of the harvester model are not related functionally to the main parameters and performance capabilities. (Materials and methods The close correlation in the form of a linear equation between their design parameters and the capacity of combines was revealed. Verification of this equation in the process of operation of the combine showed that it statistically stable and the estimates are always within the confidence interval with an error of 5-8 percent. It was found that four parameters of the variety of factors, that affect the performance of the harvester per hour net time, having most close correlation with it are: the motor power and the square of the separation concave, straw walkers and sieves for cleaning. (Results and discussion On the basis of the revealed correlation dependence we proposed a new method of assessment of the technical level of combines, which is based on the throughput (kg/s of the wetted material and the size series, indicating the nominal productivity of the combine in centners of grain harvested in 1 hour of basic time. The methodological background and mathematical apparatus

  13. Technical and economic assessment of processes for the production of butanol and acetone

    Science.gov (United States)

    1982-01-01

    This report represents a preliminary technical and economic evaluation of a process which produces mixed solvents (butaol/acetone/ethanol) via fermentation of sugars derived from renewable biomass resources. The objective is to assess the technology of producing butanol/acetone from biomass, and select a viable process capable of serving as a base case model for technical and economic analysis. It is anticipated that the base case process developed herein can then be used as the basis for subsequent studies concerning biomass conversion processes capable of producing a wide range of chemicals. The general criteria utilized in determining the design basis for the process are profit potential and non-renewable energy displacement potential. The feedstock chosen, aspen wood, was selected from a number of potential renewable biomass resources as the most readily available in the United States and for its relatively large potential for producing reducing sugars.

  14. Working group 1B - basis for the standard-liquid pathway

    International Nuclear Information System (INIS)

    Budnitz, R.

    1993-01-01

    This paper presents a summary of the progress made by working group 1B (Basis for the Standard-Liquid Pathway) during the Electric Power Research Institute's EPRI Workshop on the technical basis of EPA HLW Disposal Criteria, March 1993. This group discussed the containment requirements of Environmental Protection Agency (EPA) standard 40 CFR Part 191. This is a major issue when considering the liquid pathway of contamination during the disposal of high-level radioactive wastes. Questions that were raised by this group were (1) What were the problems with Table 1 of 40 CFR Part 191?; (2) What would be fixed with the person-rem alternative that is offered?; and (3) What would be fixed if Table 1 were supplemented with additional columns for other pathways? Other topics that were touched on were the definition of the term open-quotes reasonable expectationsclose quotes and 100,000 year criteria

  15. Proposal for a new Electrical Supply of the Computer Centre for LHC

    CERN Document Server

    Funken, A

    2001-01-01

    To handle the future LHC experiment needs, the Computer Centre will go through a complete change of data processing methods. A total of five Computing farms will be built covering an area of 2,000 m2. The electrical power required for the new Computing farms will increase by five fold to 2 MW. This will have major impact on the technical infrastructures. Focusing on electrical issues, this paper initially explains the principle of the present electrical supply and the major drawbacks. Taking advantage of the opportunity offered by these big changes and conclusions drawn from the recent ST/EL reports, the strategy of electrical supply of building 513 is reviewed, in particular the Diesel backup supply. On this basis and benchmarking with similar Computer Centres, a proposal for a new electrical supply is presented, the objectives being to meet the increase in demand, reliability and safe operation of the Computer Centre.

  16. 77 FR 64564 - Implementation of Regulatory Guide 1.221 on Design-Basis Hurricane and Hurricane Missiles

    Science.gov (United States)

    2012-10-22

    ...-Basis Hurricane and Hurricane Missiles AGENCY: Nuclear Regulatory Commission. ACTION: Proposed interim...-ISG-024, ``Implementation of Regulatory Guide 1.221 on Design-Basis Hurricane and Hurricane Missiles....221, ``Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants.'' DATES: Submit...

  17. Marketing Technology. FasTrak Specialization Integrated Technical and Academic Competency (ITAC). Revised.

    Science.gov (United States)

    Ohio State Dept. of Education, Columbus. Div. of Career-Technical and Adult Education.

    This document presents the Ohio Integrated Technical and Academic Competency profile for marketing technology. The profile is to serve as the basis for curriculum development in Ohio's secondary, adult, and postsecondary programs. The profile includes a comprehensive listing of 580 specialty and foundation key indicators for evaluating mastery of…

  18. Forecasting Resource as a Method of Increasing the Security of Technical Devices

    Science.gov (United States)

    Cherepanov, Anatoly P.; Lyapustin, Pavel K.

    2017-10-01

    The article shows a method of increasing the safe operation of technical devices at various stages of the life cycle according to the proposed classification parameters of the resource by applying the model of resource prediction. The model takes into account the presence of defects, the rate of corrosion and corrosion resistance of the material, the volume of technical diagnosis, the degree of risk in case of failure or damage of technical devices. The article shows the application of the model resource of the technical device from the manufacture to the end of its service life.

  19. Regional dimensions of international scientific and technical cooperation

    Directory of Open Access Journals (Sweden)

    Tetiana Chernytska

    2013-02-01

    Full Text Available The article has examined a phenomenon of international scientific and technical cooperation within individual regions, conditions and factors of its formation. It has been analyzed the evolution, basic essential features, models and trends of development of local innovation alliances, their participation in international scientific and technical cooperation. It has been proposed the priorities of formation of a quality mechanism to improve this form of cooperation in Ukraine and establishment of prerequisites for its expansion with European organizational structures that operate in innovation field (technology parks, technology clusters, innovation centers, etc..

  20. Proposed underground gasification. [United Kingdom

    Energy Technology Data Exchange (ETDEWEB)

    1986-05-01

    An underground coal gasification experiment which could provide the key to recovering the energy in millions of tonnes of otherwise inaccessible undersea coal reserves is proposed by the NCB. The Board's Headquarters Technical Department hope to carry out a field trial in a six foot thick coal seam about 2000 feet beneath a former wartime airfield near the hamlet of Ossington near Newark, Notts, UK. This paper describes briefly the proposed project, which could cost up to 15 million pounds over five years. It has the backing and financial support of the European Economic Community.

  1. Hydrogen Technical Analysis -- Dissemination of Information

    Energy Technology Data Exchange (ETDEWEB)

    George Kervitsky, Jr.

    2006-03-20

    SENTECH is a small energy and environmental consulting firm providing technical, analytical, and communications solutions to technology management issues. The activities proposed by SENTECH focused on gathering and developing communications materials and information, and various dissemination activities to present the benefits of hydrogen energy to a broad audience while at the same time establishing permanent communications channels to enable continued two-way dialog with these audiences in future years. Effective communications and information dissemination is critical to the acceptance of new technology. Hydrogen technologies face the additional challenge of safety preconceptions formed primarily as a result of the crash of the Hindenburg. Effective communications play a key role in all aspects of human interaction, and will help to overcome the perceptual barriers, whether of safety, economics, or benefits. As originally proposed SENTECH identified three distinct information dissemination activities to address three distinct but important audiences; these formed the basis for the task structure used in phases 1 and 2. The tasks were: (1) Print information--Brochures that target the certain segment of the population and will be distributed via relevant technical conferences and traditional distribution channels. (2) Face-to-face meetings--With industries identified to have a stake in hydrogen energy. The three industry audiences are architect/engineering firms, renewable energy firms, and energy companies that have not made a commitment to hydrogen (3) Educational Forums--The final audience is students--the future engineers, technicians, and energy consumers. SENTECH will expand on its previous educational work in this area. The communications activities proposed by SENTECH and completed as a result of this cooperative agreement was designed to compliment the research and development work funded by the DOE by presenting the technical achievements and validations

  2. Technical specifications for mechanical recycling of agricultural plastic waste

    International Nuclear Information System (INIS)

    Briassoulis, D.; Hiskakis, M.; Babou, E.

    2013-01-01

    Highlights: • Technical specifications for agricultural plastic wastes (APWs) recycling proposed. • Specifications are the base for best economical and environmental APW valorisation. • Analysis of APW reveals inherent characteristics and constraints of APW streams. • Thorough survey on mechanical recycling processes and industry as it applies to APW. • Specifications for APW recycling tested, adjusted and verified through pilot trials. - Abstract: Technical specifications appropriate for the recycling of agricultural plastic wastes (APWs), widely accepted by the recycling industry were developed. The specifications establish quality standards to be met by the agricultural plastics producers, users and the agricultural plastic waste management chain. They constitute the base for the best economical and environmental valorisation of the APW. The analysis of the APW streams conducted across Europe in the framework of the European project “LabelAgriWaste” revealed the inherent characteristics of the APW streams and the inherent constraints (technical or economical) of the APW. The APW stream properties related to its recycling potential and measured during pilot trials are presented and a subsequent universally accepted simplified and expanded list of APW recycling technical specifications is proposed and justified. The list includes two sets of specifications, applied to two different quality categories of recyclable APW: one for pellet production process (“Quality I”) and another one for plastic profile production process (“Quality II”). Parameters that are taken into consideration in the specifications include the APW physical characteristics, contamination, composition and degradation. The proposed specifications are focused on polyethylene based APW that represents the vast majority of the APW stream. However, the specifications can be adjusted to cover also APW of different materials (e.g. PP or PVC) that are found in very small quantities

  3. The Physikalisch-Technische Bundesanstalt PTB (physical-technical Federal institution) - research institute and highest technical authority

    International Nuclear Information System (INIS)

    Klages, H.

    1976-01-01

    The PTB Braunschweig and Berlin is a Federal institution for the natural sciences and engineering and the highest technical authority for measurements. It is subject to the directions of the Federal Ministry for Economic Affairs. Its main tasks are representation, maintenance and development of physical units and, in connection with this, research, examinations, and granting permissions for calibration measuring equipment, as well as examinations of building types and permissions. The types of measuring equipment are represented. Many examinations are carried out on a voluntary basis. The advisory activities and the PTB's publications are also reported on. An organizational plan informs of the structure of the PTB. (orig.) [de

  4. Management of efficiency of agricultural production on the basis of ...

    African Journals Online (AJOL)

    Management of efficiency of agricultural production on the basis of margin approach. ... Journal of Fundamental and Applied Sciences ... and systematized to the management of production costs of agricultural products, the proposed definition ...

  5. 32 CFR 206.5 - Final proposal process.

    Science.gov (United States)

    2010-07-01

    ... the basis of “educational value for the dollar.” NSEP is interested in funding proposals in areas... institution to integrate the efforts of the proposed program into the educational process? What plans are...) MISCELLANEOUS NATIONAL SECURITY EDUCATION PROGRAM (NSEP) GRANTS TO INSTITUTIONS OF HIGHER EDUCATION § 206.5...

  6. A proposal for both plasma ion- and electron-temperature diagnostics under simultaneous incidence of particles and x-rays into a semiconductor on the basis of a proposed model for a semiconductor detector response

    International Nuclear Information System (INIS)

    Numakura, T; Cho, T; Kohagura, J; Hirata, M; Minami, R; Yoshida, M; Nakashima, Y; Tamano, T; Yatsu, K; Miyoshi, S

    2003-01-01

    A method is proposed for obtaining radial profiles of plasma temperatures of both plasma ion (T i ) and electron (T e ) simultaneously by the use of a semiconductor detector array. The method is based on our developed particle-response model for a semiconductor detector; in particular, the response theory is constructed for giving the applicability in particle energies ranging down to a kiloelectronvolt. Calculated results from our model are in fairly good agreement with experimental data on the detector response of incident particle beams with energies in the range 100 eV to a few kiloelectronvolts. On the basis of the verification of the proposed model, an idea of the use of a developed semiconductor detector array covered with 'reliably unbreakable' ultrathin SiO 2 'dead-layer filters' having various nanometre-order thicknesses is applied for simultaneous T i and T e analyses by using charge-exchange neutral particles and x-rays from plasmas. Radial profiles of T i and T e are obtained in a single plasma discharge alone, and the data reliability is independently cross-checked by a radial scan of a conventional charge-exchange neutral-particle analyser system as well as a 50-channel microchannel plate x-ray diagnostics system in the GAMMA 10 tandem mirror

  7. Data basis for materials for a new North Sea Agreement 1995 - Collecting and assembling of data basis for assigning priorities to possible Norwegian proposals for new materials in the North Sea Agreement; Datagrunnlag for stoffer til ny Nordsjoeavtale 1995. Innhenting og sammenstilling av datagrunnlag for prioritering av eventuelle norske forslag til nye stoffer i Nordsjoeavtalen

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, H E; Tobiesen, A

    1994-03-12

    In connection with the new North Sea Agreement in 1995, Norway may propose that the addition of certain environmentally hazardous chemicals should be reduced. Norway may propose 5-10 substances or groups of substances. This report lists available information about 28 contaminants as a basis for prioritizing. The relevant data shown are physical and chemical properties, quantities produced, emissions, toxicity, decomposition and bioaccumulation. The report also suggests a rough priority. 36 refs., 3 tabs.

  8. MR-guided dynamic PET reconstruction with the kernel method and spectral temporal basis functions

    Science.gov (United States)

    Novosad, Philip; Reader, Andrew J.

    2016-06-01

    Recent advances in dynamic positron emission tomography (PET) reconstruction have demonstrated that it is possible to achieve markedly improved end-point kinetic parameter maps by incorporating a temporal model of the radiotracer directly into the reconstruction algorithm. In this work we have developed a highly constrained, fully dynamic PET reconstruction algorithm incorporating both spectral analysis temporal basis functions and spatial basis functions derived from the kernel method applied to a co-registered T1-weighted magnetic resonance (MR) image. The dynamic PET image is modelled as a linear combination of spatial and temporal basis functions, and a maximum likelihood estimate for the coefficients can be found using the expectation-maximization (EM) algorithm. Following reconstruction, kinetic fitting using any temporal model of interest can be applied. Based on a BrainWeb T1-weighted MR phantom, we performed a realistic dynamic [18F]FDG simulation study with two noise levels, and investigated the quantitative performance of the proposed reconstruction algorithm, comparing it with reconstructions incorporating either spectral analysis temporal basis functions alone or kernel spatial basis functions alone, as well as with conventional frame-independent reconstruction. Compared to the other reconstruction algorithms, the proposed algorithm achieved superior performance, offering a decrease in spatially averaged pixel-level root-mean-square-error on post-reconstruction kinetic parametric maps in the grey/white matter, as well as in the tumours when they were present on the co-registered MR image. When the tumours were not visible in the MR image, reconstruction with the proposed algorithm performed similarly to reconstruction with spectral temporal basis functions and was superior to both conventional frame-independent reconstruction and frame-independent reconstruction with kernel spatial basis functions. Furthermore, we demonstrate that a joint spectral

  9. An enhanced radial basis function network for short-term electricity price forecasting

    International Nuclear Information System (INIS)

    Lin, Whei-Min; Gow, Hong-Jey; Tsai, Ming-Tang

    2010-01-01

    This paper proposed a price forecasting system for electric market participants to reduce the risk of price volatility. Combining the Radial Basis Function Network (RBFN) and Orthogonal Experimental Design (OED), an Enhanced Radial Basis Function Network (ERBFN) has been proposed for the solving process. The Locational Marginal Price (LMP), system load, transmission flow and temperature of the PJM system were collected and the data clusters were embedded in the Excel Database according to the year, season, workday and weekend. With the OED applied to learning rates in the ERBFN, the forecasting error can be reduced during the training process to improve both accuracy and reliability. This would mean that even the ''spikes'' could be tracked closely. The Back-propagation Neural Network (BPN), Probability Neural Network (PNN), other algorithms, and the proposed ERBFN were all developed and compared to check the performance. Simulation results demonstrated the effectiveness of the proposed ERBFN to provide quality information in a price volatile environment. (author)

  10. Los Alamos National Laboratory Environmental Restoration Project quarterly technical report, April--June 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-18

    This quarterly report describes the technical status of activities in the Los Alamos National Laboratory Environmental Restoration (ER) Project. Each activity is identified by an activity data sheet number, a brief title describing the activity or the technical area where the activity is located, and the name of the project leader. The Hazardous and Solid Waste Amendments (HSWA) portion of the facility operating permit requires the submission of a technical progress report on a quarterly basis. This report, submitted to fulfill the permit`s requirement, summarizes the work performed and the results of sampling and analysis in the ER Project. Suspect waste found include: Radionuclides, high explosives, metals, solvents and organics. The data provided in this report have not been validated. These data are considered ``reviewed data.``

  11. An interrelation of physical and technical readiness as a basis in sport result achievement of 400 m hurdlers

    Directory of Open Access Journals (Sweden)

    Oleg Grebeniuk

    2017-04-01

    Full Text Available Purpose: to establish the relationship of physical and technical preparedness to achieve sports results of 400 m hurdlers at the stage of preliminary base preparation. Material & Methods: study involved the first grade athletes in the amount of 18 people. Methods of research: pedagogical observation, pedagogical experiment, pedagogical testing of physical and technical readiness, telepodometry, methods of mathematical statistics. Results: it found that the major indicators of special physical readiness in the step of preliminary base preparation are: run at 100 m. result which was 96.4% from the model; run at 200 m – 96,0% from the model; run at 400 m – 98,7% from the model; hopping run 100 m – 93,4% and jumps 20 m on one leg – 91,1% % from the model. Conclusion: study of individual elements technique allows us to characterize not only the technique of movements, but also the level of physical qualities.

  12. A Proposal to Build an Education Research and Development Program: The Kamehameha Early Education Project Proposal. Technical Report #3.

    Science.gov (United States)

    Gallimore, Ronald; And Others

    This report summarizes the programmatic features of a proposal for the Kamehameha Early Education Project (KEEP), a program aimed at the development, demonstration, and dissemination of methods for improving the education of Hawaiian and part-Hawaiian children. A brief description of the proposed project goals, structure, organization, and…

  13. 75 FR 27552 - Credit Reforms in Organized Wholesale Electric Markets; Further Notice Concerning Technical...

    Science.gov (United States)

    2010-05-17

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. RM10-13-000] Credit Reforms in Organized Wholesale Electric Markets; Further Notice Concerning Technical Conference May 10, 2010... technical conference related to the Commission's Notice of Proposed Rulemaking on Credit Reforms in...

  14. Physics at the proposed National Underground Science Facility

    International Nuclear Information System (INIS)

    Nieto, M.M.

    1983-01-01

    The scientific, technical, and financial reasons for building a National Underground Science Facility are discussed. After reviewing examples of other underground facilities, we focus on the Los Alamos proposal and the national for its choice of site

  15. Moving Mini-Max - a new indicator for technical analysis

    OpenAIRE

    Z. K. Silagadze

    2008-01-01

    We propose a new indicator for technical analysis. The indicator emphasizes maximums and minimums in price series with inherent smoothing and has a potential to be useful in both mechanical trading rules and chart pattern analysis.

  16. Model's sparse representation based on reduced mixed GMsFE basis methods

    Energy Technology Data Exchange (ETDEWEB)

    Jiang, Lijian, E-mail: ljjiang@hnu.edu.cn [Institute of Mathematics, Hunan University, Changsha 410082 (China); Li, Qiuqi, E-mail: qiuqili@hnu.edu.cn [College of Mathematics and Econometrics, Hunan University, Changsha 410082 (China)

    2017-06-01

    In this paper, we propose a model's sparse representation based on reduced mixed generalized multiscale finite element (GMsFE) basis methods for elliptic PDEs with random inputs. A typical application for the elliptic PDEs is the flow in heterogeneous random porous media. Mixed generalized multiscale finite element method (GMsFEM) is one of the accurate and efficient approaches to solve the flow problem in a coarse grid and obtain the velocity with local mass conservation. When the inputs of the PDEs are parameterized by the random variables, the GMsFE basis functions usually depend on the random parameters. This leads to a large number degree of freedoms for the mixed GMsFEM and substantially impacts on the computation efficiency. In order to overcome the difficulty, we develop reduced mixed GMsFE basis methods such that the multiscale basis functions are independent of the random parameters and span a low-dimensional space. To this end, a greedy algorithm is used to find a set of optimal samples from a training set scattered in the parameter space. Reduced mixed GMsFE basis functions are constructed based on the optimal samples using two optimal sampling strategies: basis-oriented cross-validation and proper orthogonal decomposition. Although the dimension of the space spanned by the reduced mixed GMsFE basis functions is much smaller than the dimension of the original full order model, the online computation still depends on the number of coarse degree of freedoms. To significantly improve the online computation, we integrate the reduced mixed GMsFE basis methods with sparse tensor approximation and obtain a sparse representation for the model's outputs. The sparse representation is very efficient for evaluating the model's outputs for many instances of parameters. To illustrate the efficacy of the proposed methods, we present a few numerical examples for elliptic PDEs with multiscale and random inputs. In particular, a two-phase flow model in

  17. Use of economic statistical method with the analysis of capital expenditure (on the basis of the coal industry)

    Energy Technology Data Exchange (ETDEWEB)

    Zhidchenko, N V

    1979-01-01

    It is shown, that the effective method in analyzing capital expenditure is the use of the economic statistical method. It is a result of the fact that capital expenditure is formed under the influence of a number of factors. On the basis of the coal industry, a model of capital expenditure, in which we found reflection of mining geological, technical, and technical conditions of production, was constructed. A level of capital expenditure is analyzed for various groups of mines and recommendations of a better use of basic industrial capital at coal enterprises is analyzed.

  18. Research as a pedagogical principle in professional technical education of secondary level for the constitution of the social and professional subject

    Directory of Open Access Journals (Sweden)

    Salete Valer

    2017-12-01

    Full Text Available The official documents written in the last decade for Basic Education have reinforced the need for polytechnic and universal education. They propose research as a pedagogical principle, including in the Professional Technical Education of Secondary Level. This article aims to detect which literacy practices and technologies are involved in that principle, in the teaching object of the Languages (mother tongue and additional languages disciplines. The theoretical basis for the analysis of the object under study relied on BRASIL (2013, BRASIL (2015, Demo (2006, 2015, Martins (2009 e Rojo (2005, 2013 among others, and utilized documentary research. The results indicate that the Languages disciplines have a fundamental role concerning literacy teaching involved in the research practice. It was concluded literacy related to investigative practices and the use of digital technologies should be used as pedagogical resources also in other disciplines of the courses, so that the proposed education may be effective in the modality of education discussed here.

  19. Failure Rate Prediction of Active Component Using PM Basis Database

    International Nuclear Information System (INIS)

    Kim, J. S.; Kim, H. W.; Park, J. S.; Jung, S. G.

    2011-01-01

    The safety security and efficient management of NPPs (Nuclear Power Plants) have been increased after the accident of TEPCO's Fukushima nuclear power stations. The needs for the safety and efficiency are becoming more important because about 90 percent of the NPPs all over the world are more than 20 operation years old. The preventive maintenance criteria need to be flexible, considering long-term development of the equipment performance and preventive maintenance. The PMBD (Preventive Maintenance Basis Database) program was widely used for optimization of the preventive maintenance criteria. PMBD program contains all kinds of failure mechanisms for each equipment that may occur in the power plant based on RCM(Reliability-Centered Maintenance) and numerically calculate the variation of reliability and failure rate based on PM interval changes. In this study, propriety evaluation of preventive maintenance task, cycle, technical basis for cost effective preventive maintenance strategy and an appropriate evaluation were suggested by the case application of PMBD for major components in the NPPs

  20. Tools to support important technical decisions during accident conditions

    International Nuclear Information System (INIS)

    Tenschert, J.; Bergiers, C.

    2008-01-01

    To handle design basis and beyond design basis accidents with intact reactor core, Nuclear Power Plants are using Emergency Operating Procedures (EOP) that they may have developed based on the generic Westinghouse Emergency Response Guidelines. Even though the EOPs are very directive, some questions are left to external support, i.e. to a team of persons constituting the so-called Technical Support Center (TSC). The Pressurized Water Reactor Owner Group (PWROG, previously Westinghouse Owner Group, WOG) has developed a TSC manual to support this group in their decision making process. Because of the specific and particular design of the Beznau NPP (KKB) Safety Systems, development of a plant-specific TSC manual required a lot of additions compared to the generic material. This plant-specific TSC manual is a helpful tool for the Site Emergency Director (SED) of the KKB to better evaluate issues and potential concerns arising while executing the EOPs. The majority of considered issues are relevant for beyond design basis accidents and external events. (orig.)

  1. Technical Support for the development of DCS

    International Nuclear Information System (INIS)

    Oh, In Seok; Lee, Cheol Kwon; Kim, Dong Hoon; Kim, Jung Taek; Hwang, In Koo; Park, Jae Chang; Lee, Dong Young; Park, Won Man

    2008-05-01

    The objective of this project is to provide a technical support to Woori Tech Co. in its design and manufacture process of the DCS as a part of KNICS development program to promote the technology self-reliance for non-safety equipment for NPPs(Nuclear Power Plants). We support Woori Tech Co. to develop a DCS which satisfies the requirements for Shinkori 3 and 4 NPPs in the aspects of reliability, applicability and technical competitiveness. As the results of this project the following items were developed and/or implemented; · Design basis and requirements for a DCS system · Design requirements for control communication networks · Architecture of control networks · Design requirements of EWS(Engineering Workstation) · Plan of software verification and validation · Operation display design · Soft control functions · Application development tools of DCS · Analysis and V/V activities on DCS control network protocols · Software verification and validation and documentation guidelines · User manual documents

  2. Conceptual basis for the european sustainability footprint

    OpenAIRE

    PELLETIER NATHANIEL; MAAS Rob; GORALCZYK MALGORZATA; WOLF Marc-Andree

    2012-01-01

    Sustainability is central to the policy objectives of the European Commission (EC), but a widely accepted integrated sustainability assessment framework in support of policy analysis and development is currently lacking. Here, we describe the conceptual basis for the proposed European Sustainability Footprint (ESF) - an integrated sustainability assessment framework for establishing a baseline and tracking trends with respect to the sustainability of European production and consumption. This ...

  3. Technical considerations associated with spent fuel acceptance. Final report

    International Nuclear Information System (INIS)

    Supko, E.M.

    1996-06-01

    This study was initiated by the Electric Power Research Institute (EPRI) to identify technical considerations associated with spent fuel acceptance and implementation of a waste management system that includes the use of transportable storage systems, and to serve as an opening dialogue among Standard Contract Holders and the department of Energy's Office of Civilian Radioactive Waste management (OCRWM) prior to the development of waste acceptance criteria or issuance of a Notice of Proposed Rulemaking by OCRWM to amend the Standard Contract. The original purpose of the Notice of Proposed Rulemaking was to address changes to the Standard Contract to implement a multi-purpose canister based system and to address other issues that were not adequately addressed in the standard contract. Even if DOE does not develop a multi-purpose canister based system for waste acceptance, it will still be necessary to develop waste acceptance criteria in order to accept spent fuel in transportable storage systems that are being deployed for at-reactor storage. In this study, technical issues associated with spent fuel acceptance will be defined and potential options and alternatives for resolution of technical considerations will be explored

  4. "Escola Familia": A Proposal

    Science.gov (United States)

    Carani, George; Carani, José; Strong-Wilson, Teresa

    2014-01-01

    "Alphabetização" (literacy) of young children involves a school exclusively devoted to the early years, parental participation, and teachers specialized in early literacy. This is the basis of José Carani's proposal for an "escola familia" in the municipality of Cambé (Brazil). This "Note from the Field," based on our…

  5. Dynamical basis sets for algebraic variational calculations in quantum-mechanical scattering theory

    Science.gov (United States)

    Sun, Yan; Kouri, Donald J.; Truhlar, Donald G.; Schwenke, David W.

    1990-01-01

    New basis sets are proposed for linear algebraic variational calculations of transition amplitudes in quantum-mechanical scattering problems. These basis sets are hybrids of those that yield the Kohn variational principle (KVP) and those that yield the generalized Newton variational principle (GNVP) when substituted in Schlessinger's stationary expression for the T operator. Trial calculations show that efficiencies almost as great as that of the GNVP and much greater than the KVP can be obtained, even for basis sets with the majority of the members independent of energy.

  6. The Michigan high-level radioactive waste program: Final technical progress report

    International Nuclear Information System (INIS)

    1987-01-01

    This report comprises the state of Michigan's final technical report on the location of a proposed high-level radioactive waste disposal site. Included are a list of Michigan's efforts to review the DOE proposal and a detailed report on the application of geographic information systems analysis techniques to the review process

  7. Predicting the electricity demand of an oil industry region on the basis of a stochastic model

    Energy Technology Data Exchange (ETDEWEB)

    Ragimova, R A; Khaykin, I Ye

    1979-01-01

    A justified decision to accept a particular development design may be made only on the basis of a scientific prediction of the basic technical and economic indicators. Used as the basic factor which impacts on the electricity demand is the total oil production and the flow of the total liquid pumped from the bowels of the earth. The initial information is statistical data about the expenditure of electricity, the oil and liquid production for 8-10 years. The existence is accepted of a direct relation between the resultive and the factorial signs. Based on a normal law of distribution of random errors, reliable probabilities are found for determining the electricity demand of an object with an assigned degree of precision. Calculations through the proposed model in the practical work of the energy services make it possible to expose the degree of quantitative influence of the basic parameters of the development of a deposit on the value of the expenditure of electricity and to justifiably predict the electricity demand for oil production.

  8. Simulated lumbar minimally invasive surgery educational model with didactic and technical components.

    Science.gov (United States)

    Chitale, Rohan; Ghobrial, George M; Lobel, Darlene; Harrop, James

    2013-10-01

    The learning and development of technical skills are paramount for neurosurgical trainees. External influences and a need for maximizing efficiency and proficiency have encouraged advancements in simulator-based learning models. To confirm the importance of establishing an educational curriculum for teaching minimally invasive techniques of pedicle screw placement using a computer-enhanced physical model of percutaneous pedicle screw placement with simultaneous didactic and technical components. A 2-hour educational curriculum was created to educate neurosurgical residents on anatomy, pathophysiology, and technical aspects associated with image-guided pedicle screw placement. Predidactic and postdidactic practical and written scores were analyzed and compared. Scores were calculated for each participant on the basis of the optimal pedicle screw starting point and trajectory for both fluoroscopy and computed tomographic navigation. Eight trainees participated in this module. Average mean scores on the written didactic test improved from 78% to 100%. The technical component scores for fluoroscopic guidance improved from 58.8 to 52.9. Technical score for computed tomography-navigated guidance also improved from 28.3 to 26.6. Didactic and technical quantitative scores with a simulator-based educational curriculum improved objectively measured resident performance. A minimally invasive spine simulation model and curriculum may serve a valuable function in the education of neurosurgical residents and outcomes for patients.

  9. Hyperspherical Coulomb spheroidal basis in the Coulomb three-body problem

    International Nuclear Information System (INIS)

    Abramov, D. I.

    2013-01-01

    A hyperspherical Coulomb spheroidal (HSCS) representation is proposed for the Coulomb three-body problem. This is a new expansion in the set of well-known Coulomb spheroidal functions. The orthogonality of Coulomb spheroidal functions on a constant-hyperradius surface ρ = const rather than on a constant-internuclear-distance surface R = const, as in the traditional Born-Oppenheimer approach, is a distinguishing feature of the proposed approach. Owing to this, the HSCS representation proves to be consistent with the asymptotic conditions for the scattering problem at energies below the threshold for three-body breakup: only a finite number of radial functions do not vanish in the limit of ρ→∞, with the result that the formulation of the scattering problem becomes substantially simpler. In the proposed approach, the HSCS basis functions are considerably simpler than those in the well-known adiabatic hyperspherical representation, which is also consistent with the asymptotic conditions. Specifically, the HSCS basis functions are completely factorized. Therefore, there arise no problems associated with avoided crossings of adiabatic hyperspherical terms.

  10. 7 CFR 1487.6 - What are the criteria for evaluating proposals?

    Science.gov (United States)

    2010-01-01

    ... CREDIT CORPORATION, DEPARTMENT OF AGRICULTURE LOANS, PURCHASES, AND OTHER OPERATIONS TECHNICAL ASSISTANCE... completeness and will evaluate each proposal against the factors described in paragraph (a) of this section... within FAS for decision. FAS may, when appropriate to the subject matter of the proposal, request the...

  11. Cooperation of Russian and EU technical support organizations

    International Nuclear Information System (INIS)

    Kuznetsov, M.V.; Kozlov, Vl.V.; Kapralov, E.Yu.

    2007-01-01

    Since 1992, the fruitful collaboration of the Russian and Western-European technical support organizations (TSOs) is being continued due to the support of the European Commission. There are two main areas of activities. The first one is more of methodological assistance and enhancing RF TSOs capabilities to support Rostekhnadzor decision making process. Experience and knowledge acquired in this area projects increase RF TSOs capabilities regarding a wide spectrum of safety related issues assessment, in particular safety analyses, reactor vessel embrittlement, application of 'leak before break' concept, severe accident and accident management, fire risk evaluation, etc. The second area is focused on licensing related assessments of EC financed on site assistance projects (modernisations). This area projects promote implementation in Russia a licensing process based on a technical dialogue between operator and regulator as well contributes to transfer of Western practice in assessment of NPPs modernization. The improvement of managerial, scientific and technical capabilities of RF TSO experts may be considered as noteworthy and practical result of the TSOs cooperation. The continuation of such modality of RF and EU TSOs cooperation will be a good basis to cope with present and future challenges faced by TSOs in enhancing nuclear safety. (author)

  12. 76 FR 27952 - Small Business Size Standards: Professional, Scientific and Technical Services.

    Science.gov (United States)

    2011-05-13

    ... Administration (SBA or Agency) proposed to increase small business size standards for 35 industries and one sub... SMALL BUSINESS ADMINISTRATION 13 CFR Part 121 RIN 3245-AG07 Small Business Size Standards: Professional, Scientific and Technical Services. AGENCY: U.S. Small Business Administration. ACTION: Proposed...

  13. Final waste classification and waste form technical position papers

    International Nuclear Information System (INIS)

    1983-05-01

    The waste classification technical position paper describes overall procedures acceptable to NRC staff which may be used by licensees to determine the presence and concentrations of the radionuclides listed in section 61.55, and thereby classifying waste for near-surface disposal. This technical position paper also provides guidance on the types of information which should be included in shipment manifests accompanying waste shipments to near-surface disposal facilities. The technical position paper on waste form provides guidance to waste generators on test methods and results acceptable to NRC staff for implementing the 10 CFR Part 61 waste form requirements. It can be used as an acceptable approach for demonstrating compliance with the 10 CFR Part 61 waste structural stability criteria. This technical position paper includes guidance on processing waste into an acceptable stable form, designing acceptable high-integrity containers, packaging cartridge filters, and minimizing radiation effects on organic ion-exchange resins. The guidance in the waste form technical position paper may be used by licensees as the basis for qualifying process control programs to meet the waste form stability requirements, including tests which can be used to demonstrate resistance to degradation arising from the effects of compression, moisture, microbial activity, radiation, and chemical changes. Generic test data (e.g., topical reports prepared by vendors who market solidification technology) may be used for process control program qualification where such generic data is applicable to the particular types of waste generated by a licensee

  14. Brownfields Green Avenue Sites: Technical Memorandum - Conceptual Design for Sustainable Redevelopment

    Science.gov (United States)

    This technical memorandum briefly describes the site and proposed conceptual site plan, indicates conceptual design considerations, specifies recommended green and sustainable features, and offers other recommendations

  15. PRELIMINARY SELECTION OF MGR DESIGN BASIS EVENTS

    International Nuclear Information System (INIS)

    Kappes, J.A.

    1999-01-01

    The purpose of this analysis is to identify the preliminary design basis events (DBEs) for consideration in the design of the Monitored Geologic Repository (MGR). For external events and natural phenomena (e.g., earthquake), the objective is to identify those initiating events that the MGR will be designed to withstand. Design criteria will ensure that radiological release scenarios resulting from these initiating events are beyond design basis (i.e., have a scenario frequency less than once per million years). For internal (i.e., human-induced and random equipment failures) events, the objective is to identify credible event sequences that result in bounding radiological releases. These sequences will be used to establish the design basis criteria for MGR structures, systems, and components (SSCs) design basis criteria in order to prevent or mitigate radiological releases. The safety strategy presented in this analysis for preventing or mitigating DBEs is based on the preclosure safety strategy outlined in ''Strategy to Mitigate Preclosure Offsite Exposure'' (CRWMS M andO 1998f). DBE analysis is necessary to provide feedback and requirements to the design process, and also to demonstrate compliance with proposed 10 CFR 63 (Dyer 1999b) requirements. DBE analysis is also required to identify and classify the SSCs that are important to safety (ITS)

  16. Crew Transportation Technical Management Processes

    Science.gov (United States)

    Mckinnie, John M. (Compiler); Lueders, Kathryn L. (Compiler)

    2013-01-01

    Under the guidance of processes provided by Crew Transportation Plan (CCT-PLN-1100), this document, with its sister documents, International Space Station (ISS) Crew Transportation and Services Requirements Document (CCT-REQ-1130), Crew Transportation Technical Standards and Design Evaluation Criteria (CCT-STD-1140), Crew Transportation Operations Standards (CCT STD-1150), and ISS to Commercial Orbital Transportation Services Interface Requirements Document (SSP 50808), provides the basis for a National Aeronautics and Space Administration (NASA) certification for services to the ISS for the Commercial Provider. When NASA Crew Transportation System (CTS) certification is achieved for ISS transportation, the Commercial Provider will be eligible to provide services to and from the ISS during the services phase.

  17. Performance-oriented asymptotic tracking control of hydraulic systems with radial basis function network disturbance observer

    Directory of Open Access Journals (Sweden)

    Jian Hu

    2016-05-01

    Full Text Available Uncertainties, including parametric uncertainties and uncertain nonlinearities, always exist in positioning servo systems driven by a hydraulic actuator, which would degrade their tracking accuracy. In this article, an integrated control scheme, which combines adaptive robust control together with radial basis function neural network–based disturbance observer, is proposed for high-accuracy motion control of hydraulic systems. Not only parametric uncertainties but also uncertain nonlinearities (i.e. nonlinear friction, external disturbances, and/or unmodeled dynamics are taken into consideration in the proposed controller. The above uncertainties are compensated, respectively, by adaptive control and radial basis function neural network, which are ultimately integrated together by applying feedforward compensation technique, in which the global stabilization of the controller is ensured via a robust feedback path. A new kind of parameter and weight adaptation law is designed on the basis of Lyapunov stability theory. Furthermore, the proposed controller obtains an expected steady performance even if modeling uncertainties exist, and extensive simulation results in various working conditions have proven the high performance of the proposed control scheme.

  18. Estimating the CCSD basis-set limit energy from small basis sets: basis-set extrapolations vs additivity schemes

    Energy Technology Data Exchange (ETDEWEB)

    Spackman, Peter R.; Karton, Amir, E-mail: amir.karton@uwa.edu.au [School of Chemistry and Biochemistry, The University of Western Australia, Perth, WA 6009 (Australia)

    2015-05-15

    Coupled cluster calculations with all single and double excitations (CCSD) converge exceedingly slowly with the size of the one-particle basis set. We assess the performance of a number of approaches for obtaining CCSD correlation energies close to the complete basis-set limit in conjunction with relatively small DZ and TZ basis sets. These include global and system-dependent extrapolations based on the A + B/L{sup α} two-point extrapolation formula, and the well-known additivity approach that uses an MP2-based basis-set-correction term. We show that the basis set convergence rate can change dramatically between different systems(e.g.it is slower for molecules with polar bonds and/or second-row elements). The system-dependent basis-set extrapolation scheme, in which unique basis-set extrapolation exponents for each system are obtained from lower-cost MP2 calculations, significantly accelerates the basis-set convergence relative to the global extrapolations. Nevertheless, we find that the simple MP2-based basis-set additivity scheme outperforms the extrapolation approaches. For example, the following root-mean-squared deviations are obtained for the 140 basis-set limit CCSD atomization energies in the W4-11 database: 9.1 (global extrapolation), 3.7 (system-dependent extrapolation), and 2.4 (additivity scheme) kJ mol{sup –1}. The CCSD energy in these approximations is obtained from basis sets of up to TZ quality and the latter two approaches require additional MP2 calculations with basis sets of up to QZ quality. We also assess the performance of the basis-set extrapolations and additivity schemes for a set of 20 basis-set limit CCSD atomization energies of larger molecules including amino acids, DNA/RNA bases, aromatic compounds, and platonic hydrocarbon cages. We obtain the following RMSDs for the above methods: 10.2 (global extrapolation), 5.7 (system-dependent extrapolation), and 2.9 (additivity scheme) kJ mol{sup –1}.

  19. Estimating the CCSD basis-set limit energy from small basis sets: basis-set extrapolations vs additivity schemes

    International Nuclear Information System (INIS)

    Spackman, Peter R.; Karton, Amir

    2015-01-01

    Coupled cluster calculations with all single and double excitations (CCSD) converge exceedingly slowly with the size of the one-particle basis set. We assess the performance of a number of approaches for obtaining CCSD correlation energies close to the complete basis-set limit in conjunction with relatively small DZ and TZ basis sets. These include global and system-dependent extrapolations based on the A + B/L α two-point extrapolation formula, and the well-known additivity approach that uses an MP2-based basis-set-correction term. We show that the basis set convergence rate can change dramatically between different systems(e.g.it is slower for molecules with polar bonds and/or second-row elements). The system-dependent basis-set extrapolation scheme, in which unique basis-set extrapolation exponents for each system are obtained from lower-cost MP2 calculations, significantly accelerates the basis-set convergence relative to the global extrapolations. Nevertheless, we find that the simple MP2-based basis-set additivity scheme outperforms the extrapolation approaches. For example, the following root-mean-squared deviations are obtained for the 140 basis-set limit CCSD atomization energies in the W4-11 database: 9.1 (global extrapolation), 3.7 (system-dependent extrapolation), and 2.4 (additivity scheme) kJ mol –1 . The CCSD energy in these approximations is obtained from basis sets of up to TZ quality and the latter two approaches require additional MP2 calculations with basis sets of up to QZ quality. We also assess the performance of the basis-set extrapolations and additivity schemes for a set of 20 basis-set limit CCSD atomization energies of larger molecules including amino acids, DNA/RNA bases, aromatic compounds, and platonic hydrocarbon cages. We obtain the following RMSDs for the above methods: 10.2 (global extrapolation), 5.7 (system-dependent extrapolation), and 2.9 (additivity scheme) kJ mol –1

  20. Draft 1992 Resource Program : Technical Report.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1992-01-01

    The 1992 Resource Program will propose actions to meet future loads placed on the Bonneville Power Administration (BPA). It will also discuss and attempt to resolve resource-related policy issues. The Resource Program assesses resource availability and costs, and analyzes resource requirements and alternative ways of meeting those requirements through both conservation and generation resources. These general resource conclusions are then translated to actions for both conservation and generation. The Resource Program recommends budgets for the Office of Energy Resources for Fiscal Years (FY) 1994 and 1995. BPA's Resource Program bears directly on an important BPA responsibility: the obligation under the Northwest Power Act{sup 3} to meet the power requirements of public and private utility and direct service industrial (DSI) customers according to their contractual agreements. BPA's Draft 1992 Resource Program is contained in four documents: (1) 1992 Resource Program Summary; (2) Technical Report; (3) Technical Assumptions Appendix; and, (4) Conservation Implementation Plan. This volume is the Draft 1992 Resource Program Technical Report, a comprehensive document that provides supporting data and analyses for Resource Program recommendations.