WorldWideScience

Sample records for standard design basis

  1. International standard for design basis threat (DBT)

    International Nuclear Information System (INIS)

    Blankenship, J.A.

    2002-01-01

    Full text: A design basis threat (DBT) has been used by the United States since the 1970's as a basis for the design of a facility physical protection system, a basis for the evaluation of the facility physical protection system, and as a standard against which to compare the continuously changing threat. In the last two years substantial effort has been made to develop an international standard for the development of a design basis threat. This approach is the result of a year's worth of discussions between the United States, Germany, United Kingdom, France, and most recently the Russian Federation. The International Atomic Energy Agency (IAEA) supported these discussions and the resulting process, which culminated in a three day workshop on the development of a state DBT. The IAEA was directly involved in this process due to the latest revision of INFCIRC 225, which recommends the use of a DBT in the state physical protection regime. This international standard for the development of a DBT is a significant milestone in the international community. This was necessary because Sandia National Laboratory had developed material for a 'DBT Workshop', and a standard, international approach had to be established before the workshop could be finalized and the instructional material provided to the IAEA for general use. This paper presents a summary of the new international approach to the creation and use of a design basis threat. The paper describes how a DBT is created within a state. This paper also explains the advantages and disadvantages of using this internationalized approach to the DBT. Each state may, of course, choose to modify their use of the DBT to better fit their culture, technical experience of the facilities and authorities, and strengths and weaknesses of their regulatory systems. The internationalized version of the creation and use of the DBT is a major milestone in the international effort of the United States and the IAEA, and this paper is a

  2. Simulant Basis for the Standard High Solids Vessel Design

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, Reid A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Fiskum, Sandra K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Suffield, Sarah R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Daniel, Richard C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gauglitz, Phillip A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wells, Beric E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2017-09-30

    The Waste Treatment and Immobilization Plant (WTP) is working to develop a Standard High Solids Vessel Design (SHSVD) process vessel. To support testing of this new design, WTP engineering staff requested that a Newtonian simulant and a non-Newtonian simulant be developed that would represent the Most Adverse Design Conditions (in development) with respect to mixing performance as specified by WTP. The majority of the simulant requirements are specified in 24590-PTF-RPT-PE-16-001, Rev. 0. The first step in this process is to develop the basis for these simulants. This document describes the basis for the properties of these two simulant types. The simulant recipes that meet this basis will be provided in a subsequent document.

  3. Simulant Basis for the Standard High Solids Vessel Design

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, Reid A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Fiskum, Sandra K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Suffield, Sarah R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Daniel, Richard C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gauglitz, Phillip A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wells, Beric E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-09-01

    This document provides the requirements for a test simulant suitable for demonstrating the mixing requirements for the Single High Solids Vessel Design (SHSVD). This simulant has not been evaluated for other purposes such as gas retention and release or erosion. The objective of this work is to provide an underpinning for the simulant properties based on actual waste characterization.

  4. Equipment qualification NPP in harsh environmental conditions occurring during a design basis accident (DBA), beyond design basis accident (BDBA) in accordance with international standards

    International Nuclear Information System (INIS)

    Aparkin, F.M.; )

    2015-01-01

    The purpose of Equipment Qualification NPP (EQ), safety-related electrical and mechanical equipment is: reducing the probability of equipment failure common cause in connection with the harsh environmental conditions at the design and beyond design basis accidents; to demonstrate that the safety related electrical and mechanical equipment can perform their specific functions related safety in harsh environments in design and beyond design basis accidents. Presentation defines methodological bases of practical EQ in accordance with international standards used for PWR, for demonstration the performance of its safety functions, which subjected to abnormal and accident conditions, including loss of ventilation systems, breaks feed waterline, steam and cooling water main system and seismic events [ru

  5. A basis for standardized seismic design (SSD) for nuclear power plants/critical facilities

    International Nuclear Information System (INIS)

    O'Hara, T.F.; Jacobson, J.P.; Bellini, F.X.

    1991-01-01

    US Nuclear Power Plants (NPP's) are designed, engineered and constructed to stringent standards. Their seismic adequacy is assured by compliance with regulatory standards and demonstrated by both probabilistic risk assessments (PRAs) and seismic margin studies. However, present seismic siting criteria requires improvement. Proposed changes to siting criteria discussed here will provide a predictable licensing process and a stable regulatory environment. Two recent state-of-the-art studies evaluate the seismic design for all eastern US (EUS) NPP'S: a Lawrence Livermore National Labs study (LLNL, 1989) funded by the NRC and similar research by the Electric Power Research Institute (EPRI, 1989) supported by the utilities. Both confirm that Appendix A 10CFR Part 100 has not provided consistent seismic design levels for all sites. Standardized Seismic Design (SSD) uses a probabilistic framework to accommodate alternative deterministic interpretations. It uses seismic hazard input from EPRI or LLNL to produce consistent bases for future seismic design. SSD combines deterministic and probabilistic insights to provide a comprehensive approach for determining a future site's acceptable seismic design basis

  6. Ergonomic Analysis of Tricycle Sidecar Seats: Basis for Proposed Standard Design

    Directory of Open Access Journals (Sweden)

    Michael C. Godoy

    2015-12-01

    Full Text Available Ergonomics (also called human factors engineering is the study of human characteristics for the appropriate design of the living and work environment. It is applied in various industrial areas which includes transportation.Tricycle being one of the most common means of public transportation in Lipa City has various adaptations to suit the culture, and environment. The purpose of this study is to analyze the variability in design of the tricycles in Lipa City, Philippines and propose a standard ergonomically designed tricycle sidecar seat for a greater population. The study was conducted at 26 tricycle terminals with 232 tricycle samples within Lipa City proper including the public market area where 400 commuters were given questionnaires to determine the risk factors associated with the existing tricycle sidecar seat design. Anthropometric measurements of 100 males and 100 female commuters were obtained together with the sidecar dimensions of 232 tricycles to substantiate the observed variations in design. Using the design for the average and design for the extremes, it was found out that most of the tricycles in Lipa City, Philippines have inappropriate inclined seat and lowered sidecar seat pan height which can result to leg and abdominal pain; narrowed seat pan depth which caused pressure on buttocks and legs; narrowed backrest width which can cause upper and low back pain; low backrest height that can pose upper back pain; which can also result to abdominal pain; inclined backrest and limited vertical clearance which can cause upper back pain and neck pain. The researcher proposed a sidecar seat design standard which can be used by the Land Transportation Office, and Land Transportation Franchising and Regulatory Board to provide ease, comfort, and convenience to the passengers.

  7. Design basis 2

    Energy Technology Data Exchange (ETDEWEB)

    Larsen, G.; Soerensen, P. [Risoe National Lab., Roskilde (Denmark)

    1996-09-01

    Design Basis Program 2 (DBP2) is comprehensive fully coupled code which has the capability to operate in the time domain as well as in the frequency domain. The code was developed during the period 1991-93 and succeed Design Basis 1, which is a one-blade model presuming stiff tower, transmission system and hub. The package is designed for use on a personal computer and offers a user-friendly environment based on menu-driven editing and control facilities, and with graphics used extensively for the data presentation. Moreover in-data as well as results are dumped on files in Ascii-format. The input data is organized in a in-data base with a structure that easily allows for arbitrary combinations of defined structural components and load cases. (au)

  8. Designing electronic equipment on the basis of standard mechanical structures using internet re­sour­ces

    Directory of Open Access Journals (Sweden)

    Karlangach A. P.

    2016-12-01

    Full Text Available The author proposes a method to design electronic equipment based on functional-node design method that involves the use of 2D- and 3D- models mechanical structures for electronic equipment as a way to reduce development time and errors when creating design documentation for electronic equipment. At present, most areas of science and technology are computerized, more problems in designing electronic equipment are dealt with using computer-aided design (CAD and Computer-aided manufacturing (CAM to reduce the time required for development and manufacturing of electronic equipment. Development of design documentation also requires a more effective approach, because the less the time for development of the design documentation is, the faster the developed device will go into production. The aim of the study is to develop a method of designing electronic equipment using 2D and 3D models of standard mechanical structures for electronic equipment using Internet resources. Based on the presented methods is an example of designing a device from standard bearing structures. Compared with traditional technology, the method of designing electronic equipment using standard parts has the following advantages: - reduces time and improves quality of development through the use of existing design documentation; - accelerates the implementation and introducing into production processes; - increases unification of design solutions.

  9. Interior design conceptual basis

    CERN Document Server

    Sully, Anthony

    2015-01-01

    Maximizing reader insights into interior design as a conceptual way of thinking, which is about ideas and how they are formulated. The major themes of this book are the seven concepts of planning, circulation, 3D, construction, materials, colour and lighting, which covers the entire spectrum of a designer’s activity. Analysing design concepts from the view of the range of possibilities that the designer can examine and eventually decide by choice and conclusive belief the appropriate course of action to take in forming that particular concept, the formation and implementation of these concepts is taken in this book to aid the designer in his/her professional task of completing a design proposal to the client. The purpose of this book is to prepare designers to focus on each concept independently as much as possible, whilst acknowledging relative connections without unwarranted influences unfairly dictating a conceptual bias, and is about that part of the design process called conceptual analysis. It is assu...

  10. Design Load Basis for Offshore Wind turbines

    DEFF Research Database (Denmark)

    Natarajan, Anand; Hansen, Morten Hartvig; Wang, Shaofeng

    2016-01-01

    DTU Wind Energy is not designing and manufacturing wind turbines and does therefore not need a Design Load Basis (DLB) that is accepted by a certification body. However, to assess the load consequences of innovative features and devices added to existing offshore turbine concepts or new offshore...... turbine concept developed in our research, it is useful to have a full DLB that follows the current design standard and is representative of a general DLB used by the industry. It will set a standard for the offshore wind turbine design load evaluations performed at DTU Wind Energy, which is aligned...

  11. 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

  12. Determination of Design Basis Earthquake ground motion

    International Nuclear Information System (INIS)

    Kato, Muneaki

    1997-01-01

    This paper describes principle of determining of Design Basis Earthquake following the Examination Guide, some examples on actual sites including earthquake sources to be considered, earthquake response spectrum and simulated seismic waves. In sppendix of this paper, furthermore, seismic safety review for N.P.P designed before publication of the Examination Guide was summarized with Check Basis Earthquake. (J.P.N.)

  13. Determination of Design Basis Earthquake ground motion

    Energy Technology Data Exchange (ETDEWEB)

    Kato, Muneaki [Japan Atomic Power Co., Tokyo (Japan)

    1997-03-01

    This paper describes principle of determining of Design Basis Earthquake following the Examination Guide, some examples on actual sites including earthquake sources to be considered, earthquake response spectrum and simulated seismic waves. In sppendix of this paper, furthermore, seismic safety review for N.P.P designed before publication of the Examination Guide was summarized with Check Basis Earthquake. (J.P.N.)

  14. Design Characteristics as Basis for Design Languages

    DEFF Research Database (Denmark)

    Mortensen, Niels Henrik

    1997-01-01

    The application of modern feature based CAD systems has in many companies lead to significant rationalisation of design, particulary the "down stream" acticities such as NC code generation, FEM analysis, mould flow simulation and documentation. The subject of this paper is the "up stream......" activities, i.e.the synthesis of designs. One can now ask: what preconditions have to be fulfilled in order to be able to synthesize designs in an interplay with a computer system, a Designer's Workbench (DWB). One precondition seems to be the existence of one or more design languaes or design grammars, thus...... the designer can "spell" a desig. This paper will propose contents of a design language/design grammar....

  15. Design basis reconstitution for an effective design control program

    International Nuclear Information System (INIS)

    Banerjee, A.K.

    1987-01-01

    Configuration management is a new buzz word in the nuclear power industry. Whatever its definition, everyone agrees that the configuration of a nuclear power plant must be managed effectively. In layman's terms, configuration management means that a plant must be built, operated, and maintained in a manner consistent with its design basis. Thus, control of the design basis is the most important element in any configuration management program. Until recently, the US Nuclear Regulatory Commission's (NRC's) review of design basis focused on the plants that were about to get operating licenses. However, incidents at a few operating nuclear plants and NRC inspections (Safety System Functional Inspection and Safety System Outage Modification Inspection) have indicated weaknesses in older operating plant design basis documentation and design change control programs. Thus, reconstitution of plant design basis has become an important issue. This paper presents the major element of a design basis reconstitution program, which can be an immense undertaking for some of the older operating plants

  16. 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)

  17. PRELIMINARY SELECTION OF MGR DESIGN BASIS EVENTS

    Energy Technology Data Exchange (ETDEWEB)

    J.A. Kappes

    1999-09-16

    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&O 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).

  18. 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

  19. System Design and the Safety Basis

    Energy Technology Data Exchange (ETDEWEB)

    Ellingson, Darrel

    2008-05-06

    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 & decommissioning (D&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.

  20. Standards of Multimedia Graphic Design in Education

    Science.gov (United States)

    Aldalalah, Osamah Ahmad; Ababneh, Ziad Waleed Mohamed

    2015-01-01

    This study aims to determine Standards of Multimedia Graphic Design in Education through the analysis of the theoretical basis and previous studies related to this subject. This study has identified the list of standards of Multimedia, Graphic Design, each of which has a set indicator through which the quality of Multimedia can be evaluated in…

  1. Prototype Hanford Surface Barrier: Design basis document

    International Nuclear Information System (INIS)

    Myers, D.R.; Duranceau, D.A.

    1994-11-01

    The Hanford Site Surface Barrier Development Program (BDP) was organized in 1985 to develop the technology needed to provide a long-term surface barrier capability for the Hanford Site and other arid sites. This document provides the basis of the prototype barrier. Engineers and scientists have momentarily frozen evolving barrier designs and incorporated the latest findings from BDP tasks. The design and construction of the prototype barrier has required that all of the various components of the barrier be brought together into an integrated system. This integration is particularly important because some of the components of the protective barreir have been developed independently of other barreir components. This document serves as the baseline by which future modifications or other barrier designs can be compared. Also, this document contains the minutes of meeting convened during the definitive design process in which critical decisions affecting the prototype barrier's design were made and the construction drawings

  2. 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

  3. 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

  4. Basis and rational for standardization in radiation protection

    International Nuclear Information System (INIS)

    Idris Besar

    1985-01-01

    The historical background for the standardization in radiation protection with special reference to the dose limits recommended by the ICRP which include tolerance dose, maximum permissible dose, and the present recommendation based on the ICRP 26 are presented. The basis and rational for the establishement of these limits are discussed

  5. Design-Load Basis for LANL Structures, Systems, and Components

    Energy Technology Data Exchange (ETDEWEB)

    I. Cuesta

    2004-09-01

    This document supports the recommendations in the Los Alamos National Laboratory (LANL) Engineering Standard Manual (ESM), Chapter 5--Structural providing the basis for the loads, analysis procedures, and codes to be used in the ESM. It also provides the justification for eliminating the loads to be considered in design, and evidence that the design basis loads are appropriate and consistent with the graded approach required by the Department of Energy (DOE) Code of Federal Regulation Nuclear Safety Management, 10, Part 830. This document focuses on (1) the primary and secondary natural phenomena hazards listed in DOE-G-420.1-2, Appendix C, (2) additional loads not related to natural phenomena hazards, and (3) the design loads on structures during construction.

  6. 10 CFR 72.92 - Design basis external natural events.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Design basis external natural events. 72.92 Section 72.92... Evaluation Factors § 72.92 Design basis external natural events. (a) Natural phenomena that may exist or that... must be adopted for evaluating the design basis external natural events based on the characteristics of...

  7. 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)

  8. International Peer Reviews of Design Basis

    International Nuclear Information System (INIS)

    Hughes, Peter

    2013-01-01

    International peer reviews: Design and safety assessment review service: - Review of design requirements; - Review in support of licensing; - Review in support of severe accident management; - Review in support of modifications; - Review in relation to periodic safety, or life extension; - Reviews take place at any time in NPP lifecycle from concept, through design and operations

  9. Design basis for the NRC Operations Center

    Energy Technology Data Exchange (ETDEWEB)

    Lindell, M.K.; Wise, J.A.; Griffin, B.N.; Desrosiers, A.E.; Meitzler, W.D.

    1983-05-01

    This report documents the development of a design for a new NRC Operations Center (NRCOC). The project was conducted in two phases: organizational analysis and facility design. In order to control the amount of traffic, congestion and noise within the facility, it is recommended that information flow in the new NRCOC be accomplished by means of an electronic Status Information Management System. Functional requirements and a conceptual design for this system are described. An idealized architectural design and a detailed design program are presented that provide the appropriate amount of space for operations, equipment and circulation within team areas. The overall layout provides controlled access to the facility and, through the use of a zoning concept, provides each team within the NRCOC the appropriate balance of ready access and privacy determined from the organizational analyses conducted during the initial phase of the project.

  10. Design basis for the NRC Operations Center

    International Nuclear Information System (INIS)

    Lindell, M.K.; Wise, J.A.; Griffin, B.N.; Desrosiers, A.E.; Meitzler, W.D.

    1983-05-01

    This report documents the development of a design for a new NRC Operations Center (NRCOC). The project was conducted in two phases: organizational analysis and facility design. In order to control the amount of traffic, congestion and noise within the facility, it is recommended that information flow in the new NRCOC be accomplished by means of an electronic Status Information Management System. Functional requirements and a conceptual design for this system are described. An idealized architectural design and a detailed design program are presented that provide the appropriate amount of space for operations, equipment and circulation within team areas. The overall layout provides controlled access to the facility and, through the use of a zoning concept, provides each team within the NRCOC the appropriate balance of ready access and privacy determined from the organizational analyses conducted during the initial phase of the project

  11. 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

  12. A risk-informed framework for establishing a beyond design basis safety basis for external hazards

    Energy Technology Data Exchange (ETDEWEB)

    Amico, P. [Hughes Associates, Inc, Baltimore, MD (United States); Anoba, R. [Hughes Associates, Inc, Raleigh, NC (United States); Najafi, B. [Hughes Associates, Inc., Los Gatos, CA (United States)

    2014-07-01

    The events at Fukushima Daiichi taught us that meeting a deterministic design basis requirement for external hazards does not assure that the risk is low. As observed at the plant, the two primary reasons for this are failure cliffs above the design basis event and that combined hazard effects are not considered in design. Because the possible combinations of design basis exceedences and external hazard combinations are very large and complex, an approach focusing only on the most important ones is needed. For this reason, a risk informed approach is the most effective approach, which is discussed in this paper. (author)

  13. Development of standard design licensing system of nuclear power plants

    International Nuclear Information System (INIS)

    Lee, S. K.; Yun, Y. K.; Kim, W. S.; Lee, J. H.; Baek, M.

    2001-01-01

    The design of the APR 1400 (Advanced Power Reactor 1400) is being developed based on the concept of a standard design so that the APR 1400 can be constructed repetitively without major design change. Therefore, in order to avoid repetitive licensing review for the portion of the standard design of the APR 1400, it is necessary to introduced a new licensing system for a standard design. Since the Korean government has acknowledged this necessity, it is now pursuing the legislation of a standard design licensing system. In this technical report, procedural requirements and the format and contents of licensing basis documents considered for the adaption of a standard design licensing system are introduced

  14. Data base pertinent to earthquake design basis

    International Nuclear Information System (INIS)

    Sharma, R.D.

    1988-01-01

    Mitigation of earthquake risk from impending strong earthquakes is possible provided the hazard can be assessed, and translated into appropriate design inputs. This requires defining the seismic risk problem, isolating the risk factors and quantifying risk in terms of physical parameters, which are suitable for application in design. Like all other geological phenomena, past earthquakes hold the key to the understanding of future ones. Quantificatio n of seismic risk at a site calls for investigating the earthquake aspects of the site region and building a data base. The scope of such investigations is il lustrated in Figure 1 and 2. A more detailed definition of the earthquake problem in engineering design is given elsewhere (Sharma, 1987). The present document discusses the earthquake data base, which is required to support a seismic risk evaluation programme in the context of the existing state of the art. (author). 8 tables, 10 figs., 54 refs

  15. Selection of design basis event for modular high temperature gas-cooled reactor

    International Nuclear Information System (INIS)

    Sato, Hiroyuki; Nakagawa, Shigeaki; Ohashi, Hirofumi

    2016-06-01

    Japan Atomic Energy Agency (JAEA) has been investigating safety requirements and basic approach of safety guidelines for modular High Temperature Gas-cooled Reactor (HTGR) aiming to increase internarial contribution for nuclear safety by developing an international HTGR safety standard under International Atomic Energy Agency. In this study, we investigate a deterministic approach to select design basis events utilizing information obtained from probabilistic approach. In addition, selections of design basis events are conducted for commercial HTGR designed by JAEA. As a result, an approach for selecting design basis event considering multiple failures of safety systems is established which has not been considered as design basis in the safety guideline for existing nuclear facility. Furthermore, selection of design basis events for commercial HTGR has completed. This report provides an approach and procedure for selecting design basis events of modular HTGR as well as selected events for the commercial HTGR, GTHTR300. (author)

  16. MAN-004 Design Standards Manual

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, Timothy L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-07-01

    At Sandia National Laboratories in New Mexico (SNL/NM), the design, construction, operation, and maintenance of facilities is guided by industry standards, a graded approach, and the systematic analysis of life cycle benefits received for costs incurred. The design of the physical plant must ensure that the facilities are "fit for use," and provide conditions that effectively, efficiently, and safely support current and future mission needs. In addition, SNL/NM applies sustainable design principles, using an integrated whole-building design approach, from site planning to facility design, construction, and operation to ensure building resource efficiency and the health and productivity of occupants. The safety and health of the workforce and the public, any possible effects on the environment, and compliance with building codes take precedence over project issues, such as performance, cost, and schedule. These design standards generally apply to all disciplines on all SNL/NM projects. Architectural and engineering design must be both functional and cost-effective. Facility design must be tailored to fit its intended function, while emphasizing low-maintenance, energy-efficient, and energy-conscious design. Design facilities that can be maintained easily, with readily accessible equipment areas, low maintenance, and quality systems. To promote an orderly and efficient appearance, architectural features of new facilities must complement and enhance the existing architecture at the site. As an Architectural and Engineering (A/E) professional, you must advise the Project Manager when this approach is prohibitively expensive. You are encouraged to use professional judgment and ingenuity to produce a coordinated interdisciplinary design that is cost-effective, easily contractible or buildable, high-performing, aesthetically pleasing, and compliant with applicable building codes. Close coordination and development of civil, landscape, structural, architectural, fire

  17. Seismic design standardization of nuclear facilities

    International Nuclear Information System (INIS)

    Reddy, G.R.; Vaze, K.K.

    2011-01-01

    Full text: Structures, Systems and Components (SSCs) of Nuclear Facilities have to be designed for normal operating loads such as dead weight, pressure, temperature etc., and accidental loads such as earthquakes, floods, extreme, wind air craft impact, explosions etc. Man made accidents such as aircraft impact, explosions etc., some times may be considered as design basis event and some times taken care by providing administrative controls. This will not be possible in the case of natural events such as earthquakes, flooding, extreme winds etc. Among natural events earthquakes are considered as most devastating and need to be considered as design basis event. It is generally felt design of SSCs for earthquake loads is very time consuming and expensive. Conventional seismic design approaches demands for large number of supports for systems and components. This results in large space occupation and in turn creates difficulties for maintenance and in service inspection of systems and components. In addition, complete exercise of design need to be repeated for plants being located at different sites due to different seismic demands. However, advanced seismic response control methods will help to standardize the seismic design meeting the safety and economy. These methods adopt passive, semi active and active devices, and base isolators to control the seismic response. In nuclear industry, it is advisable to go for passive devices to control the seismic responses. Ideally speaking, these methods will make the designs made for normal loads can also satisfy the seismic demand without calling for change in material, geometry, layout etc. in the SSCs. This paper explain the basic ideas of seismic response control methods, demonstrate the effectiveness of control methods through case studies and eventually give the procedure to be adopted for seismic design standardization of nuclear facilities

  18. Data Requirements and the Basis for Designing Health Information Kiosks.

    Science.gov (United States)

    Afzali, Mina; Ahmadi, Maryam; Mahmoudvand, Zahra

    2017-09-01

    Health kiosks are an innovative and cost-effective solution that organizations can easily implement to help educate people. To determine the data requirements and basis for designing health information kiosks as a new technology to maintain the health of society. By reviewing the literature, a list of information requirements was provided in 4 sections (demographic information, general information, diagnostic information and medical history), and questions related to the objectives, data elements, stakeholders, requirements, infrastructures and the applications of health information kiosks were provided. In order to determine the content validity of the designed set, the opinions of 2 physicians and 2 specialists in medical informatics were obtained. The test-retest method was used to measure its reliability. Data were analyzed using SPSS software. In the proposed model for Iran, 170 data elements in 6 sections were presented for experts' opinion, which ultimately, on 106 elements, a collective agreement was reached. To provide a model of health information kiosk, creating a standard data set is a critical point. According to a survey conducted on the various literature review studies related to the health information kiosk, the most important components of a health information kiosk include six categories; information needs, data elements, applications, stakeholders, requirements and infrastructure of health information kiosks that need to be considered when designing a health information kiosk.

  19. DART - for design basis justification and safety related information management

    International Nuclear Information System (INIS)

    Billington, A.; Blondiaux, P.; Boucau, J.; Cantineau, B.; Doumont, C.; Mared, A.

    2000-01-01

    DART is the acronym for Design Analysis Re-engineering Tool. It embodies a systematic and integrated approach to NPP safety re-assessment and configuration management, that makes use of Reverse Failure Mode and Effect Analysis in conjunction with a state-of-the-art relational database and a standardized data format, to permit long-term management of plant safety related information. The plant design is reviewed in a step-by-step logical fashion by constructing fault trees that identify the link between undesired consequences and their causes. Each failure cause identified in a fault tree is addressed by defining functional requirements, which are in turn addressed by documenting the specific manner in which the plant complies with the requirement. The database can be used to generate up-to-date plant safety related documents, including: SAR, Systems Descriptions, Technical Specifications and plant procedures. The approach is open-minded by nature and therefore is not regulatory driven, however the plant licensing basis will also be reviewed and documented within the same database such that a Regulatory Conformance Program may be integrated with the other safety documentation. This methodology can thus reconstitute the plant design bases in a comprehensive and systematic way, while allowing to uncover weaknesses in design. The original feature of the DART methodology is that it links all the safety related documents together, facilitating the evaluation of the safety impact resulting from any plant modification. Due to its capability to retrieve the basic justifications of the plant design, it is also a useful tool for training the young generation of plant personnel. The DART methodology has been developed for application to units 2, 3 and 4 at Vattenfall's Ringhals site in Sweden. It may be applied to any nuclear power plant or industrial facility where public safety is a concern. (author)

  20. DART - for design basis justification and safety related information management

    International Nuclear Information System (INIS)

    Billington, A.; Blondiaux, B.; Boucau, J.; Cantineau, B.; Mared, A.

    2001-01-01

    DART is the acronym for Design Analysis Re-Engineering Tool. It embodies a systematic and integrated approach to NPP safety re-assessment and configuration management, that makes use of Reverse Failure Mode and Effect Analysis in conjunction with a state-of-the-art relational database and a standardized data format, to permit long-term management of plant safety related information. The plant design is reviewed in a step-by-step logical fashion by constructing fault trees that identify the link between undesired consequences and their causes. Each failure cause identified in a fault tree is addressed by defining functional requirements, which are in turn addressed by documenting the specific manner in which the plant complies with the requirement. The database can then be used to generate up-to-date plant safety related documents, including: SAR, Systems Descriptions, Technical Specifications and plant procedures. The approach is open-minded by nature and therefore is not regulatory driven, however the plant licensing basis will also be reviewed and documented within the same database such that a Regulatory Conformance Program may be integrated with the other safety documentation. This methodology can thus reconstitute the plant design bases in a comprehensive and systematic way, while allowing to uncover weaknesses in design. The original feature of the DART methodology is that it links all the safety related documents together, facilitating the evaluation of the safety impact resulting from any plant modification. Due to its capability to retrieve the basic justifications of the plant design, it is also a useful tool for training the young generation of plant personnel. The DART methodology has been developed for application to units 2, 3 and 4 at Vattenfall's Ringhals site in Sweden. It may be applied to any nuclear power plant or industrial facility where public safety is a concern. (author)

  1. 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

  2. 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.

  3. Design basis document open-item resolution and reportability

    International Nuclear Information System (INIS)

    Gambhir, S.K.; Livingston, B.R.; Purcell, J.J.; Erickson, E.A.

    1989-01-01

    In the process of reconstituting the design bases for older nuclear power plants, information or references may not be available to fully define the design requirements or to document and verify the adequacy of the design. Also, information that is in conflict with other data is identified. The missing and conflicting information must be reconstituted in order to adequately document the design bases of the plant. For these operating facilities, the identification, tracking, and resolution of missing or conflicting information is very important when the reporting requirements stipulated by 10CFR21, 10CFR50.72, and 10CFR50.73 are considered. Additionally, controlled documentation (calculations, drawings, etc.) used to develop the design basis documents may contain conflicting data. In some cases, conflicts between the as-built design and licensing or design basis requirements established in specific commitments to the U.S. Nuclear Regulatory Commission may be identified. Furthermore, concerns regarding the adequacy of safety-related systems or components to perform their required function may be identified that would warrant prompt action by the licensee. The approach discussed in this paper was used by Omaha Public Power District for the ongoing design basis reconstitution effort at the Fort Calhoun nuclear plant

  4. Discussion about design basis flood of site of research reactors by river

    International Nuclear Information System (INIS)

    Rong Feng; Zhao Jianjun; Du Qiaomin; Zhang Lingyan

    2006-01-01

    This paper presents the well-defined standard in relation to design the basis flood of the sites of research reactors by river. It is based on the concept of some relational standards, analysis of hydrological calculation technology and methods, and analysis of accident dangerous degrees of research reactor, as well as in combination with the engineering practices. The flood preventing standard for research reactors with higher power should be the same with that of the nuclear power plants. (authors)

  5. Design basis programs and improvements in plant operation

    International Nuclear Information System (INIS)

    Metcalf, M.F.

    1991-01-01

    Public Service Electric and Gas (PSE and G) Company operates three commercial nuclear power plants in southern New Jersey. The three plants are of different designs and vintages (two pressurized water reactors licensed in 1976 and 1980 and one boiling water reactor licensed in 1986). As the industry recognized the need to develop design basis programs, PSE and G also realized the need after a voluntary 52-day shutdown of one unit because of electrical design basis problems. In its drive to be a premier electric utility, PSE and G has been aggressively active in developing design basis documents (DBDs) with supporting projects and refined uses to obtain the expected value and see the return on investment. Progress on Salem is nearly 75% complete, while Hope Creek is 20% complete. To data, PSE and G has experienced success in the use of DBDs in areas such as development of plant modifications, development of the reliability-centered maintenance program, procedure upgrades, improved document retrieval, resolution of regulatory issues, and training. The paper examines the design basis development process, supporting projects, and expected improvements in plant operations as a result of these efforts

  6. Six Dimension Strategy As A Basis Of Banking Standard Contract

    Directory of Open Access Journals (Sweden)

    Wulanmas Frederik

    2012-01-01

    Full Text Available Indonesia banking based on Article 4 of Act No.10, 1998, aims at supporting the implementation of national development in order to improve equity, economic growth and national stability in the direction of improving people’s welfare. Therefore, to show how important is banking role in supporting the implementation of development, the 6 (six Strategic Dimensions as the foundation of Banking Standards Contract are: (1. Prudent Banking Supervision and Good Corporate Governance (GCG in banking activities, (2. Refunctionalization the principle of Contract Law in Banking Standards Contract, (3. Ethics Value in Business, (4. The Act No. 8, 1999 on Consumer Protection, (5. Enforcement of Human Rights Principles in banking activities, (6. Abuse of Circumstances implementations (Misbruik van Omstandigheden in banking Contract. Based on the 6 (six Strategic Dimension as the foundation of Banking Standard Contract, it will undoubtedly create justice, equity and assurance of the rights and obligations of the parties framed in the contractual and law bonds.

  7. Canister storage building design basis accident analysis documentation

    International Nuclear Information System (INIS)

    KOPELIC, S.D.

    1999-01-01

    This document provides the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report

  8. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    International Nuclear Information System (INIS)

    CROWE, R.D.

    1999-01-01

    This document provides the detailed accident analysis to support ''HNF-3553, Spent Nuclear Fuel Project Final Safety, Analysis Report, Annex A,'' ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report

  9. Cold Vacuum Drying Facility Design Basis Accident Analysis Documentation

    International Nuclear Information System (INIS)

    PIEPHO, M.G.

    1999-01-01

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report, ''Cold Vacuum Drying Facility Final Safety Analysis Report (FSAR).'' All assumptions, parameters and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR

  10. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    International Nuclear Information System (INIS)

    CROWE, R.D.; PIEPHO, M.G.

    2000-01-01

    This document provided the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report''. All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report

  11. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    Energy Technology Data Exchange (ETDEWEB)

    CROWE, R.D.; PIEPHO, M.G.

    2000-03-23

    This document provided the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report''. All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  12. Canister storage building design basis accident analysis documentation

    Energy Technology Data Exchange (ETDEWEB)

    KOPELIC, S.D.

    1999-02-25

    This document provides the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  13. System 80+trademark Standard Design: CESSAR design certification

    International Nuclear Information System (INIS)

    1990-01-01

    This report, entitled Combustion Engineering Standard Safety Analysis Report - Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80+trademark Standard Design. This Volume 16 details the application of Human Factors Engineering in the design process

  14. Basis for NGNP Reactor Design Down-Selection

    International Nuclear Information System (INIS)

    Demick, L.E.

    2010-01-01

    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.

  15. 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.

  16. 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.

  17. Basis for NGNP Reactor Design Down-Selection

    Energy Technology Data Exchange (ETDEWEB)

    L.E. Demick

    2011-11-01

    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.

  18. Design Basis for Fibre Reinforced Concrete (FRC) Pavements

    DEFF Research Database (Denmark)

    Bendixen, Søren; Stang, Henrik

    1996-01-01

    opening relationship can beused to descibe the properties of fibre reinforced concrete (FRC) intension and how the stress-crack opening relationship can beapplied in a simple design scheme for pavements. The projectincludes development of design tools, experiments to determine thestress-crack opening......The paper summarises a Ph.D. project on development of a new design basis for fibre reinforced concrete ground slabs. The stress-crack openingrelationship is a well know basic material property of theso-called fictitious crack model for concrete. In the presentstudy it is shown how the stress-crack...

  19. System 80+trademark standard design: CESSAR design certification

    International Nuclear Information System (INIS)

    1990-01-01

    This report has been prepared in support of the industry effort to standardize nuclear plant designs. The documents in this series describe the Combustion Engineering, Inc. System 80+ TM Standard Design

  20. System 80+trademark Standard Design: CESSAR design certification

    International Nuclear Information System (INIS)

    1990-01-01

    This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80 + trademark Standard Design. This volume 10 discusses the Steam and Power Conversion System and Radioactive Waste Management

  1. System 80+trademark Standard Design: CESSAR design certification

    International Nuclear Information System (INIS)

    1990-01-01

    This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80 + trademark Standard Design. This volume 9 discusses Electric Power and Auxiliary Systems

  2. System 80+trademark Standard Design: CESSAR design certification

    International Nuclear Information System (INIS)

    1990-01-01

    This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80 + trademark Standard Design. This volume 8 provides a description of instrumentation and controls

  3. System 80+trademark Standard Design: CESSAR design certification

    International Nuclear Information System (INIS)

    1990-01-01

    This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80+trademark Standard Design. This Volume 18 provides Appendix B, Probabilistic Risk Assessment

  4. System 80+trademark Standard Design: CESSAR design certification

    International Nuclear Information System (INIS)

    1990-01-01

    This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describes the Combustion Engineering, Inc. System 80+trademark Standard Design. This Volume 17 provides Appendix A of this report, closure of unresolved and Genetic Safety Issues

  5. System 80+trademark standard design: CESSAR design certification

    International Nuclear Information System (INIS)

    1990-01-01

    This report, entitled Combustion Engineering Standard Safety Analysis Report--Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These documents describe the Combustion Engineering, Inc. System 80+trademark Standard Design. This report, Volume 13, documents increase and decrease of reactor cooling system inventory and radioactive material release from a subsystem or component

  6. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    Energy Technology Data Exchange (ETDEWEB)

    CROWE, R.D.

    1999-09-09

    This document provides the detailed accident analysis to support ''HNF-3553, Spent Nuclear Fuel Project Final Safety, Analysis Report, Annex A,'' ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  7. Design basis tropical cyclone for nuclear power plants

    International Nuclear Information System (INIS)

    1984-01-01

    The general characteristics of tropical cyclones are discussed in this Safety Guide, with particular emphasis on their pressure and wind structures in the light of available data. General methods are given for the evaluation of the relevant parameters of a Probable Maximum Tropical Cyclone (PMTC), which can be used as the Design Basis Tropical Cyclone (DBTC); these parameters then serve as inputs for the derivation of a design basis surge and a design basis wind. A possible method is also given for the evaluation of the PMTC pressure and wind field based on an approach valid primarily for a particular region. This method depends on the results of a theoretical study on the tropical cyclone structure and makes use of a large amount of data, including aircraft reconnaissance observations for 170 most intense tropical cyclones near the coast of Japan, Taiwan and the Philippines for the period 1960-1974, as well as detailed analyses of all the extreme storms along the Gulf of Mexico and the east coast of the USA during 1900-1978, for the determination of the necessary parameters

  8. Application of information technologies of automation designing for research of designs on nonlinear the deformed basis

    Directory of Open Access Journals (Sweden)

    Я.О. Слободян

    2004-04-01

    Full Text Available  The results of numerical researches of designs on nonlinear the deformed basis with application of modern information technologies of automation designing are given on the basis of a program complex LIRA also estimation of an error of the decision of a nonlinear task by a step-by-step method.

  9. Emergency procedures beyond design basis ''Feed and Bleed''

    International Nuclear Information System (INIS)

    Dominguez Bautista, M.T.; Campuzano Pena, F.

    1994-01-01

    The incorporation of Beyond-Design-Basis Emergency Procedures, also called the Emergency Manual or Severe Accident Manual, has been an important step forward in nuclear power plant safety. These procedures cover situations in which the deterministic criteria used in plant design have been contravened. In such situations new accident scenarios, unforeseen system actions or a combination of both, need to be considered. Establishing these procedures is actually the last in a sequence of activities the sequence includes definition of scenarios, study of their phenomena, analysis of optional system actions, verification of their effectiveness and finally, implementation of the procedure. The systematization of these new strategies is supported by the results of the probabilistic analyses which serve in this case to pinpoint the objectives of these strategies. This paper describes the application of this methodology in the definition of a procedure for heat sink recovery on the secondary side (feed and bleed) if this has been totally or partially lost in a beyond-design-basis event. (Author)

  10. Spent Nuclear Fuel (SNF) Project Design Basis Capacity Study

    International Nuclear Information System (INIS)

    CLEVELAND, K.J.

    2000-01-01

    This study of the design basis capacity of process systems was prepared by Fluor Federal Services for the Spent Nuclear Fuel Project. The evaluation uses a summary level model of major process sub-systems to determine the impact of sub-system interactions on the overall time to complete fuel removal operations. The process system model configuration and time cycle estimates developed in the original version of this report have been updated as operating scenario assumptions evolve. The initial document released in Fiscal Year (FY) 1996 varied the number of parallel systems and transport systems over a wide range, estimating a conservative design basis for completing fuel processing in a two year time period. Configurations modeling planned operations were updated in FY 1998 and FY 1999. The FY 1998 Base Case continued to indicate that fuel removal activities at the basins could be completed in slightly over 2 years. Evaluations completed in FY 1999 were based on schedule modifications that delayed the start of KE Basin fuel removal, with respect to the start of KW Basin fuel removal activities, by 12 months. This delay resulted in extending the time to complete all fuel removal activities by 12 months. However, the results indicated that the number of Cold Vacuum Drying (CVD) stations could be reduced from four to three without impacting the projected time to complete fuel removal activities. This update of the design basis capacity evaluation, performed for FY 2000, evaluates a fuel removal scenario that delays the start of KE Basin activities such that staffing peaks are minimized. The number of CVD stations included in all cases for the FY 2000 evaluation is reduced from three to two, since the scenario schedule results in minimal time periods of simultaneous fuel removal from both basins. The FY 2000 evaluation also considers removal of Shippingport fuel from T Plant storage and transfer to the Canister Storage Building for storage

  11. Spent Nuclear Fuel (SNF) Project Design Basis Capacity Study

    Energy Technology Data Exchange (ETDEWEB)

    CLEVELAND, K.J.

    2000-08-17

    This study of the design basis capacity of process systems was prepared by Fluor Federal Services for the Spent Nuclear Fuel Project. The evaluation uses a summary level model of major process sub-systems to determine the impact of sub-system interactions on the overall time to complete fuel removal operations. The process system model configuration and time cycle estimates developed in the original version of this report have been updated as operating scenario assumptions evolve. The initial document released in Fiscal Year (FY) 1996 varied the number of parallel systems and transport systems over a wide range, estimating a conservative design basis for completing fuel processing in a two year time period. Configurations modeling planned operations were updated in FY 1998 and FY 1999. The FY 1998 Base Case continued to indicate that fuel removal activities at the basins could be completed in slightly over 2 years. Evaluations completed in FY 1999 were based on schedule modifications that delayed the start of KE Basin fuel removal, with respect to the start of KW Basin fuel removal activities, by 12 months. This delay resulted in extending the time to complete all fuel removal activities by 12 months. However, the results indicated that the number of Cold Vacuum Drying (CVD) stations could be reduced from four to three without impacting the projected time to complete fuel removal activities. This update of the design basis capacity evaluation, performed for FY 2000, evaluates a fuel removal scenario that delays the start of KE Basin activities such that staffing peaks are minimized. The number of CVD stations included in all cases for the FY 2000 evaluation is reduced from three to two, since the scenario schedule results in minimal time periods of simultaneous fuel removal from both basins. The FY 2000 evaluation also considers removal of Shippingport fuel from T Plant storage and transfer to the Canister Storage Building for storage.

  12. Design Optimization of Centrifugal Pump Using Radial Basis Function Metamodels

    Directory of Open Access Journals (Sweden)

    Yu Zhang

    2014-05-01

    Full Text Available Optimization design of centrifugal pump is a typical multiobjective optimization (MOO problem. This paper presents an MOO design of centrifugal pump with five decision variables and three objective functions, and a set of centrifugal pumps with various impeller shroud shapes are studied by CFD numerical simulations. The important performance indexes for centrifugal pump such as head, efficiency, and required net positive suction head (NPSHr are investigated, and the results indicate that the geometry shape of impeller shroud has strong effect on the pump's performance indexes. Based on these, radial basis function (RBF metamodels are constructed to approximate the functional relationship between the shape parameters of impeller shroud and the performance indexes of pump. To achieve the objectives of maximizing head and efficiency and minimizing NPSHr simultaneously, multiobjective evolutionary algorithm based on decomposition (MOEA/D is applied to solve the triobjective optimization problem, and a final design point is selected from the Pareto solution set by means of robust design. Compared with the values of prototype test and CFD simulation, the solution of the final design point exhibits a good consistency.

  13. Archaeological data as a basis for repository marker design

    International Nuclear Information System (INIS)

    Kaplan, M.F.

    1982-10-01

    This report concerns the development of a marking system for a nuclear waste repository which is very likely to survive for 10,000 years. In order to provide a background on the subject, and for the preliminary design presented in this report, a discussion is presented about the issues involved in human interference with the repository system and the communication of information. A separate chapter summarizes six ancient man-made monuments including: materials, effects of associated textual information on our understanding of the monument, and other features of the ancient monument relevant to marking a repository site. The information presented in the two chapters is used to provide the basis and rationale for a preliminary marker system design presented in a final chapter. 86 refs., 22 figs., 1 tab

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

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  15. Archaeological data as a basis for repository marker design

    Energy Technology Data Exchange (ETDEWEB)

    Kaplan, M.F.

    1982-10-01

    This report concerns the development of a marking system for a nuclear waste repository which is very likely to survive for 10,000 years. In order to provide a background on the subject, and for the preliminary design presented in this report, a discussion is presented about the issues involved in human interference with the repository system and the communication of information. A separate chapter summarizes six ancient man-made monuments including: materials, effects of associated textual information on our understanding of the monument, and other features of the ancient monument relevant to marking a repository site. The information presented in the two chapters is used to provide the basis and rationale for a preliminary marker system design presented in a final chapter. 86 refs., 22 figs., 1 tab.

  16. Cold Vacuum Drying facility design basis accident analysis documentation

    Energy Technology Data Exchange (ETDEWEB)

    CROWE, R.D.

    2000-08-08

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls.

  17. State Skill Standards: Housing and Interior Design

    Science.gov (United States)

    Nevada Department of Education, 2008

    2008-01-01

    Meeting the Housing and Interior Design Standards will provide students with skills for personal family life and towards becoming a professional in the interior design field. The mission of Housing and Interior Design education is to prepare students for family life, work life, and careers in the fashion industry by creating opportunities to…

  18. Transient and accident analyses topical design basis documents

    International Nuclear Information System (INIS)

    Chi, Larry; Eckert, Eugene; Grim, Brit

    2004-01-01

    The designers and operators of nuclear power plants have extensively documented system functions, licensing performance, and operating procedures for all conditions. This paper presents a complementary, systematic approach for the documentation of all requirements that are based on the analysis of operational transients, abnormal transients, accidents, and other events which are included in the design and licensing basis for the plant. Up to now, application of the approach has focused on required mitigation actions (automatic or manual). All mitigation actions are directly identified with all applicable reactor events, as well as the plant-unique systems that work together to perform each function. The approach is also applicable to all operational functions. The approach makes extensive use of data base methods, thereby providing effective ways to interrogate the information for the varied users of this information. Examples of use include: evaluations of system design changes and equipment modifications, safety evaluations of any plant change (e.g., USNRC 10CFR50.59 review), plant operations (e.g., manual actions during unplanned events), system interactions, classification of safety-related equipment, environmental qualification of equipment, and mitigation requirements for different reactor operating states. This approach has been applied in customized ways to several boiling water reactor (BWR) units, based on the desires and needs of the specific utility. (author)

  19. Study on risk factors of PWR accidents beyond design basis

    International Nuclear Information System (INIS)

    Ahn, Seung Hoon; Nah, W. J.; Bang, Y. S.; Oh, D. Y.; Oh, S. H.

    2005-01-01

    Development of the regulatory guidelines for Beyond Design Basis Accidents (BDBA) with high risk requires a detailed investigation of major factors contributing to the event risk. In this study, each event was classified by the level of risk, based on the probabilistic safety assessment results, so that BDBA with high risk could be selected, with consideration of foreign and domestic regulations, and operating experiences. The regulatory requirements and technical backgrounds for the selected accidents were investigated, and effective regulatory approaches for risk reduction of the accidents. The following conclusions were drawn from this study: - Selected high risk BDBA is station blackout, anticipated without scram, total loss of feedwater. - Major contributors to the risk of selected events were investigated, and appropriate assessment of them was recommended for development of the regulatory guidelines

  20. Three Design Basis Accidents’ Analysis on the HTR-10GT

    Directory of Open Access Journals (Sweden)

    Minggang Lang

    2017-01-01

    Full Text Available The study simulated the design basis accidents (DBAs sequences of the HTR-10GT core with THERMIX. When a DBA happens, the protection system will receive a scram signal which shall lead to active measures to shut down the reactor following it. In the paper, three typical DBA cases were studied. They include an accident induced by station blackout, a case caused by the withdrawal of one control rod out of the core by a mistake, and a case resulting from an earthquake, respectively. The simulation results illustrate that the fuel peak temperatures in the core during these accidents are 1066°C, 1201°C and 1067°C, respectively. It is shown that the HTR-10GT has a good safety characteristic.

  1. PRELIMINARY DESIGN BASIS EVENT ANALYSIS OF DOE SNF

    International Nuclear Information System (INIS)

    S. Tsai

    1999-01-01

    The purpose of this document is to perform a preliminary design basis event (DBE) analysis of the DOE Spent Nuclear Fuel (SNF) waste form. The objective of the analysis is to determine any preclosure safety impacts of the waste form on the Monitored Geologic Repository (MGR). The scope of this analysis is to determine the offsite dose consequences and associated frequencies of selected DBEs for systems handling disposable canisters that bound all surface and subsurface off-normal events, and to compare these results against regulatory limits. The results of this work are preliminary and are intended to be used to establish a set of preliminary MGR and waste form requirements, to identify mitigation or prevention features that may be required to meet regulatory limits, and to provide input to the Site Recommendation (SR) report. This document is prepared in accordance with the associated development plan (Civilian Radioactive Waste Management System Management and Operating Contractor [CRWMS M andO] 1999g)

  2. System 80+trademark Standard Design: CESSAR design certification. Volume 25

    International Nuclear Information System (INIS)

    1997-01-01

    This report has been prepared in support of the industry effort to standardize nuclear plant designs. This document describes the Combustion Engineering, Inc. System 80+trademark Standard Design. This volume contains sections 12 thru 16 of Chapter 19 -- Probabilistic Risk Assessment. Topics covered are: containment response analysis; consequence analysis; containment response and consequence analysis sensitivity analysis; summary and conclusions; and references

  3. DOE Standard: Fire protection design criteria

    Energy Technology Data Exchange (ETDEWEB)

    1999-07-01

    The development of this Standard reflects the fact that national consensus standards and other design criteria do not comprehensively or, in some cases, adequately address fire protection issues at DOE facilities. This Standard provides supplemental fire protection guidance applicable to the design and construction of DOE facilities and site features (such as water distribution systems) that are also provided for fire protection. It is intended to be used in conjunction with the applicable building code, National Fire Protection Association (NFPA) Codes and Standards, and any other applicable DOE construction criteria. This Standard replaces certain mandatory fire protection requirements that were formerly in DOE 5480.7A, ``Fire Protection``, and DOE 6430.1A, ``General Design Criteria``. It also contains the fire protection guidelines from two (now canceled) draft standards: ``Glove Box Fire Protection`` and ``Filter Plenum Fire Protection``. (Note: This Standard does not supersede the requirements of DOE 5480.7A and DOE 6430.1A where these DOE Orders are currently applicable under existing contracts.) This Standard, along with the criteria delineated in Section 3, constitutes the basic criteria for satisfying DOE fire and life safety objectives for the design and construction or renovation of DOE facilities.

  4. DOE Standard: Fire protection design criteria

    International Nuclear Information System (INIS)

    1999-07-01

    The development of this Standard reflects the fact that national consensus standards and other design criteria do not comprehensively or, in some cases, adequately address fire protection issues at DOE facilities. This Standard provides supplemental fire protection guidance applicable to the design and construction of DOE facilities and site features (such as water distribution systems) that are also provided for fire protection. It is intended to be used in conjunction with the applicable building code, National Fire Protection Association (NFPA) Codes and Standards, and any other applicable DOE construction criteria. This Standard replaces certain mandatory fire protection requirements that were formerly in DOE 5480.7A, ''Fire Protection'', and DOE 6430.1A, ''General Design Criteria''. It also contains the fire protection guidelines from two (now canceled) draft standards: ''Glove Box Fire Protection'' and ''Filter Plenum Fire Protection''. (Note: This Standard does not supersede the requirements of DOE 5480.7A and DOE 6430.1A where these DOE Orders are currently applicable under existing contracts.) This Standard, along with the criteria delineated in Section 3, constitutes the basic criteria for satisfying DOE fire and life safety objectives for the design and construction or renovation of DOE facilities

  5. 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

  6. SRS BEDROCK PROBABILISTIC SEISMIC HAZARD ANALYSIS (PSHA) DESIGN BASIS JUSTIFICATION

    International Nuclear Information System (INIS)

    2005-01-01

    This represents an assessment of the available Savannah River Site (SRS) hard-rock probabilistic seismic hazard assessments (PSHAs), including PSHAs recently completed, for incorporation in the SRS seismic hazard update. The prior assessment of the SRS seismic design basis (WSRC, 1997) incorporated the results from two PSHAs that were published in 1988 and 1993. Because of the vintage of these studies, an assessment is necessary to establish the value of these PSHAs considering more recently collected data affecting seismic hazards and the availability of more recent PSHAs. This task is consistent with the Department of Energy (DOE) order, DOE O 420.1B and DOE guidance document DOE G 420.1-2. Following DOE guidance, the National Map Hazard was reviewed and incorporated in this assessment. In addition to the National Map hazard, alternative ground motion attenuation models (GMAMs) are used with the National Map source model to produce alternate hazard assessments for the SRS. These hazard assessments are the basis for the updated hard-rock hazard recommendation made in this report. The development and comparison of hazard based on the National Map models and PSHAs completed using alternate GMAMs provides increased confidence in this hazard recommendation. The alternate GMAMs are the EPRI (2004), USGS (2002) and a regional specific model (Silva et al., 2004). Weights of 0.6, 0.3 and 0.1 are recommended for EPRI (2004), USGS (2002) and Silva et al. (2004) respectively. This weighting gives cluster weights of .39, .29, .15, .17 for the 1-corner, 2-corner, hybrid, and Greens-function models, respectively. This assessment is judged to be conservative as compared to WSRC (1997) and incorporates the range of prevailing expert opinion pertinent to the development of seismic hazard at the SRS. The corresponding SRS hard-rock uniform hazard spectra are greater than the design spectra developed in WSRC (1997) that were based on the LLNL (1993) and EPRI (1988) PSHAs. The

  7. The concept of risk in the design basis threat

    International Nuclear Information System (INIS)

    Reynolds, J.M.

    2001-01-01

    Full text: Mathematically defined, risk is a product of one or more probability factors and one or more consequences. Actuarial analysis of risk requires the creation of a numeric algorithm that reflects the interaction of different probability factors, where probability data usually draws on direct measurements of incidence. For physical protection purposes, the algorithms take the general form: Risk = Probability of successful attack x Consequence where the overall probability of a successful attack will be determined by the product of, amongst other things, the probability of there being sufficient intent, the probability of there being available hostile resources, the probability of deterrence, and the probability that a hostile act will be detected and prevented. Deliberate, malevolent acts against nuclear facilities are rare. In so far as it is possible to make an actuarial type of judgement, the probability of malevolent activity against a nuclear facility is almost zero. This creates a problem for a numerical assessment of risk for nuclear facilities where the value (consequence) term could be almost infinite. As can be seen from the general equation above, a numerical algorithm of risk of malevolent activity affecting nuclear facilities could only yield a zero or infinite result. In such circumstances, intelligence-based threat assessments are sometimes thought of as a substitute for historic data in the determination of probability. However, if the paucity of historic data reflects the actual threat - which by and large it should - no amount of intelligence is likely to yield a substantially different conclusion. This mathematical approach to analysing risk appears to lead us either to no risk and no protection or to an infinite risk demanding every conceivable protective measure. The Design Basis Threat (DBT) approach offers a way out of the dilemma. Firstly, it allows us to eliminate from further consideration all zero or near zero probabilities

  8. Improved Design Basis for Laterally Loaded Large Diameter Pile

    DEFF Research Database (Denmark)

    Leth, Caspar Thrane

    in dry sand by use of centrifuge modelling and to compare the findings with the standard p-y curves. It has been chosen to apply piles with an embedment length of 6 to 10 times the diameter of the applied piles. The general static behaviour of monopiles in dry sand has based on centrifuge tests been...... initial response and a higher ultimate capacity. The initial stiffness of the soil-structure interaction measured in the centrifuge tests, equivalent to initial stiffness of p-y curves, shows a dependency of depth and diameter. Control issues in relation to cyclic tests have resulted in tests...... on the structure and the productivity of the turbine. Current design practice for monopiles are based on p-y curves developed for slender piles with a diameter of 0.6 m. The focus on the structure stiffness has entailed a significant research on the soil-structure interaction for large diameter monopiles...

  9. Assessment of Offshore Wind System Design, Safety, and Operation Standards

    Energy Technology Data Exchange (ETDEWEB)

    Sirnivas, Senu [National Renewable Energy Lab. (NREL), Golden, CO (United States); Musial, Walt [National Renewable Energy Lab. (NREL), Golden, CO (United States); Bailey, Bruce [AWS Trupower LLC, Albany, NY (United States); Filippelli, Matthew [AWS Trupower LLC, Albany, NY (United States)

    2014-01-01

    This report is a deliverable for a project sponsored by the U.S. Department of Energy (DOE) entitled National Offshore Wind Energy Resource and Design Data Campaign -- Analysis and Collaboration (contract number DE-EE0005372; prime contractor -- AWS Truepower). The project objective is to supplement, facilitate, and enhance ongoing multiagency efforts to develop an integrated national offshore wind energy data network. The results of this initiative are intended to 1) produce a comprehensive definition of relevant met-ocean resource assets and needs and design standards, and 2) provide a basis for recommendations for meeting offshore wind energy industry data and design certification requirements.

  10. Plutonium Can-In-Canister-Design Basis Event Analysis

    International Nuclear Information System (INIS)

    Kaplan, G.; Tsai, S.S.

    1999-01-01

    The purpose of this document is to perform a preliminary design basis event (DBE) analysis of the immobilized plutonium (can-in-canister) waste form to be referred to in this analysis as high level waste/plutonium (HLW/Pu). The objective of the analysis is to determine any preclosure safety impacts of the waste form on the Monitored Geologic Repository (MGR). The scope of this analysis is to determine the offsite dose consequences and associated frequencies of selected DBEs for systems handling disposable canisters that bound all surface and subsurface off-normal events, and to compare these results against regulatory limits. The results of this work are preliminary and are intended to be used to establish a set of preliminary MGR and waste form requirements, to identify mitigation or prevention options that may be required to meet regulatory limits, and to provide input to the Site Recommendation (SR) report. This document is prepared in accordance with the associated development plan (Civilian Radioactive Waste Management System Management and Operating Contractor [CRWMS M and O] 1999e)

  11. System 80+trademark Standard Design: CESSAR design certification. Volume 8

    International Nuclear Information System (INIS)

    1997-01-01

    This report has been prepared in support of the industry effort to standardize nuclear plant designs. This document describes the Combustion Engineering, Inc. System 80+trademark Standard Design. This volume contains Chapter 7 -- Instrumentation and Controls. Topics covered are: reactor protection system; engineered safety feature actuation systems; systems required for safe shutdown; safety-related display instrumentation; all other instrumentation for safety; and control systems not required for safety. Appendix 7A is included

  12. MOV motor and gearbox performance under design basis loads

    International Nuclear Information System (INIS)

    DeWall, K.G.; Watkins, J.C.

    1998-01-01

    This paper describes the results of valve testing sponsored by the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research and conducted at the Idaho National Engineering and Environmental Laboratory. The research objective was to evaluate the capabilities of specific actuator motor and gearbox assemblies under various design basis loading conditions. The testing was performed using the motor-operated valve load simulator, a test fixture that simulates the stem load profiles a valve actuator would experience when closing a valve against flow and pressure loadings. The authors tested five typical motors (four ac motors and one dc motor) with three gearbox assemblies at conditions a motor might experience in a power plant, including such off-normal conditions as operation at high temperature and reduced voltage. The authors also determined the efficiency of the actuator gearbox. The testing produced the following significant results: all five motors operated at or above their rated torque during tests at full voltage and ambient temperature; for all five motors (dc as well as ac), the actual torque loss due to voltage degradation was greater than the torque loss predicted using common methods; startup torques in locked rotor tests compared well with stall torques in dynamometer-type tests; the methods commonly used to predict torque losses due to elevated operating temperatures sometimes bounded the actual losses, but not in all cases; the greatest discrepancy involved the prediction for the dc motor; running efficiencies published by the manufacturer for actuator gearboxes were higher than the actual efficiencies determined from testing, in some instances, the published pullout efficiencies were also higher than the actual values; operation of the gearbox at elevated temperature did not affect the operating efficiency

  13. Design basis flood for nuclear power plants on river sites

    International Nuclear Information System (INIS)

    1983-01-01

    The Guide presents techniques for determining the design basis flood (DBF) to be used for siting nuclear power plants at or near non-tidal reaches of rivers and for protecting nuclear power plants against floods. Since flooding of a nuclear power plant can have repercussions on safety, the DBF is always chosen to have a very low probability of exceedance per annum. The DBF may result from one or more of the following causes: (1) Precipitation, snowmelt; (2) Failure of water control structures, either from seismic or hydrological causes or from faulty operation of these structures; (3) Channel obstruction such as landslide, ice effects, log or debris jams, and effects of vulcanism. Normally the DBF is not less than any recorded or historical flood occurrence. For flood evaluation two types of methods are discussed in this Guide: probabilistic and deterministic. Simple probabilistic methods to determine floods of such low exceedance probability have a great degree of uncertainty and are presented for use only during the site survey. However, the more sophisticated probabilistic methods, the so-called stochastic methods, may give an acceptable result, as outlined in this Guide. The preferred method of evaluating the component of the DBF due to precipitation, as described in this Guide, is the deterministic one, based on the concept of a limit to the probable maximum precipitation (PMP) and on the unit hydrograph technique. Dam failures may generate a flood substantially more severe than that due to precipitation. The methodology for evaluating these types of floods is therefore presented in this Guide. Making allowance for the possible simultaneous occurrence of two or more important flood-producing events is also discussed here. The Guide does not deal with floods caused by sabotage

  14. NPP Design Basis Handover and Knowledge Preservation from Subcontractors, Vendors and EPC

    International Nuclear Information System (INIS)

    Freeland, Kent

    2013-01-01

    Using PLM-based Workflow for Configuration Management (CM) in the Nuclear Power Industry Advantages – some work to do! • NPP’s must adapt to using PLM-based solutions to support CM and to synchronize design changes to asset or product changes, and reduce “slipstreaming”. In the NPP world, this often appears as events that circumvent CM – for example, non-approved parts substitutions and “temporary” plant modifications that are never removed. • PLM serves as the method for unifying the application of requirements to design changes, processes and workflow. In NPP’s, requirements are generally considered only relevant to designs – not process and workflow. • PLM supports Configuration Management and Design Basis in Regulator Action Tracking for NPP’s, and application of PLM-based CM to regulator action and compliance systems. This is a poorly-understood application of CM in NPP’s, yet these elements control large parts of the NPP design basis. • Suppliers, EPC’s and Technology Vendors must also understand the role of CM, SE and PLM in construction of new standards-driven NPP designs (like EPR and Westinghouse AP-1000 NPP designs), as well as understanding the role and handling of Knowledge Systems

  15. An operator basis for the Standard Model with an added scalar singlet

    Energy Technology Data Exchange (ETDEWEB)

    Gripaios, Ben [Cavendish Laboratory, J.J. Thomson Avenue, Cambridge (United Kingdom); Sutherland, Dave [Cavendish Laboratory, J.J. Thomson Avenue, Cambridge (United Kingdom); Kavli Institute for Theoretical Physics, UCSB Kohn Hall, Santa Barbara CA (United States)

    2016-08-17

    Motivated by the possible di-gamma resonance at 750 GeV, we present a basis of effective operators for the Standard Model plus a scalar singlet at dimensions 5, 6, and 7. We point out that an earlier list at dimensions 5 and 6 contains two redundant operators at dimension 5.

  16. Business School's Performance Management System Standards Design

    Science.gov (United States)

    Azis, Anton Mulyono; Simatupang, Togar M.; Wibisono, Dermawan; Basri, Mursyid Hasan

    2014-01-01

    This paper aims to compare various Performance Management Systems (PMS) for business school in order to find the strengths of each standard as inputs to design new model of PMS. There are many critical aspects and gaps notified for new model to improve performance and even recognized that self evaluation performance management is not well…

  17. Design Standards for School Art Facilities

    Science.gov (United States)

    National Art Education Association, 2015

    2015-01-01

    "Design Standards for School Art Facilities" is an invaluable resource for any school or school district looking to build new facilities for the visual arts or renovate existing ones. Discover detailed information about spaces for the breadth of media used in the visual arts. Photographs illustrate all types of features including…

  18. The earthquake problem in engineering design: generating earthquake design basis information

    International Nuclear Information System (INIS)

    Sharma, R.D.

    1987-01-01

    Designing earthquake resistant structures requires certain design inputs specific to the seismotectonic status of the region, in which a critical facility is to be located. Generating these inputs requires collection of earthquake related information using present day techniques in seismology and geology, and processing the collected information to integrate it to arrive at a consolidated picture of the seismotectonics of the region. The earthquake problem in engineering design has been outlined in the context of a seismic design of nuclear power plants vis a vis current state of the art techniques. The extent to which the accepted procedures of assessing seismic risk in the region and generating the design inputs have been adherred to determine to a great extent the safety of the structures against future earthquakes. The document is a step towards developing an aproach for generating these inputs, which form the earthquake design basis. (author)

  19. Science, education and industry information resources complementarity as a basis for design of knowledge management systems

    Science.gov (United States)

    Maksimov, N. V.; Tikhomirov, G. V.; Golitsyna, O. L.

    2017-01-01

    The main problems and circumstances that influence the processes of creating effective knowledge management systems were described. These problems particularly include high species diversity of instruments for knowledge representation, lack of adequate lingware, including formal representation of semantic relationships. For semantic data descriptions development a conceptual model of the subject area and a conceptual-lexical system should be designed on proposals of ISO-15926 standard. It is proposed to conduct an information integration of educational and production processes on the basis of information systems technologies. Integrated knowledge management system information environment combines both traditional information resources and specific information resources of subject domain including task context and implicit/tacit knowledge.

  20. Development of Mitigation Strategy for Beyond Design Basis External Events for NRC Design Certification

    International Nuclear Information System (INIS)

    Kim, Dong Hak; Lee, Jae Jong; Kim, Myung Ki

    2013-01-01

    In this study, how to develop FLEX strategy for beyond-design-basis external events for U. S. NRC design certification is examined. The development method of FLEX strategy for U. S. NRC design certification is examined. The applicants should make unit-specific FLEX strategy and establish the minimum coping capabilities consistent with unit-specific evaluation of the potential impacts and responses to BDBEEs. NEI 12-06 outlines the process to define and deploy the diverse and flexible mitigation strategies(FLEX strategy) that will increase defense-in-depth for beyond-design-basis scenarios to address the extended loss of alternating current (ac) power (ELAP) and loss of normal access to the ultimate heat sink (LUHS) occurring simultaneously at all units on a site. The order (EA-12-049) is issued to all reactor licensees, including holders of active, Construction Permit (CP) holders, and Combined License (COL) holders. Applicants for the new reactor design certification should prepare and submit FLEX strategy for NRC staff's review. Site-specific data related with the new reactor can't be determined during the new reactor design certification applications so that the unit-specific FLEX strategy should be developed

  1. 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

  2. Evaluation of a performance-based standards approach to heavy vehicle design to reduce pavement wear

    CSIR Research Space (South Africa)

    Nordengen, Paul A

    2013-11-01

    Full Text Available of the Australian PBS system while the infrastructure performance standards are based on South African bridge and pavement design standards. In order to optimise road wear per ton of payload, the South African Mechanistic-Empirical Design Method, which is the basis...

  3. Key issues on safety design basis selection and safety assessment

    International Nuclear Information System (INIS)

    An, S.; Togo, Y.

    1976-01-01

    In current fast reactor design in Japan, four design accident conditions and four design seismic conditions are adopted as the design base classifications. These are classified by the considerations on both likelihood of occurrence and the severeness of the consequences. There are several major problem areas in safety design consideration such as core accident problems which include fuel sodium interaction, fuel failure propagation and residual decay heat removal, and decay heat removal systems problems which is more or less the problem of selection of appropriate system and of assurance of high reliability of the system. In view of licensing, two kinds of accidents are postulated in evaluating the adequacy of a reactor site. The one is the ''major accident'' which is the accident to give most severe radiation hazard to the public from technical point of view. The other is the ''hypothetical accident'', induced public accident of which is severer than that of major accident. While the concept of the former is rather unique to Japanese licensing, the latter is almost equivalent to design base hypothetical accident of the US practice. In this paper, design bases selections, key safety issues and some of the licensing considerations in Japan are described

  4. CIF---Design basis for an integrated incineration facility

    International Nuclear Information System (INIS)

    Bennett, G.F.

    1991-01-01

    This paper discusses the evolution of chosen technologies that occurred during the design process of the US Department of Energy (DOE) incineration system designated the Consolidated Incineration Facility (CIF) as the Savannah River Plant, Aiken, South Carolina. The Plant is operated for DOE by the Westinghouse Savannah River Company. The purpose of the incineration system is to treat low level radioactive and/or hazardous liquid and solid wastes by combustion. The objective for the facility is to thermally destroy toxic constituents and volume reduce waste material. Design criteria requires operation be controlled within the limits of RCRA's permit envelope

  5. 76 FR 50275 - Guidance for the Assessment of Beyond-Design-Basis Aircraft Impacts

    Science.gov (United States)

    2011-08-12

    ... COMMISSION Guidance for the Assessment of Beyond-Design-Basis Aircraft Impacts AGENCY: Nuclear Regulatory...-Design-Basis Aircraft Impacts.'' This guide describes a method that the staff of NRC considers acceptable... for Performing Aircraft Impact Assessments for New Plant Designs,'' Revision 8, issued April 2011. The...

  6. Biologic basis of TCM syndromes and the standardization of syndrome classification

    Directory of Open Access Journals (Sweden)

    Fafeng Cheng

    2014-10-01

    Full Text Available Traditional Chinese medicine (TCM syndrome is an integral and essential component of TCM theory, and goes beyond philosophic concepts. This article reviews the concept of TCM syndromes and summarizes research findings on the biologic foundation of syndromes. In addition, insight is provided into the promotion of standardization of syndrome classification by enforcing uniformity of TCM terminology, applying standardized diagnostic criteria and operating procedures to minimize subjective effects. Also incorporating interdisciplinary approaches such as data mining and structure modeling, as well as integrating findings on biomarker research are discussed. Consideration is made of the fundamental TCM aspects of syndrome elements, symptoms, phenotypic features, as well as diseases, to form an integral process in the diagnostic path. We believe that better understanding of the biologic basis of the TCM syndrome and standardization of syndrome classification will improve diagnosis, which in turn will enhance therapeutic efficacy and disease prognosis.

  7. Metrological Array of Cyber-Physical Systems. Part 15. Approach to the Creation of Temperature Standard on Basis of Fundamental Physical Constants

    Directory of Open Access Journals (Sweden)

    Bohdan STADNYK

    2016-04-01

    Full Text Available After proving the existence of Temperature Quantum the next step would be the study of possibility of Temperature Standard creation. We consider the general principles of design and operation of such advanced Temperature Standard constructed on the basis of Quantum Temperature Unit. The latter is determined solely via the fundamental physical constants. Approach to the mentioned Standard is developed in this paper.

  8. Planning for nuclear security: Design Basis Threats and physical ...

    African Journals Online (AJOL)

    A competent authority for nuclear security then gives approval for the implementation of the physical protection plan. The DBT assessment methodology is an International Atomic Energy Agency (IAEA) recommended method for designing security measures corresponding to the categories of radioactive sources. The higher ...

  9. Proposal of the stiffness design model of the column basis

    NARCIS (Netherlands)

    Wald, F.; Sokol, Z.; Steenhuis, C.M.

    1996-01-01

    The connection between the steel column footing and the concrete foundation has a rotational rigidity significant for the overall frame analysis. This rigidity could be taken into account to predict the horizontal drift of the frame in serviceability limit state. A pi J posal of the stiffness design

  10. Design basis reconstitution and configuration management of nuclear power plants

    International Nuclear Information System (INIS)

    Smith, P.R.

    1989-01-01

    The major design requirements of nuclear power plant components, systems, and structures are found in the plant's licensing commitments documented in the Final Safety Analysis Report and in the technical specification commitments of the plant. These specifications consider the original design and its degradation by in-service use. Before a nuclear power plant begins operation, the plant systems, structures, and organizational elements are functionally arranged to operate in a particular way. This functional arrangement is specified by the plant's design requirements and is called its configuration. The paper discusses configuration management and information management for configuration management. The management of large amounts of information and the various information systems associated with nuclear generating facilities is an ever-growing challenge for utilities. Plant operations involve a complex interrelation among data elements, especially in relation to design modifications and operational changes. Consequently, the operation of these data systems is interrelated and, as a result, redundant data items may exist. Thus, in view of the need to control and manage the plant configuration baseline, managers are striving to streamline their information management programs, which usually involves the integration of data-base systems

  11. DBADOSE: a PC program for stack design and the PRR-1 design basis accident

    International Nuclear Information System (INIS)

    Leopando, L.S.

    1994-01-01

    DBA D OSE is a program written to be used as a tool to verify the adequacy of the design of the stack of the Philippine Research Reactor-1 (PRR-1) under design basis accident conditions. DBA D OSE runs on IBM-compatible personal computers. In the design basis accident, a substantial amount of fission products is released into the air inside the reactor building. The emergency ventilation system is assumed to function, creating a negative air pressure inside the building that will prevent the uncontrolled release of fission products into the atmosphere. The emergency ventilation system will drive filtered building air through a stack to create the negative pressure. Unavoidably, some of the fission products will pass through the filter and will be discharged. The fission products will be carried by the wind beyond the reactor site and will cause some exposure of the public to radiation. DBA D OSE may be used to calculate the amounts of exposure dose for various stack configurations and meteorological conditions at given distances from the reactor. The exposure doses may be compared with acceptable limits. The source code of DBA D OSE contains approximately 3000 lines of FORTRAN-77 (written for the Microsoft Fortran 4.10 compiler) and 300 lines of assembler. DBA D OSE.EXE is only 58 kB in size and needs only about 71 kB of RAM to run. A math-coprocessor is not needed but will speed up runs considerably. (author). 8 refs., 8 tabs

  12. DESIGN BASIS ACCIDENT ANALYSIS OF A SMALL MODULAR REACTOR

    OpenAIRE

    Aydogan, Fatih

    2017-01-01

    The International Reactor Innovative and Secure (IRIS) is an integrated small modular reactor (SMR) designed byWestinghouse Electric Company and a consortium of organizations. It has a thermal electric power rating of 1000MWth and an electric power rating of 335 MWe. Being an SMR that features a derivative pressurized water reactordesign, it contains the core, upper plenum, lower plenum, pressurizer, reactor coolant pumps, and steam generatorsin a single reactor vessel. An important feature o...

  13. Breckinridge Project, initial effort. Report II. Breckinridge Project design basis

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-01-01

    The Breckinridge Project is a pioneer endeavor involving the engineering, construction, and operation of a commercial facility that will convert 23,000 tons per day of run-of-mine, high-sulfur coal into 50,000 barrels per day of liquid hydrocarbons equivalent to those produced from crude oil. The Initial Effort, now complete, was executed under Cooperative Agreement No. DE-FC05-80OR20717 between the Department of Energy and the Participants, Ashland Synthetic Fuels, Inc., and Airco Energy Company, Inc. The Initial Effort produced a preliminary design, capital estimate, and economic analysis of the commercial plant, as well as a plan for the design, construction, and operation of that plant. The extensive and rigorous attention given to environmental, socioeconomic, safety, and health considerations is indicative of the high priority these issues will continue to receive throughout the life of the project. The Breckinridge Energy Company, a partnership of several major corporations, is being formed to finance, own, and manage the Breckinridge Project. Report II is intended for the reader who is primarily interested in less detailed discussion of the coal liquefaction process and Breckinridge facility than presented in the eleven volumes of Reports IV and V. The overview section describes the project goals and briefly introduces the coal liquefaction process. The report continues with a discussion of the history of the project and the H-COAL process from its concept to the proposed commercialization technology. The report describes the site, the Breckinridge Facility, and concludes with a summary of the eleven reports that contain the deliverable documentation of the Initial Effort or Development Phase of the project.

  14. 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 72.94 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE Siting Evaluation Factors § 72.94 Design basi...

  15. Standard mirror fusion reactor design study

    International Nuclear Information System (INIS)

    Moir, R.W.

    1978-01-01

    This report covers the work of the Magnetic Fusion Energy Division's reactor study group during FY 1976 on the standard mirror reactor. The ''standard'' mirror reactor is characterized as a steady state, neutral beam sustained, D-T fusioning plasma confined by a Yin-Yang magnetic mirror field. The physics parameters are obtained from the same physics model that explains the 2XIIB experiment. The model assumes that the drift cyclotron loss cone mode occurs on the boundary of the plasma, and that it is stabilized by warm plasma with negligible energy investment. The result of the study was a workable mirror fusion power plant, steady-state blanket removal made relatively simple by open-ended geometry, and no impurity problem due to the positive plasma potential. The Q (fusion power/injected beam power) turns out to be only 1.1 because of loss out the ends from Coulomb collisions, i.e., classical losses. This low Q resulted in 77% of the gross electrical power being used to power the injectors, thereby causing the net power cost to be high. The low Q stimulated an intensive search for Q-enhancement concepts, resulting in the LLL reactor design effort turning to the field reversal mirror and the tandem mirror, each having Q of order 5

  16. Improved Design Basis for Laterally Loaded Large Diameter Pile

    DEFF Research Database (Denmark)

    Leth, Caspar Thrane

    The development of offshore wind turbines has been in rapid growth since the construction of the first offshore wind farm in 1991 at Vindeby, Denmark. Developing from 11 turbines at a water depth of 2-6 m each with a capacity of 450 kW to the latest farms with up to 175 turbines each with a capac......The development of offshore wind turbines has been in rapid growth since the construction of the first offshore wind farm in 1991 at Vindeby, Denmark. Developing from 11 turbines at a water depth of 2-6 m each with a capacity of 450 kW to the latest farms with up to 175 turbines each...... with a capacity of 3.6 MW and placed at water depths beyond 25 m. Different foundation solutions have over the years been applied for offshore turbines, but monopiles are currently the most applied foundation type and are typically with a pile diameter of 4-6 m and applied up to a water depth of 25 m....... The expected development of offshore wind farms is towards larger farms, larger turbines and larger water depths. Monopiles have been applied widely and it is of interest to investigate the possibilities to further optimize the design and in particular the modelling of the soil-structure interaction...

  17. Reducing Uncertainty in the Seismic Design Basis for the Waste Treatment Plant, Hanford, Washington

    International Nuclear Information System (INIS)

    Brouns, Thomas M.; Rohay, Alan C.; Reidel, Steve; Gardner, Martin G.

    2007-01-01

    The seismic design basis for the Waste Treatment Plant (WTP) at the Department of Energy's (DOE) Hanford Site near Richland was re-evaluated in 2005, resulting in an increase by up to 40% in the seismic design basis. The original seismic design basis for the WTP was established in 1999 based on a probabilistic seismic hazard analysis completed in 1996. The 2005 analysis was performed to address questions raised by the Defense Nuclear Facilities Safety Board (DNFSB) about the assumptions used in developing the original seismic criteria and adequacy of the site geotechnical surveys. The updated seismic response analysis used existing and newly acquired seismic velocity data, statistical analysis, expert elicitation, and ground motion simulation to develop interim design ground motion response spectra which enveloped the remaining uncertainties. The uncertainties in these response spectra were enveloped at approximately the 84th percentile to produce conservative design spectra, which contributed significantly to the increase in the seismic design basis.

  18. Drain Tank Information for Developing Design Basis of the Preliminary Design - R00

    Energy Technology Data Exchange (ETDEWEB)

    Ferrada, Juan J [ORNL

    2011-01-01

    Tokamak Cooling Water System (TCWS) drain tanks (DTs) serve two functions: normal operation and safety operation. Normal DTs are used for regular maintenance operations when draining is necessary. Safety DTs are used to receive the water leaked into the Vacuum Vessel (VV) after an in-vessel loss of cooling accident (LOCA) event. The preliminary design of the DTs shall be based on the information provided by this document. The capacity of the normal DTs is estimated based on the internal volume of in-vessel components [e.g., First Wall/Blanket (FW/BLK) and Divertor (DIV)], Neutral Beam Injector (NBI) components, and TCWS piping, heat exchangers, electric heaters, pump casing, pressurizers, and valves. Water volumes have been updated based on 2004 design information, changes adopted because of approved Project Change Requests (PCRs), and data verification by U.S. ITER. Two tanks will store water from normal draining operations of the FW/BLK and DIV Primary Heat Transfer Systems (PHTSs). One tank will store water from normal draining operations of the NBI PHTS. The capacity of the safety DTs is based on analysis of a design-basis accident:1 a large leak from in-vessel components. There are two safety DTs that will receive water from a VV LOCA event and drainage from the VV, as needed. In addition, there is one sump tank for the DIV that will be used for collecting drain water from the draining and drying processes and specifically for draining the DIV system as the DIV cassettes lines are at a lower elevation than the DT connection point. Information documented in this report must be refined and verified during the preliminary design of the DTs, and there are several aspects to be considered to complete the preliminary design. Input to these design considerations is discussed in this report and includes, but is not limited to, water inventory; operating procedures/maintenance; Failure Modes and Effects Analysis (FMEA); tank layout anddimensions, including design

  19. Drain Tank Information for Developing Design Basis of the Preliminary Design

    Energy Technology Data Exchange (ETDEWEB)

    Ferrada, Juan J [ORNL

    2012-02-01

    Tokamak Cooling Water System (TCWS) drain tanks (DTs) serve two functions: normal operation and safety operation. Normal DTs are used for regular maintenance operations when draining is necessary. Safety DTs are used to receive the water leaked into the Vacuum Vessel (VV) after an in-vessel loss of coolant accident (LOCA) event. The preliminary design of the DTs shall be based on the information provided by this document. The capacity of the normal DTs is estimated based on the internal volume of in-vessel components [e.g., First Wall/Blanket (FW/BLK) and Divertor (DIV)]; Neutral Beam Injector (NBI) components; and TCWS piping, heat exchangers, electric heaters, pump casing, pressurizers, and valves. Water volumes have been updated based on 2004-design information, changes adopted because of approved Project Change Requests (PCRs), and data verification by US ITER and AREVA Federal Services, the US ITER A and E Company. Two tanks will store water from normal draining operations of the FW/BLK and DIV Primary Heat Transfer Systems (PHTSs). One tank will store water from normal draining operations of the NBI PHTS. The capacity of the safety DTs is based on analysis of a design basis accident: a large leak from in-vessel components. There are two safety DTs that will receive water from a VV LOCA event and drainage from the VV, as needed. In addition, there is one sump tank for the DIV that will be used for collecting drain water from the draining and drying processes and specifically for draining the DIV system as the DIV cassette lines are at a lower elevation than the DT connection point. Information documented in this report must be refined and verified during the preliminary design of the DTs, and there are several aspects to be considered to complete the preliminary design. Input to these design considerations is discussed in this report and includes, but is not limited to, water inventory; operating procedures/maintenance; Failure Modes and Effects Analysis (FMEA

  20. Basis of the tubesheet heat exchanger design rules used in the French pressure vessel code

    International Nuclear Information System (INIS)

    Osweiller, F.

    1990-01-01

    For about 40 years most tubesheet heat exchangers have been designed according to the standards of TEMA. Partly due to their simplicity, these rules do not assure a safe heat-exchangers design in all cases. This is the main reason why new tubesheet design rules were developed in 1981 in France for the French pressure vessel code CODAP. For fixed tubesheet heat exchangers the new rules account for the elastic rotational restraint of the shell and channel at the outer edge of the tubesheet. For floating-head and U- tube exchangers an approach was selected with some modifications. In both cases the tubesheet is replaced by an equivalent solid plate with adequate effective elastic constants, and the tube bundle is simulated by an elastic foundation. The elastic restraint at the edge of the tubesheet due the shell and channel is accounted for in different ways in the two types of heat exchangers. The purpose of the paper is to present the main basis of these rules and to compare them to TEMA rules

  1. Standard High Solids Vessel Design De-inventory Simulant Qualification

    Energy Technology Data Exchange (ETDEWEB)

    Fiskum, Sandra K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Burns, Carolyn A.M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gauglitz, Phillip A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Linn, Diana T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Peterson, Reid A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Smoot, Margaret R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2017-09-12

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is working to develop a Standard High Solids Vessel Design (SHSVD) process vessel. To support testing of this new design, WTP engineering staff requested that a Newtonian simulant be developed that would represent the de-inventory (residual high-density tank solids cleanout) process. Its basis and target characteristics are defined in 24590-WTP-ES-ENG-16-021 and implemented through PNNL Test Plan TP-WTPSP-132 Rev. 1.0. This document describes the de-inventory Newtonian carrier fluid (DNCF) simulant composition that will satisfy the basis requirement to mimic the density (1.18 g/mL ± 0.1 g/mL) and viscosity (2.8 cP ± 0.5 cP) of 5 M NaOH at 25 °C.1 The simulant viscosity changes significantly with temperature. Therefore, various solution compositions may be required, dependent on the test stand process temperature range, to meet these requirements. Table ES.1 provides DNCF compositions at selected temperatures that will meet the density and viscosity specifications as well as the temperature range at which the solution will meet the acceptable viscosity tolerance.

  2. Determination of a Basis for Design of a Yam (Dioscorea Spp ...

    African Journals Online (AJOL)

    Manual separation is both tedious and expensive, so the work reported here was done to determine a suitable basis for the design of a mechanical minisett sorter. Results from this study showed that the minisetts cut from the regions of the parent tuber can be separated on the basis of characteristic dimensions of arc length ...

  3. The Mixed Waste Management Facility. Design basis integrated operations plan (Title I design)

    International Nuclear Information System (INIS)

    1994-12-01

    The Mixed Waste Management Facility (MWMF) will be a fully integrated, pilotscale facility for the demonstration of low-level, organic-matrix mixed waste treatment technologies. It will provide the bridge from bench-scale demonstrated technologies to the deployment and operation of full-scale treatment facilities. The MWMF is a key element in reducing the risk in deployment of effective and environmentally acceptable treatment processes for organic mixed-waste streams. The MWMF will provide the engineering test data, formal evaluation, and operating experience that will be required for these demonstration systems to become accepted by EPA and deployable in waste treatment facilities. The deployment will also demonstrate how to approach the permitting process with the regulatory agencies and how to operate and maintain the processes in a safe manner. This document describes, at a high level, how the facility will be designed and operated to achieve this mission. It frequently refers the reader to additional documentation that provides more detail in specific areas. Effective evaluation of a technology consists of a variety of informal and formal demonstrations involving individual technology systems or subsystems, integrated technology system combinations, or complete integrated treatment trains. Informal demonstrations will typically be used to gather general operating information and to establish a basis for development of formal demonstration plans. Formal demonstrations consist of a specific series of tests that are used to rigorously demonstrate the operation or performance of a specific system configuration

  4. Guidance on the implementation of modifications to mitigate beyond design basis accidents

    International Nuclear Information System (INIS)

    Harris, S.; Marczak, J.; O'Neill, M.

    2014-01-01

    Following the events at Fukushima, Canadian Nuclear Power Plants (NPP) procured equipment and initiated modifications to improve response capability for Beyond Design Basis Accidents (BDBA). These changes were not typical of other design modifications to the nuclear power plants and reinforced the need for additional guidance for modifications to address BDBA. This paper describes the guidance that was developed to guide the design, procurement, installation, operation, and maintenance of equipment and modifications to mitigate BDBAs. The guidance developed prescribes a graded approach based on a categorization of the nature of the modification. Four categories of modifications are introduced, with the distinction being the degree of interface with existing design basis systems, structures and components (SSCs). This has resulted in a cost-effective means of implementing additional capability to mitigate BDBA conditions, and yet ensure the design basis capability of SSCs is maintained. Operating experience with use of the guidance is also discussed. (author)

  5. Design and fabrication of NDA standards

    International Nuclear Information System (INIS)

    Long, S.M.; Hsue, S.T.

    1996-01-01

    The Plutonium Facility, TA-55, at Los Alamos National Laboratory is currently producing NDA calibration standards used by various laboratories in the DOE complex. These NIST traceable standards have been produced to calibrate NDA instruments for accountability measurements used for resolving shipper/receiver differences, and for accountability in process residues and process waste. Standards are needed to calibrate various NDA (Non-destructive Assay) instruments such as neutron coincidence counters, gamma-ray counters, and calorimeters. These instruments measure various ranges of nuclear material being produced in the DOE nuclear community. Los Alamos National Laboratory has taken a lead role in fabrication of uranium and plutonium standards, along with other actinides such as neptunium and americium. These standards have been fabricated for several laboratories within the complex. This paper will summarize previous publications detailing the careful planning encompassing components such as precise weighing, destructive analysis, and the use of post fabrication NDA measurements to confirm that the standards meet all preliminary expectations before use in instrument calibration. The paper will also describe the specialized containers, diluents, and the various amount of nuclear materials needed to accommodate the calibration ranges of the instruments

  6. 38 CFR 39.22 - Architectural design standards.

    Science.gov (United States)

    2010-07-01

    ... 38 Pensions, Bonuses, and Veterans' Relief 2 2010-07-01 2010-07-01 false Architectural design...-16-10) Standards and Requirements for Project § 39.22 Architectural design standards. The..., Ontario, CA 91761-2816. (a) Architectural and structural requirements—(1) Life Safety Code. Standards must...

  7. JSC Design and Procedural Standards, JSC-STD-8080

    Science.gov (United States)

    Punch, Danny T.

    2011-01-01

    This document provides design and procedural requirements appropriate for inclusion in specifications for any human spaceflight program, project, spacecraft, system, or end item. The term "spacecraft" as used in the standards includes launch vehicles, orbital vehicles, non-terrestrial surface vehicles, and modules. The standards are developed and maintained as directed by Johnson Space Center (JSC) Policy Directive JPD 8080.2, JSC Design and Procedural Standards for Human Space Flight Equipment. The Design and Procedural Standards contained in this manual represent human spacecraft design and operational knowledge applicable to a wide range of spaceflight activities. These standards are imposed on JSC human spaceflight equipment through JPD 8080.2. Designers shall comply with all design standards applicable to their design effort.

  8. 76 FR 63541 - Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants

    Science.gov (United States)

    2011-10-13

    ... Hurricane Missiles for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide... regulatory guide, (RG) 1.221, ``Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants... missiles that a nuclear power plant should be designed to withstand to prevent undue risk to the health and...

  9. Establishing design basis threats for the physical protection of nuclear materials and facilities

    International Nuclear Information System (INIS)

    Chetvergov, S.

    2001-01-01

    In the area of nuclear energy utilization, the Republic of Kazakhstan follows the standards of international legislation and is a participant of the Nuclear Weapons Non-proliferation Treaty as a country that does not have nuclear weapons. In the framework of this treaty, Kazakhstan provides for the measures to ensure the regime of nonproliferation. The Republic signed the Agreement with the IAEA on the guarantee that was ratified by the Presidential Decree in 1995. Now the Government of the RK is considering the Convention on Physical Protection of Nuclear Materials. Kazakhstan legislation in the area of nuclear energy utilization is represented by a set of laws: the main of them is the Law of the Republic of Kazakhstan 'On the utilization of atomic energy', dated April 14, 1997. According to the Law, the issues of physical protection are regulated by interdepartmental guideline documents. Nuclear science and industry of RK include: Enterprises on uranium mining and processing; Ulba metallurgical plant, manufacturing fuel pellets of uranium dioxide for heat release assemblies of RBMK and WWR reactor types, with the enrichment on U235 1.6-4.4%; Power plant in Aktau for heat and power supply and water desalination, based on fast breeder reactor BN-350; Research reactors of National Nuclear Center: WWR-K - water-water reactor, with 10 MW power, uses highly enriched uranium (up to 36% of U-235); IVG.1M - water-water heterogeneous reactor of vessel type on thermal neutrons, maximum power is 35 MW; IGR - impulse homogeneous graphite reactor on thermal neutrons, with graphite reflector; RA - high temperature gas cooled reactor on thermal neutrons, 0.5 MW power. The establishment of design basis threats for nuclear objects in the Republic of Kazakhstan is an urgent problem because of the developing military-political situation in the region. It is necessary to specify important elements affecting the specific features of the design basis threat: military operations of

  10. Achieving IT-supported standardized nursing documentation through participatory design

    DEFF Research Database (Denmark)

    Rasmussen, Stine Loft; Lyng, Karen Marie; Jensen, Sanne

    2012-01-01

    that support guideline-based highly structured standard documentation in a large organization with many stakeholders. Applying a participatory design (PD) approach at many organizational levels has involved the stakeholders actively in the design process. Developing a set of design principles has concurrently...... made it possible to frame the discussions among the different stakeholders. Both PD and design principles have been instrumental in designing and implementing a set of standard templates that support the daily work and coordination between the nurses...

  11. Preliminary Evaluation Methodology of ECCS Performance for Design Basis LOCA Redefinition

    International Nuclear Information System (INIS)

    Kang, Dong Gu; Ahn, Seung Hoon; Seul, Kwang Won

    2010-01-01

    To improve their existing regulations, the USNRC has made efforts to develop the risk-informed and performance-based regulation (RIPBR) approaches. As a part of these efforts, the rule revision of 10CFR50.46 (ECCS Acceptance Criteria) is underway, considering some options for 4 categories of spectrum of break sizes, ECCS functional reliability, ECCS evaluation model, and ECCS acceptance criteria. Since the potential for safety benefits and unnecessary burden reduction from design basis LOCA redefinition is high relative to other options, the USNRC is proceeding with the rulemaking for design basis LOCA redefinition. An instantaneous break with a flow rate equivalent to a double ended guillotine break (DEGB) of the largest primary piping system in the plant is widely recognized as an extremely unlikely event, while redefinition of design basis LOCA can affect the existing regulatory practices and approaches. In this study, the status of the design basis LOCA redefinition and OECD/NEA SMAP (Safety Margin Action Plan) methodology are introduced. Preliminary evaluation methodology of ECCS performance for LOCA is developed and discussed for design basis LOCA redefinition

  12. 7 CFR 1717.605 - Design standards, plans and specifications, construction standards, and RUS accepted materials.

    Science.gov (United States)

    2010-01-01

    ..., construction standards, and RUS accepted materials. 1717.605 Section 1717.605 Agriculture Regulations of the... standards, plans and specifications, construction standards, and RUS accepted materials. All borrowers... system design, construction standards, and the use of RUS accepted materials. Borrowers must comply with...

  13. System Design for Navy Occupational Standards Development

    Science.gov (United States)

    2014-07-01

    need to increase access and visibility, reduce errors and approval times, institute administrative metrics, and standardize the occupational...considerable effort is devoted to ensuring that the grammatical style and form of tasks are consistent across tasks and among other rating OCCSTDs. Once the...reduced overhead and 12 complexity when writing queries for reports. This encapsulation of the data store also increases the portability and

  14. Simulation of a beyond design-basis-accident with RELAP5/MOD3.1

    Energy Technology Data Exchange (ETDEWEB)

    Banati, J. [Lappeenranta Univ. of Technology, Lappeenranta (Finland)

    1995-09-01

    This paper summarizes the results of analyses, parametric and sensitivity studies, performed using the RELAP5/MOD3.1 computer code for the 4th IAEA Standard Problem Exercise (SPE-4). The test, conducted on the PMK-2 facility in Budapest, involved simulation of a Small Break Loss Of Coolant Accident (SBLOCA) with a 7.4% break in the cold leg of a VVER-440 type pressurized water reactor. According to the scenario, the unavailability of the high pressure injection system led to a beyond design basis accident. For prevention of core damage, secondary side bleed-and-feed accident management measures were applied. A brief description of the PMK-2 integral type test facility is presented, together with the profile and some key phenomenological aspects of this particular experiment. Emphasis is placed on the ability of the code to predict the main trends observed in the test and thus, an assessment is given for the code capabilities to represent the system transient.

  15. Defense-in-depth approach against a beyond design basis event

    Energy Technology Data Exchange (ETDEWEB)

    Hoang, H., E-mail: Hoa.hoang@ge.com [GE Hitachi Nuclear Energy, 1989 Little Orchard St., 95125 San Jose, California (United States)

    2013-10-15

    The US industry, with the approval of the Nuclear Regulatory Commission, is promoting an approach to add diverse and flexible mitigation strategies, or Flex, that will increase the defense-in-depth capability for the nuclear power plants in the event of beyond design basis event, such as at the Fukushima Dai-ichi station. The objective of Flex is to establish and indefinite coping capability to prevent damage to the fuel in the core and spent fuel pool, and to maintain the containment function by utilizing installed equipment, on-site portable equipment and pre-staged off-site resources. This capability will address both an extended loss of all Ac power and a loss of ultimate heat sink which could arise following a design basis event with additional failures, and conditions from a beyond design basis event. (author)

  16. System 80+{trademark} Standard Design: CESSAR design certification. Volume 16: Amendment I

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-21

    This report, entitled Combustion Engineering Standard Safety Analysis Report - Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80+{trademark} Standard Design. This Volume 16 details the application of Human Factors Engineering in the design process.

  17. System 80+{trademark} Standard Design: CESSAR design certification. Volume 2: Amendment I

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-21

    This report, entitled Combustion Engineering Standard Safety Analysis Report - Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These documents describe the Combustion Engineering, Inc. System 80+{sup TM} Standard Design. This report, Volume 2, in conjunction with Volume 3, provides the design of structures, components, equipment and systems.

  18. System 80+{trademark} Standard Design: CESSAR design certification. Volume 4: Amendment I

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-21

    This report, entitled Combustion Engineering Standard Safety Analysis Report - Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These documents describe the Combustion Engineering, Inc. System 80+{sup TM} Standard Design. This report, Volume 4, provides a description of the reactor, reactor internals, fuel assemblies, and associated design requirements.

  19. State Skill Standards: Fashion, Textiles and Design

    Science.gov (United States)

    Campbell, Rene Crepaldi; Gaudy, Glenna; Green-Jobe, Victoria; Hatch, Susan; Moen, Julianne; Sheldon, Shannon; Smith, Loree; Chessell, Karen

    2008-01-01

    The mission of Fashion, Textiles and Design Education is to prepare students for family and community life and careers in the fashion industry by creating opportunities to develop the knowledge, skills, attitudes and behaviors needed to: (1) Examine skills needed to effectively manage clothing decisions; (2) Evaluate the use, care and production…

  20. Design Basis Threat (DBT) Approach for the First NPP Security System in Indonesia

    International Nuclear Information System (INIS)

    Ign Djoko Irianto

    2004-01-01

    Design Basis Threat (DBT) is one of the main factors to be taken into account in the design of physical protection system of nuclear facility. In accordance with IAEA's recommendations outlined in INFCIRC/225/Rev.4 (Corrected), DBT is defined as: attributes and characteristics of potential insider and/or external adversaries, who might attempt unauthorized removal of nuclear material or sabotage against the nuclear facilities. There are three types of adversary that must be considered in DBT, such as adversary who comes from the outside (external adversary), adversary who comes from the inside (internal adversary), and adversary who comes from outside and colludes with insiders. Current situation in Indonesia, where many bomb attacks occurred, requires serious attention on DBT in the physical protection design of NPP which is to be built in Indonesia. This paper is intended to describe the methodology on how to create and implement a Design Basis Threat in the design process of NPP physical protection in Indonesia. (author)

  1. Planning of designing and installation of mechanical elements at the gear speed reducer on the basis of the parameter technology

    Directory of Open Access Journals (Sweden)

    D. Letić

    2013-01-01

    Full Text Available The development and implementation of the computer methods at project managing in the part of the planning of designing and installation of mechanical elements with the fit (assembly block of the gear speed reducer is significant and at present irreplaceable engineering task if it has been realized by the modern parameter technology. There are multifunction uses of this organized group of activities, beginning from the quick changeability of elements still in the phase of designing and constructing, thanks to the characteristics of their associativity, still to the wide basis of standard elements that are incorporated in the very program package. Meanwhile, these activities are not simple, so their realization has to be planned from the stand - point of time, resource and cost of realization. For the very designing and constructing was used AutoCAD Mechanical, and for the design managing Microsoft Project.

  2. The System 80+ Standard Plant design control document. Volume 20

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains 2 technical specifications bases as part of Appendix 16 A Tech Spec Bases. They are TS B3.8 Electrical Power Technical Systems Bases and TS B3.9 Refueling Operations Bases. All 3 parts of section 17 (QA) and all 10 parts of section 18 (Human Factors) of the ADM Design and Analysis are contained in this volume. Topics covered in section 17 are: design phase QA; operations phase QA; and design phase reliability assurance. Topics covered by section 18 are: design team organization; design goals; design process; functional task analysis; control room configuration; information presentation; control and monitoring; verification and validation; and review documents

  3. Interior Design Standards in the Secondary FCS Curriculum

    Science.gov (United States)

    Katz, Shana H.; Smith, Bettye P.

    2006-01-01

    This article deals with a study on interior design standards in the secondary FCS curriculum. This study assessed the importance FCS teachers placed on content standards in the interior design curriculum to help determine the amount of time and emphasis to place on the units within the courses. A cover letter and questionnaire were sent…

  4. The System 80+ Standard Plant design control document. Volume 23

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains part 16 References and Appendix 19 A Design Alternatives for section 19 (Probabilistic Risk Assessment) of the ADM Design and Analysis. Also covered is section 20 Unresolved Safety Issues of the ADM Design and Analysis. Finally sections 1--6 of the ADM Emergency Operations Guidelines are contained in this volume. Information covered in these sections include: standard post-trip actions; diagnostic actions; reactor trip recovery guideline; LOCA recovery; SG tube rupture recovery

  5. Analysis of regulatory requirement for beyond design basis events of SMART

    International Nuclear Information System (INIS)

    Kim, W. S.; Seol, K. W.

    2000-01-01

    To enhance the safety of SMART reactor, safety and regulatory requirements associated with beyond design basis events (beyond BDE), which were developed and applied to advanced light water reactor designs, were analyzed along with a design status of passive reactor. And, based on these requirements, their applicability on the SMART design was evaluated. In the design aspect, severe accident prevention and mitigation features, containment performance, and accident management were analyzed. The evaluation results show that the requirement related to beyond DBE such as ATWS, loss of residual heat removal during shutdown operation, station blackout, fire, inter-system LOCA, and well-known events from severe accident phenomena is applicable to the SMART design. However, comprehensive approach against beyond DBE is not yet provided in the SMART design, and then it is required to designate and analyze the beyond DBE-related features. This study is expected to contribute to efforts to improve plant safety and to establish regulatory requirements for safety review

  6. Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America

    International Nuclear Information System (INIS)

    Prasad, Rajiv; Hibler, Lyle F.; Coleman, Andre M.; Ward, Duane L.

    2011-01-01

    The purpose of this document is to describe approaches and methods for estimation of the design-basis flood at nuclear power plant sites. Chapter 1 defines the design-basis flood and lists the U.S. Nuclear Regulatory Commission's (NRC) regulations that require estimation of the design-basis flood. For comparison, the design-basis flood estimation methods used by other Federal agencies are also described. A brief discussion of the recommendations of the International Atomic Energy Agency for estimation of the design-basis floods in its member States is also included.

  7. Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America

    Energy Technology Data Exchange (ETDEWEB)

    Prasad, Rajiv; Hibler, Lyle F.; Coleman, Andre M.; Ward, Duane L.

    2011-11-01

    The purpose of this document is to describe approaches and methods for estimation of the design-basis flood at nuclear power plant sites. Chapter 1 defines the design-basis flood and lists the U.S. Nuclear Regulatory Commission's (NRC) regulations that require estimation of the design-basis flood. For comparison, the design-basis flood estimation methods used by other Federal agencies are also described. A brief discussion of the recommendations of the International Atomic Energy Agency for estimation of the design-basis floods in its member States is also included.

  8. Grid fault and design-basis for wind turbines. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, A.D.; Cutululis, N.A.; Markou, H.; Soerensen, Poul; Iov, F.

    2010-01-15

    This is the final report of a Danish research project 'Grid fault and design-basis for wind turbines'. The objective of this project has been to assess and analyze the consequences of the new grid connection requirements for the fatigue and ultimate structural loads of wind turbines. The fulfillment of the grid connection requirements poses challenges for the design of both the electrical system and the mechanical structure of wind turbines. The development of wind turbine models and novel control strategies to fulfill the TSO's requirements are of vital importance in this design. Dynamic models and different fault ride-through control strategies have been developed and assessed in this project for three different wind turbine concepts (active stall wind turbine, variable speed doublyfed induction generator wind turbine, variable speed multipole permanent magnet wind turbine). A computer approach for the quantification of the wind turbines structural loads caused by the fault ride-through grid requirement, has been proposed and exemplified for the case of an active stall wind turbine. This approach relies on the combination of knowledge from complimentary simulation tools, which have expertise in different specialized design areas for wind turbines. In order to quantify the impact of the grid faults and grid requirements fulfillment on wind turbines structural loads and thus on their lifetime, a rainflow and a statistical analysis for fatigue and ultimate structural loads, respectively, have been performed and compared for two cases, i.e. one when the turbine is immediately disconnected from the grid when a grid fault occurs and one when the turbine is equipped with a fault ride-through controller and therefore it is able to remain connected to the grid during the grid fault. Different storm control strategies, that enable variable speed wind turbines to produce power at wind speeds higher than 25m/s and up to 50m/s without substantially increasing

  9. System 80+{trademark} standard design: CESSAR design certification. Volume 5: Amendment I

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-21

    This report has been prepared in support of the industry effort to standardize nuclear plant designs. The documents in this series describe the Combustion Engineering, Inc. System 80+{sup TM} Standard Design.

  10. Study on effective prestressing effects on concrete containment under the design-basis pressure condition

    International Nuclear Information System (INIS)

    Sun Feng; Pan Rong; Wang Lu; Mao Huan; Yang Yu

    2013-01-01

    Prestressing technology is widely used in nuclear power plant containment building, and the durability of containment structure is affected directly by the distribution and loss of prestressing value under design-basis pressure. Containment structure and the distribution of prestressing system are introduced briefly. Furthermore, the calculating process of horizontal prestressing bunch loss near the equipment hatch hole is put forward in details, and the containment structure prestressing loss when 5-year pressure test is obtained. Based above analysis, the finite element model of the prestressed concrete containment structure is built by using ANSYS code, the prestressing effect on concrete containment is analysed. The results show that most of the design pressure is bore by the prestressing system under the design-basis pressure, so the containment structure is safe. These conclusions are consistent with prestressing containment system design concepts, which can provide reference to the engineering staff. (authors)

  11. The power of simplification: Operator interface with the AP1000{sup R} during design-basis and beyond design-basis events

    Energy Technology Data Exchange (ETDEWEB)

    Williams, M. G.; Mouser, M. R.; Simon, J. B. [Westinghouse Electric Company, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2012-07-01

    The AP1000{sup R} plant is an 1100-MWe pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and cost. The passive safety features are designed to function without safety-grade support systems such as component cooling water, service water, compressed air or HVAC. The AP1000 passive safety features achieve and maintain safe shutdown in case of a design-basis accident for 72 hours without need for operator action, meeting the expectations provided in the European Utility Requirements and the Utility Requirement Document for passive plants. Limited operator actions may be required to maintain safe conditions in the spent fuel pool (SFP) via passive means. This safety approach therefore minimizes the reliance on operator action for accident mitigation, and this paper examines the operator interaction with the Human-System Interface (HSI) as the severity of an accident increases from an anticipated transient to a design basis accident and finally, to a beyond-design-basis event. The AP1000 Control Room design provides an extremely effective environment for addressing the first 72 hours of design-basis events and transients, providing ease of information dissemination and minimal reliance upon operator actions. Symptom-based procedures including Emergency Operating Procedures (EOPs), Abnormal Operating Procedures (AOPs) and Alarm Response Procedures (ARPs) are used to mitigate design basis transients and accidents. Use of the Computerized Procedure System (CPS) aids the operators during mitigation of the event. The CPS provides cues and direction to the operators as the event progresses. If the event becomes progressively worse or lasts longer than 72 hours, and depending upon the nature of failures that may have occurred, minimal operator actions may be required outside of the control room in areas that have been designed to be accessible using components that have been

  12. The power of simplification: Operator interface with the AP1000R during design-basis and beyond design-basis events

    International Nuclear Information System (INIS)

    Williams, M. G.; Mouser, M. R.; Simon, J. B.

    2012-01-01

    The AP1000 R plant is an 1100-MWe pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and cost. The passive safety features are designed to function without safety-grade support systems such as component cooling water, service water, compressed air or HVAC. The AP1000 passive safety features achieve and maintain safe shutdown in case of a design-basis accident for 72 hours without need for operator action, meeting the expectations provided in the European Utility Requirements and the Utility Requirement Document for passive plants. Limited operator actions may be required to maintain safe conditions in the spent fuel pool (SFP) via passive means. This safety approach therefore minimizes the reliance on operator action for accident mitigation, and this paper examines the operator interaction with the Human-System Interface (HSI) as the severity of an accident increases from an anticipated transient to a design basis accident and finally, to a beyond-design-basis event. The AP1000 Control Room design provides an extremely effective environment for addressing the first 72 hours of design-basis events and transients, providing ease of information dissemination and minimal reliance upon operator actions. Symptom-based procedures including Emergency Operating Procedures (EOPs), Abnormal Operating Procedures (AOPs) and Alarm Response Procedures (ARPs) are used to mitigate design basis transients and accidents. Use of the Computerized Procedure System (CPS) aids the operators during mitigation of the event. The CPS provides cues and direction to the operators as the event progresses. If the event becomes progressively worse or lasts longer than 72 hours, and depending upon the nature of failures that may have occurred, minimal operator actions may be required outside of the control room in areas that have been designed to be accessible using components that have been designed

  13. Reconfigurable Flight Control Design using a Robust Servo LQR and Radial Basis Function Neural Networks

    Science.gov (United States)

    Burken, John J.

    2005-01-01

    This viewgraph presentation reviews the use of a Robust Servo Linear Quadratic Regulator (LQR) and a Radial Basis Function (RBF) Neural Network in reconfigurable flight control designs in adaptation to a aircraft part failure. The method uses a robust LQR servomechanism design with model Reference adaptive control, and RBF neural networks. During the failure the LQR servomechanism behaved well, and using the neural networks improved the tracking.

  14. Radial basis function (RBF) neural network control for mechanical systems design, analysis and Matlab simulation

    CERN Document Server

    Liu, Jinkun

    2013-01-01

    Radial Basis Function (RBF) Neural Network Control for Mechanical Systems is motivated by the need for systematic design approaches to stable adaptive control system design using neural network approximation-based techniques. The main objectives of the book are to introduce the concrete design methods and MATLAB simulation of stable adaptive RBF neural control strategies. In this book, a broad range of implementable neural network control design methods for mechanical systems are presented, such as robot manipulators, inverted pendulums, single link flexible joint robots, motors, etc. Advanced neural network controller design methods and their stability analysis are explored. The book provides readers with the fundamentals of neural network control system design.   This book is intended for the researchers in the fields of neural adaptive control, mechanical systems, Matlab simulation, engineering design, robotics and automation. Jinkun Liu is a professor at Beijing University of Aeronautics and Astronauti...

  15. System 80+{trademark} Standard Design: CESSAR design certification. Volume 8: Amendment I

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-21

    This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80{sup +}{trademark} Standard Design. This volume 8 provides a description of instrumentation and controls.

  16. System 80+{trademark} Standard Design: CESSAR design certification. Volume 11: Amendment I

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-21

    This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80{sup +}{trademark} Standard Design. This volume 11 discusses Radiation Protection, Conduct of Operations, and the Initial Test Program.

  17. System 80+{trademark} Standard Design: CESSAR design certification. Volume 9: Amendment I

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-21

    This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80{sup +}{trademark} Standard Design. This volume 9 discusses Electric Power and Auxiliary Systems.

  18. NASA STD-4005: The LEO Spacecraft Charging Design Standard

    Science.gov (United States)

    Ferguson, Dale C.

    2006-01-01

    Power systems with voltages higher than about 55 volts may charge in Low Earth Orbit (LEO) enough to cause destructive arcing. The NASA STD-4005 LEO Spacecraft Charging Design Standard will help spacecraft designers prevent arcing and other deleterious effects on LEO spacecraft. The Appendices, an Information Handbook based on the popular LEO Spacecraft Charging Design Guidelines by Ferguson and Hillard, serve as a useful explanation and accompaniment to the Standard.

  19. The System 80+ Standard Plant design control document. Volume 16

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains all 3 parts of section 14 (Initial Test Program) of the ADM Design and Analysis. Topics covered are: PSAR information; FSAR information; certified design material. Also part 1 of section 15 (Accident Analysis) of the ADM Design and Analysis is included in this volume. The topic of part 1 is increase in heat removal

  20. Basis to demonstrate compliance with the National Emission Standards for Hazardous Air Pollutants for the Stand-off Experiments Range

    Energy Technology Data Exchange (ETDEWEB)

    Michael Sandvig

    2011-01-01

    The purpose of this report is to provide the basis and the documentation to demonstrate general compliance with the National Emission Standard for Hazardous Air Pollutants (NESHAPS) 40 CFR 61 Subpart H, “National Emission Standards for Emissions of Radionuclides Other Than Radon from Department of Energy Facilities,” (the Standard) for outdoor linear accelerator operations at the Idaho National Laboratory (INL) Stand-off Experiments Range (SOX). The intent of this report is to inform and gain acceptance of this methodology from the governmental bodies regulating the INL.

  1. The System 80+ Standard Plant design control document. Volume 15

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains all five parts of section 12 (Radiation Protection) of the ADM Design and Analysis. Topics covered are: ALARA exposures; radiation sources; radiation protection; dose assessment; and health physics program. All six parts and appendices A and B for section 13 (Conduct of Operations) of the ADM Design and Analysis are also contained in this volume. Topics covered are: organizational structure; training program; emergency planning; review and audit; plant procedures; industrial security; sabotage protection (App 13A); and vital equipment list (App 13B)

  2. 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...

  3. Design Basis Provisions for New and Existing Nuclear Power Plants and Nuclear Fuel Cycle Facilities in India

    International Nuclear Information System (INIS)

    Soni, R.S.

    2013-01-01

    India has 3-Stage Nuclear Power Program. • Various facilities under design, construction or operation. • Design Basis Knowledge Management (DBKM) is an important and challenging task. • Design Basis Knowledge contributes towards: - Safe operation of running plants; - Design and construction of new facilities; - Addresses issues related to future decommissioning activities

  4. The System 80+ Standard Plant design control document. Volume 21

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains parts 1--10 of section 19 (Probabilistic Risk Assessment) of the ADM Design and Analysis. Topics covered are: methodology; initiating event evaluation; accident sequence determination; data analysis; systems analysis; external events analysis; shutdown risk assessment; accident sequence quantification; and sensitivity analysis. Also included in this volume are Appendix 19.8A Shutdown Risk Assessment and Appendix A to Appendix 19.8A Request for Information

  5. The System 80+ Standard Plant design control document. Volume 11

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume covers parts 6 and 7 and appendix 7A for section 7 (Instrumentation and Control) of the ADM Design and Analysis. The topics covered by these are: other systems required for safety; control systems not required by safety; and CMF evaluation of limiting faults. Parts 1--3 of section 8 (Electric Power) of the ADM are also included in this volume. Topics covered by these parts are: introduction; offsite power system; and onsite power system

  6. The System 80+ Standard Plant design control document. Volume 24

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains sections 7--11 of the ADM Emergency Operations Guidelines. Topics covered are: excess steam demand recovery; loss of all feedwater; loss of offsite power; station blackout recovery; and functional recovery guideline. Appendix A Severe Accident Management Guidelines and Appendix B Lower Mode Operational Guidelines are also included

  7. Standardized surface engineering design of shale gas reservoirs

    Directory of Open Access Journals (Sweden)

    Guangchuan Liang

    2016-01-01

    Full Text Available Due to the special physical properties of shale gas reservoirs, it is necessary to adopt unconventional and standardized technologies for its surface engineering construction. In addition, the surface engineering design of shale gas reservoirs in China faces many difficulties, such as high uncertainty of the gathering and transportation scale, poor adaptability of pipe network and station layout, difficult matching of the process equipments, and boosting production at the late stage. In view of these problems, the surface engineering construction of shale gas reservoirs should follow the principles of “standardized design, modularized construction and skid mounted equipment”. In this paper, standardized surface engineering design technologies for shale gas reservoirs were developed with the “standardized well station layout, universal process, modular function zoning, skid mounted equipment selection, intensive site design, digitized production management” as the core, after literature analysis and technology exploration were carried out. Then its application background and surface technology route were discussed with a typical shale gas field in Sichuan–Chongqing area as an example. Its surface gathering system was designed in a standardized way, including standardized process, the modularized gathering and transportation station, serialized dehydration unit and intensive layout, and remarkable effects were achieved. A flexible, practical and reliable ground production system was built, and a series of standardized technology and modularized design were completed, including cluster well platform, set station, supporting projects. In this way, a system applicable to domestic shale gas surface engineering construction is developed.

  8. Design and industrial production of frequency standards in the USSR

    Science.gov (United States)

    Demidov, Nikolai A.; Uljanov, Adolph A.

    1990-01-01

    Some aspects of research development and production of quantum frequency standards, carried out in QUARTZ Research and Production Association (RPA), Gorky, U.S.S.R., were investigated for the last 25 to 30 years. During this period a number of rubidium and hydrogen frequency standards, based on the active maser, were developed and put into production. The first industrial model of a passive hydrogen maser was designed in the last years. Besides frequency standards for a wide application range, RPA QUARTZ investigates metrological frequency standards--cesium standards with cavity length 1.9 m and hydrogen masers with a flexible storage bulb.

  9. Analysis of Design Basis Events in a Preliminary Specific Design of PGSFR

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kwi Lim; Ha, Kwi Seok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    KAERI(Korea Atomic Energy Research Institute) has been developing a preliminary specific design of the PGSFR(Prototype Gen-IV Sodium-cooled Fast Reactor), which is a pool type sodium cooled fast reactor with a thermal power of 392.2 MW. Many alterations were made on a preliminary specific design of the PGSFR compared with a conceptual design: a heat removal capability of the DHRS was decreased, the DHXs were submerged in a cold pool, a pressure drop through the core was increased, and a shape of a redon was changed to a peanut type, etc. For identification of safety characteristics including the design changes, 5 DBE's(Design Bases Events) were analyzed using MARS-LMR code. The representative DBE's are TOP(Transient of Over Power), LOF(Loss Of Flow), LOHS(Loss Of Heat Sink), Reactor Vessel Leak and Pipe Break accidents. The representative DBE's were analyzed using the MARS-LMR code. As a result, it was identified that the PGSFR were appropriately tripped by the RPS(Reactor Protection System) and cooled by the DHRS. But a high cladding temperature was estimated in a pipe break accident. Therefore, integrity of the structure should be evaluated in the further study.

  10. Update of bridge design standards in Alabama for AASHTO LRFD seismic design requirements.

    Science.gov (United States)

    2013-11-01

    The Alabama Department of Transportation (ALDOT) has been required to update their bridge design to the LRFD Bridge Design Specifications. This transition has resulted in changes to the seismic design standards of bridges in the state. Multiple bridg...

  11. @tomic 2012 Seminar on Design Basis Threat for Cyber Attacks on the Nuclear Sector

    International Nuclear Information System (INIS)

    Schraver, M.

    2014-01-01

    On November 30, 2012 the Dutch National Coordinator for Security and Counter terrorism hosted the @tomic 2012 Seminar on Design Basis Threat for Cyber Attacks on the Nuclear Sector. A DBT is a comprehensive description of the motivation, intentions and capabilities of potential adversaries against which protection systems are designed and evaluated. The traditional DBT approach is based on a physical security perspective. It was proposed, however, that it can be modified to fit the cyber threat. The aim of the seminar was to identify possible approaches to developing a DBT ICT for the nuclear sector that takes into account the speed at which cyber tools and methods evolve. The seminar was attended by a select group of participants from government, academia and the nuclear industry. The seminar started with several presentations on the development of a DBT ICT by representatives from the Dutch National Coordinator for Security and Counter terrorism and the International Atomic Energy Agency (IAEA). The Ministry of Economic Affairs currently developing the Dutch DBT ICT, presented the Dutch approach and the current state of affairs. In addition, the keynote speech focused on the constant innovations within the cyber sector. To enable the discussion the participants took part in a red-blue team policy exercise to brainstorm about potential attacks, vulnerabilities and defensive measures. In the end the participants formulated five potential cases against which defensive measures should be in place. After the policy exercise, a discussion on the needs of a DBT ICT ensued. During the discussion various approaches were mentioned including; a scenario-based DBT (as in the exercise), protection requirements based on functional analysis of dependencies, vulnerabilities and interfaces, the adoption of existing requirements, and several combinations of these approaches; — The scenario-based approach requires the definition of reasonably likely modi operandi of attack on the

  12. Development of a design basis tornado and structural design criteria for Lawrence Livermore Laboratory's Site 300

    International Nuclear Information System (INIS)

    McDonald, J.R.; Minor, J.E.; Mehta, K.C.

    1975-11-01

    Criteria are prescribed and guidance is provided for professional personnel who are involved with the evaluation of existing buildings and facilities at Site 300 near Livermore, California to resist the possible effects of extreme winds and tornadoes. The development of parameters for the effects of tornadoes and extreme winds and guidelines for evaluation and design of structures are presented. The investigations conducted are summarized and the techniques used for arriving at the combined tornado and extreme wind risk model are discussed. The guidelines for structural design methods for calculating pressure distributions on walls and roofs of structures and methods for accommodating impact loads from missiles are also presented

  13. Rethinking Space Design Standards Toward Quality Affordable Housing In Malaysia

    Directory of Open Access Journals (Sweden)

    Ishak Nor Haniza

    2016-01-01

    Full Text Available Provision of affordable housing is important to low- and middle-income population. A fit form of house will not only fulfil a basic human need for shelter, but it also contributes to physical and psychological well-being of the occupants. Excellent quality and affordable housing is an indication of a high quality of life. While writings exist on various aspects of the quality of affordable housing in Malaysia, discussion regarding space and design standards has scarcely been given any serious academic attention. Standards concerning residential development usually cover different aspects or stages of the development process. They can include planning standards, design standards, space standards and technical construction standards. The main concern of this paper is on space and design standards specifically. Space standard can be defined as a set of framework which dictates fixed internal space minimums. Meanwhile, design standard indicates design guidelines to ensure the functionality, comfortability and habitability of the house. This paper is concerned exclusively with indoor spaces of a house excluding external circulation spaces and service facilities (in case of strata housing. Its interest is in internal space as an aspect of housing quality. It can be concluded that one of the way forward will be to find the balance between providing adequate minimum spaces for resident satisfactions and having economic values for housing developers. This paper may be used as a valuable reference for authorities and policy makers to better address the best housing space design standards that would benefit not only the occupants, but also the local government and developers alike.

  14. Computing tools for implementing standards for single-case designs.

    Science.gov (United States)

    Chen, Li-Ting; Peng, Chao-Ying Joanne; Chen, Ming-E

    2015-11-01

    In the single-case design (SCD) literature, five sets of standards have been formulated and distinguished: design standards, assessment standards, analysis standards, reporting standards, and research synthesis standards. This article reviews computing tools that can assist researchers and practitioners in meeting the analysis standards recommended by the What Works Clearinghouse: Procedures and Standards Handbook-the WWC standards. These tools consist of specialized web-based calculators or downloadable software for SCD data, and algorithms or programs written in Excel, SAS procedures, SPSS commands/Macros, or the R programming language. We aligned these tools with the WWC standards and evaluated them for accuracy and treatment of missing data, using two published data sets. All tools were tested to be accurate. When missing data were present, most tools either gave an error message or conducted analysis based on the available data. Only one program used a single imputation method. This article concludes with suggestions for an inclusive computing tool or environment, additional research on the treatment of missing data, and reasonable and flexible interpretations of the WWC standards. © The Author(s) 2015.

  15. Illinois Occupational Skill Standards: Information Technology Design/Build Cluster.

    Science.gov (United States)

    Illinois Occupational Skill Standards and Credentialing Council, Carbondale.

    This document contains Illinois Occupational Skill Standards for occupations in the Information Technology Design and Build Cluster (technical writer, programmer, system analyst, network architect, application product architect, network engineer, and database administrator). The skill standards define what an individual should know and the…

  16. Development and comparision of techniques for estimating design basis flood flows for nuclear power plants

    International Nuclear Information System (INIS)

    1980-05-01

    Estimation of the design basis flood for Nuclear Power Plants can be carried out using either deterministic or stochastic techniques. Stochastic techniques, while widely used for the solution of a variety of hydrological and other problems, have not been used to date (1980) in connection with the estimation of design basis flood for NPP siting. This study compares the two techniques against one specific river site (Galt on the Grand River, Ontario). The study concludes that both techniques lead to comparable results , but that stochastic techniques have the advantage of extracting maximum information from available data and presenting the results (flood flow) as a continuous function of probability together with estimation of confidence limits. (author)

  17. International standardization of nuclear reactor designs - the way forward

    International Nuclear Information System (INIS)

    Raetzke, Christian

    2010-01-01

    The concept of 'International Standardization of Nuclear Reactor Designs' means that vendors could build their designs in every country without having to adapt it specifically to national safety requirements. Such standardization would have two main effects. It would greatly facilitate nuclear new build worldwide by giving greater efficiency and certainty to the national licensing procedures; by taking into account the fact that vendors, and nowadays also utilities, are active across borders; by helping developing countries to establish their nuclear new build programmes; and by reducing the strain on human resources on both the regulators' and the industry's side. The second valuable effect of standardization would be to further enhance safety by improving the exchange of construction and operating experience among a number of reactors belonging to fleets of the same design. The World Nuclear Association's CORDEL (Cooperation in Reactor Design Evaluation and Licensing) Group has developed a concept for implementation of international standardization of reactor designs. It has defined a number of steps to be taken by industry. At the same time, possibilities offered by national and international regulatory mechanisms would have to be fully made use of, and some changes in regulatory frameworks might be necessary. Some steps especially towards greater cooperation of regulators have already been taken; however, much still remains to be done. The concept of deploying standardized reactor designs across a number of countries supposes an alignment and, if possible, harmonization of national safety standards; a streamlining of national licensing procedures, making them more efficient and predictable; and the willingness of national regulators to take into account licensing done in other countries. In the end, this should lead to a mutual acceptance of design approvals or, in a more distant future, even to a multinational design approval process. All in all, the concept

  18. Analysis on calculation of the maximum design basis accident with use of jet spray coolers

    International Nuclear Information System (INIS)

    Balashevskij, A.S.; Miroshnichenko, S.T.

    2012-01-01

    The paper provides results numerical simulation of a regular spray system, jet Spray Coolers, and their effect on pressure and temperature decrease in WWER containments in case of the maximum design basis accident. The RALAP5/mod3.4 and MELCOR 1.8.5 computer codes are used to determine the flow rates of steam-water mixture supplied to the containment in leaks

  19. Interregional Knowledge Management Workshop on Life Cycle Management of Design Basis Information. Issues, Challenges, Approaches

    International Nuclear Information System (INIS)

    Šula, Radek

    2013-01-01

    Introduction and objectives: • It is evident that the design basis area is from the point of view of knowledge sharing extremely complicated. • Time is changing and puts on us ever greater demands. • We have to analyze the near and remote surroundings and have to simplified the problem of knowledge sharing in that area. • I believe that it is graspable task for knowledge management and I will try to outline some possible context and approaches

  20. Ground motion following selection of SRS design basis earthquake and associated deterministic approach

    International Nuclear Information System (INIS)

    1991-03-01

    This report summarizes the results of a deterministic assessment of earthquake ground motions at the Savannah River Site (SRS). The purpose of this study is to assist the Environmental Sciences Section of the Savannah River Laboratory in reevaluating the design basis earthquake (DBE) ground motion at SRS during approaches defined in Appendix A to 10 CFR Part 100. This work is in support of the Seismic Engineering Section's Seismic Qualification Program for reactor restart

  1. Legislatation, standards and awareness of inclusive design in Denmark

    DEFF Research Database (Denmark)

    Colfelt, Solvej; Herriott, Richard

    This presents an overview of the design professions´response to government policies on accessibility and inclusive design. Architectural firms and industrial design firms have different levels of awareness and willingness to implement inclusive design and accessibility objectives. This is driven ...... in part by variation in standards and regulations between industry sectors. Interest groups apparently do not approach accessibility and design-inclusivity objectives in an orchestrated fashion and do not show an awareness of design a means to provide solution.......This presents an overview of the design professions´response to government policies on accessibility and inclusive design. Architectural firms and industrial design firms have different levels of awareness and willingness to implement inclusive design and accessibility objectives. This is driven...

  2. Seismic studies and design basis ground motion for nuclear power plant sites

    International Nuclear Information System (INIS)

    1990-01-01

    The safety guide provides the approaches to be adopted and methodology to be followed in deriving the seismic design parameters for nuclear power plant (NPP) sites. It outlines the procedure to be applied for seismic studies and design basis ground motion investigations of NPP sites. It provides guidelines to assess the suitability of the NPP site against seismically induced hazards. It also considers the aspects of mitigation of hazard due to seismically generated water waves and related floodings. Seismic instrumentation to be provided at the site is also discussed. (M.G.B.). 41 refs., 2 figs., t abs

  3. NEG and NIOSH basis for an occupational health standard: 2-diethylaminoethanol

    Energy Technology Data Exchange (ETDEWEB)

    Toren, K.

    1996-05-01

    Health effects associated with occupational exposure to 2-diethylaminoethanol (DEAE) were reviewed as part of the agreement between NIOSH and the Nordic Expert Group for Criteria Documentation of Health Risks from Chemicals to exchange information and expertise in the area of occupational safety and health to provide a scientific basis for the establishment of recommended occupational exposure limits. The occurrence, use, pharmacokinetics, toxicology, immunotoxicity and organ systems, mutagenic, genotoxic, carcinogenic, and reproductive effects of DEAE were reviewed. Three reports of clusters of cases associated with DEAE exposure were described, as were studies examining the dose response relationship of DEAE in humans and experimental animals.

  4. Knowledge about plant is basis for successful cultivation : new international standard handbook on plant physiology

    NARCIS (Netherlands)

    Esch, van H.; Heuvelink, E.; Kierkels, T.

    2015-01-01

    ‘Plant physiology in Greenhouses’ is the new international standard handbook on plant knowledge for the commercial greenhouse grower. It relates the functioning of the plant to the rapid developments in greenhouse cultivation. It is based on a continuing series of plant physiology articles published

  5. NEURO-SYSTEM OF AIMING AND STABILIZING WITH A REGULATOR ON THE BASIS OF STANDARD MODEL MODEL REFERENCE CONTROLLER

    Directory of Open Access Journals (Sweden)

    B.I. Kuznetsov

    2015-08-01

    Full Text Available The aim of this work is the synthesis of neural network aiming and stabilization system for the special equipment of moving objects with neuro-controller on the basis of standard model and performance comparison of the neural network system with the neural network predictive control. Build a block diagram of the neural network aiming and stabilization system, based on the subject control principle with PD-regulator in the position loop and with neuro-controller on the basis of standard model in the in the velocity loop. The neuro-controller on the basis of standard model Model Reference Controller is synthesized in the MATLAB Neural Network Toolbox and system simulation is performed. The studies show that the transient state variables of the system are oscillatory. Therefore, the neuro-controller with the prediction NN Predictive Controller should be used for aiming and stabilizing system to provide high dynamic characteristics achieved at the cost of higher complexity and computational cost.

  6. Characterisation of Liquefaction Effects for Beyond-Design Basis Safety Assessment of Nuclear Power Plants

    Science.gov (United States)

    Bán, Zoltán; Győri, Erzsébet; János Katona, Tamás; Tóth, László

    2015-04-01

    Preparedness of nuclear power plants to beyond design base external effects became high importance after 11th of March 2011 Great Tohoku Earthquakes. In case of some nuclear power plants constructed at the soft soil sites, liquefaction should be considered as a beyond design basis hazard. The consequences of liquefaction have to be analysed with the aim of definition of post-event plant condition, identification of plant vulnerabilities and planning the necessary measures for accident management. In the paper, the methodology of the analysis of liquefaction effects for nuclear power plants is outlined. The case of Nuclear Power Plant at Paks, Hungary is used as an example for demonstration of practical importance of the presented results and considerations. Contrary to the design, conservatism of the methodology for the evaluation of beyond design basis liquefaction effects for an operating plant has to be limited to a reasonable level. Consequently, applicability of all existing methods has to be considered for the best estimation. The adequacy and conclusiveness of the results is mainly limited by the epistemic uncertainty of the methods used for liquefaction hazard definition and definition of engineering parameters characterizing the consequences of liquefaction. The methods have to comply with controversial requirements. They have to be consistent and widely accepted and used in the practice. They have to be based on the comprehensive database. They have to provide basis for the evaluation of dominating engineering parameters that control the post-liquefaction response of the plant structures. Experience of Kashiwazaki-Kariwa plant hit by Niigata-ken Chuetsu-oki earthquake of 16 July 2007 and analysis of site conditions and plant layout at Paks plant have shown that the differential settlement is found to be the dominating effect in case considered. They have to be based on the probabilistic seismic hazard assessment and allow the integration into logic

  7. Renewable Electricity Standards: Good Practices and Design Considerations

    Energy Technology Data Exchange (ETDEWEB)

    Cox, Sadie [National Renewable Energy Lab. (NREL), Golden, CO (United States); Esterly, Sean [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2016-01-02

    In widespread use globally, renewable electricity standards (RES) are one of the most widely adopted renewable energy policies and a critical regulatory vehicle to accelerate renewable energy deployment. This policy brief provides an introduction to key RES design elements, lessons from country experience, and support resources to enable more detailed and country-specific RES policy design.

  8. Using the IMS LD Standard to Describe Learning Designs

    NARCIS (Netherlands)

    Koper, Rob; Miao, Yongwu

    2007-01-01

    Koper, R., & Miao, Y. (2008). Using the IMS LD Standard to Describe Learning Designs. In L. Lockyer, S. Bennet, S. Agostinho & B. Harper (Eds.), Handbook of Research on Learning Design and Learning Objects: Issues, Applications and Technologies (pp. 41-86). IDEA group.

  9. KIT multi-physics tools for the analysis of design and beyond design basis accidents of light water reactors

    International Nuclear Information System (INIS)

    Sanchez, Victor Hugo; Miassoedov, Alexei; Steinbrueck, M.; Tromm, W.

    2016-01-01

    This paper describes the KIT numerical simulation tools under extension and validation for the analysis of design and beyond design basis accidents (DBA) of Light Water Reactors (LWR). The description of the complex thermal hydraulic, neutron kinetics and chemo-physical phenomena going on during off-normal conditions requires the development of multi-physics and multi-scale simulations tools which are fostered by the rapid increase in computer power nowadays. The KIT numerical tools for DBA and beyond DBA are validated using experimental data of KIT or from abroad. The developments, extensions, coupling approaches and validation work performed at KIT are shortly outlined and discussed in this paper.

  10. KIT multi-physics tools for the analysis of design and beyond design basis accidents of light water reactors

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, Victor Hugo; Miassoedov, Alexei; Steinbrueck, M.; Tromm, W. [Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen (Germany)

    2016-05-15

    This paper describes the KIT numerical simulation tools under extension and validation for the analysis of design and beyond design basis accidents (DBA) of Light Water Reactors (LWR). The description of the complex thermal hydraulic, neutron kinetics and chemo-physical phenomena going on during off-normal conditions requires the development of multi-physics and multi-scale simulations tools which are fostered by the rapid increase in computer power nowadays. The KIT numerical tools for DBA and beyond DBA are validated using experimental data of KIT or from abroad. The developments, extensions, coupling approaches and validation work performed at KIT are shortly outlined and discussed in this paper.

  11. Breckinridge Project, initial effort. Report XI, Volume V. Critical review of the design basis. [Critical review

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-01-01

    Report XI, Technical Audit, is a compendium of research material used during the Initial Effort in making engineering comparisons and decisions. Volumes 4 and 5 of Report XI present those studies which provide a Critical Review of the Design Basis. The Critical Review Report, prepared by Intercontinental Econergy Associates, Inc., summarizes findings from an extensive review of the data base for the H-Coal process design. Volume 4 presents this review and assessment, and includes supporting material; specifically, Design Data Tabulation (Appendix A), Process Flow Sheets (Appendix B), and References (Appendix C). Volume 5 is a continuation of the references of Appendix C. Studies of a proprietary nature are noted and referenced, but are not included in these volumes. They are included in the Limited Access versions of these reports and may be reviewed by properly cleared personnel in the offices of Ashland Synthetic Fuels, Inc.

  12. Breckinridge Project, initial effort. Report XI, Volume IV. Critical review of the design basis. [Critical review

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-05-01

    Report XI, Technical Audit, is a compendium of research material used during the Initial Effort in making engineering comparisons and decisions. Volumes 4 and 5 of Report XI present those studies which provide a Critical Review of the Design Basis. The Critical Review Report, prepared by Intercontinental Econergy Associates, Inc., summarizes findings from an extensive review of the data base for the H-Coal process design. Volume 4 presents this review and assessment, and includes supporting material; specifically, Design Data Tabulation (Appendix A), Process Flow Sheets (Appendix B), and References (Appendix C). Volume 5 is a continuation of the references of Appendix C. Studies of a proprietary nature are noted and referenced, but are not included in these volumes. They are included in the Limited Access versions of these reports and may be reviewed by properly cleared personnel in the offices of Ashland Synthetic Fuels, Inc.

  13. Grid fault and design-basis for wind turbines - Final report

    DEFF Research Database (Denmark)

    Hansen, Anca Daniela; Cutululis, Nicolaos Antonio; Markou, Helen

    This is the final report of a Danish research project “Grid fault and design-basis for wind turbines”. The objective of this project has been to assess and analyze the consequences of the new grid connection requirements for the fatigue and ultimate structural loads of wind turbines....... The fulfillment of the grid connection requirements poses challenges for the design of both the electrical system and the mechanical structure of wind turbines. The development of wind turbine models and novel control strategies to fulfill the TSO’s requirements are of vital importance in this design. Dynamic...... approach for the quantification of the wind turbines structural loads caused by the fault ride-through grid requirement, has been proposed and exemplified for the case of an active stall wind turbine. This approach relies on the combination of knowledge from complimentary simulation tools, which have...

  14. Impact of chemistry on Standard High Solids Vessel Design mixing

    Energy Technology Data Exchange (ETDEWEB)

    Poirier, M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-03-02

    The plan for resolving technical issues regarding mixing performance within vessels of the Hanford Waste Treatment Plant Pretreatment Facility directs a chemical impact study to be performed. The vessels involved are those that will process higher (e.g., 5 wt % or more) concentrations of solids. The mixing equipment design for these vessels includes both pulse jet mixers (PJM) and air spargers. This study assesses the impact of feed chemistry on the effectiveness of PJM mixing in the Standard High Solids Vessel Design (SHSVD). The overall purpose of this study is to complement the Properties that Matter document in helping to establish an acceptable physical simulant for full-scale testing. The specific objectives for this study are (1) to identify the relevant properties and behavior of the in-process tank waste that control the performance of the system being tested, (2) to assess the solubility limits of key components that are likely to precipitate or crystallize due to PJM and sparger interaction with the waste feeds, (3) to evaluate the impact of waste chemistry on rheology and agglomeration, (4) to assess the impact of temperature on rheology and agglomeration, (5) to assess the impact of organic compounds on PJM mixing, and (6) to provide the technical basis for using a physical-rheological simulant rather than a physical-rheological-chemical simulant for full-scale vessel testing. Among the conclusions reached are the following: The primary impact of precipitation or crystallization of salts due to interactions between PJMs or spargers and waste feeds is to increase the insoluble solids concentration in the slurries, which will increase the slurry yield stress. Slurry yield stress is a function of pH, ionic strength, insoluble solids concentration, and particle size. Ionic strength and chemical composition can affect particle size. Changes in temperature can affect SHSVD mixing through its effect on properties such as viscosity, yield stress, solubility

  15. Differences in safety margins between nuclear and conventional design standards with regards to seismic hazard definition and design criteria

    International Nuclear Information System (INIS)

    Elgohary, M.; Saudy, A.; Orbovic, N.; Dejan, D.

    2006-01-01

    With the surging interest in new build nuclear all over the world and a permanent interest in earthquake resistance of nuclear plants, there is a need to quantify the safety margins in nuclear buildings design in comparison to conventional buildings in order to increase the public confidence in the safety of nuclear power plants. Nuclear (CAN3-N289 series) and conventional (NBCC 2005) seismic standards have different approaches regarding the design of civil structures. The origin of the differences lays in the safety philosophy behind the seismic nuclear and conventional standards. Conventional seismic codes contain the minimal requirement destined primarily to safeguard against major structural failure and loss of life. It doesn't limit damage to a certain acceptable degree or maintain function. Nuclear seismic code requires that structures, systems and components important to safety, withstand the effects of earthquakes. The requirement states that for equipment important to safety, both integrity and functionality should be ascertained. The seismic hazard is generally defined on the basis of the annual probability of exceedence (return period). There is a major difference on the return period and the confidence level for design earthquakes between the conventional and the nuclear seismic standards. The seismic design criteria of conventional structures are based on the use of Force Modification Factors to take into account the energy dissipation by incursion in non-elastic domain and the reserve of strength. The use of such factors to lower intentionally the seismic input is consistent with the safety philosophy of the conventional seismic standard which is the 'non collapse' rather than the integrity and/or the operability of the structures or components. Nuclear seismic standard requires that the structure remain in the elastic domain; energy dissipation by incursion in non-elastic domain is not allowed for design basis earthquake conditions. This is

  16. Designing the Information Literacy Competency Standards for nursing.

    Science.gov (United States)

    Phelps, Sue F

    2013-01-01

    This column documents the rationale for creating information literacy competency standards for nursing based on the Association of College and Research Libraries (ACRL) "Information Literacy Competency Standards for Higher Education" and the three documents from the American Association of Colleges of Nursing (AACN) on essential skills for nurses in baccalaureate, masters, and doctoral level education and practice. It chronicles the process of the task force which is designing the discipline specific skills and predicts the value of their use, once they are published.

  17. A cliff edge evaluation for CANDU-6 beyond design basis accidents

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S.M.; Kho, D.W., E-mail: wolsong@khnp.co.kr [Korea Hydro and Nuclear Power Co., Ltd., Daejeon (Korea, Republic of); Yi, S.D.; Kang, S.H.; Kim, S.R. [Nuclear Engineering Service and Solution Co., Ltd., Daejeon (Korea, Republic of)

    2015-07-01

    The condition of nuclear power plant in the event of station black out (SBO) accompanying large-scale natural disaster exceeding design basis accident (DBA) was evaluated. Additional scenarios were added to the evaluation to review capability of the plant to endure different conditions with different actions. The analysis resulted that the key action required from the operator was to ensure the opening of main steam safety valves (MSSVs) in the secondary side and of motor-operated valves for high pressure injection of Emergency Core Cooling System (HPECCS) to mitigate accidents or extend the cliff edge. (author)

  18. Environmental conditions using thermal-hydraulics computer code GOTHIC for beyond design basis external events

    International Nuclear Information System (INIS)

    Pleskunas, R.J.

    2015-01-01

    In response to the Fukushima Dai-ichi beyond design basis accident in March 2011, the Nuclear Regulatory Commission (NRC) issued Order EA-12-049, 'Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies Beyond-Design-Basis-External-Events'. To outline the process to be used by individual licensees to define and implement site-specific diverse and flexible mitigation strategies (FLEX) that reduce the risks associated with beyond design basis conditions, Nuclear Energy Institute document NEI 12-06, 'Diverse and Flexible Coping Strategies (FLEX) Implementation Guide', was issued. A beyond design basis external event (BDBEE) is postulated to cause an Extended Loss of AC Power (ELAP), which will result in a loss of ventilation which has the potential to impact room habitability and equipment operability. During the ELAP, portable FLEX equipment will be used to achieve and maintain safe shutdown, and only a minimal set of instruments and controls will be available. Given these circumstances, analysis is required to determine the environmental conditions in several vital areas of the Nuclear Power Plant. The BDBEE mitigating strategies require certain room environments to be maintained such that they can support the occupancy of personnel and the functionality of equipment located therein, which is required to support the strategies associated with compliance to NRC Order EA-12-049. Three thermal-hydraulic analyses of vital areas during an extended loss of AC power using the GOTHIC computer code will be presented: 1) Safety-related pump and instrument room transient analysis; 2) Control Room transient analysis; and 3) Auxiliary/Control Building transient analysis. GOTHIC (Generation of Thermal-Hydraulic Information for Containment) is a general purpose thermal-hydraulics software package for the analysis of nuclear power plant containments, confinement buildings, and system components. It is a volume/path/heat sink

  19. Analysis of Partial Factors for New EN 1990 Basis of Design

    Directory of Open Access Journals (Sweden)

    Marková Jana

    2017-06-01

    Full Text Available Presently the new generation of Eurocodes is under development. It is expected that the basis of structural design given in current EN 1990 will be considerably revised including the format for load combinations in the Ultimate Limit States and new categorisation of consequence classes for construction works. It is expected that the partial factors for self-weight of structural members could be reduced and factors for variable loads more differentiated. Calibration of partial factors should be performed for actions and materials including also structural glass and FRP polymers.

  20. Fusion reactor design studies: standard accounts for cost estimates

    International Nuclear Information System (INIS)

    Schulte, S.C.; Willke, T.L.; Young, J.R.

    1978-05-01

    The fusion reactor design studies--standard accounts for cost estimates provides a common format from which to assess the economic character of magnetically confined fusion reactor design concepts. The format will aid designers in the preparation of design concept costs estimates and also provide policymakers with a tool to assist in appraising which design concept may be economically promising. The format sets forth a categorization and accounting procedure to be used when estimating fusion reactor busbar energy cost that can be easily and consistently applied. Reasons for developing the procedure, explanations of the procedure, justifications for assumptions made in the procedure, and the applicability of the procedure are described in this document. Adherence to the format when evaluating prospective fusion reactor design concepts will result in the identification of the more promising design concepts thus enabling the fusion power alternatives with better economic potential to be quickly and efficiently developed

  1. System 80+{trademark} standard design incorporates radiation protection lessons learned

    Energy Technology Data Exchange (ETDEWEB)

    Crom, T.D.; Naugle, C.L. [Duke Engineering & Services, Inc., Charlotte, NC (United States); Turk, R.S. [ABB Combustion Engineering Nuclear Power, Windsor, CT (United States)

    1995-03-01

    Many lessons have been learned from the current generation of nuclear plants in the area of radiation protection. The following paper will outline how the lessons learned have been incorporated into the design and operational philosophy of the System 80+{trademark} Standard Design currently under development by ABB Combustion Engineering (ABB-CE) with support from Duke Engineering and Services, Inc. and Stone and Webster Engineering Corporation in the Balance-of-Plant design. The System 80+{trademark} Standard Design is a complete nuclear power plant for national and international markets, designed in direct response to utility needs for the 1990`s, and scheduled for Nuclear Regulatory Commission (NRC) Design Certification under the new standardization rule (10 CFR Part 52). System 80+{trademark} is a natural extension of System 80{sup R} technology, an evolutionary change based on proven Nuclear Steam Supply System (NSSS) in operation at Palo Verde in Arizona and under construction at Yonggwang in the Republic of Korea. The System 80+{trademark} Containment and much of the Balance of Plant design is based upon Duke Power Company`s Cherokee Plant, which was partially constructed in the late 1970`s, but, was later canceled (due to rapid declined in electrical load growth). The System 80+{trademark} Standard Design meets the requirements given in the Electric Power Research Institute (EPRI) Advanced Light Water Reactor (ALWR) Requirements Document. One of these requirements is to limit the occupational exposure to 100 person-rem/yr. This paper illustrates how this goal can be achieved through the incorporation of lessons learned, innovative design, and the implementation of a common sense approach to operation and maintenances practices.

  2. Designing Raster Cells as the Basis for Developing Personal Graphic Language

    Directory of Open Access Journals (Sweden)

    Jana Z. Vujić

    2011-05-01

    Full Text Available Continuous work in creating new designer solutions points towards the need to create personal routines as personalcommunication in the relation comprising design, algorithms, and original computer graphics. This paper showsprocedures for developing a control language for creating graphic designs with individual raster elements (screeningelement obtaint by halftoning. Personal commands should set routines in a language understood by the printer andthe designer. The PostScript basis is used because we mix vector and pixel graphics in the same program stream, aswell as different colour systems, and our own raster forms. The printing raster is set with the target of special designmulti-use, and this includes the field of security graphics and art computer reproduction. Each raster form assumesmodifications, creating their raster family. The raster cell content is transformed with PostScript, allowing the settingof basic values, angle and liniature for each pixel separately. Raster cells are mixed in multi-colour graphics to thelevel of individual designs with variable values of parameters determining them.

  3. Cost analysis of a commercial pyroprocess facility on the basis of a conceptual design in Korea

    International Nuclear Information System (INIS)

    Kim, S.K.; Ko, W.I.; Youn, S.R.; Gao, Ruxing

    2015-01-01

    Highlights: • Pyroprocess facility’s direct cost was calculated based on the conceptual design. • The unit cost of pyroprocess was calculated as $781/kgHM. • The unit cost was increased by 3%, considering labor allocation standards. • The operating and maintenance cost was identified as a main cost driver. - Abstract: This study postulated a commercial pyroprocess facility (KAPF+: Korea Advanced Pyroprocess Facility Plus) with a processing capacity of 400 tons/year as a cost object, and utilized an engineering cost estimation method based on a conceptual design to present the results of the total cost and unit cost estimation. According to the calculation results, the total cost and unit cost were calculated with k$779,386 and $781/kgHM, respectively. Moreover, the key cost driver was manifested as the operating and maintenance costs. In particular, equipment replacement cost was identified as an important cost driver. In addition, for an increasingly accurate cost estimation, the calculation results and allocation method of the indirect cost were reanalyzed. Finally the pyroprocess unit cost increased $5 when calculated the indirect cost using the labor time as the allocation standard. Meanwhile, the pyroprocess unit cost increased $22 as a result of allocating the indirect cost using the uniform labor cost as the cost allocation standard. Accordingly, an indirect cost allocation standard was manifested as the factor that exerts a significant effect on the pyroprocess unit cost

  4. Development, improvement and calibration of neutronic reaction rates measurements: elaboration of a standard techniques basis

    International Nuclear Information System (INIS)

    Hudelot, J.P.

    1998-06-01

    In order to improve and to validate the neutronics calculation schemes, perfecting integral measurements of neutronics parameters is necessary. This thesis focuses on the conception, the improvement and the development of neutronics reaction rates measurements, and aims at building a base of standard techniques. Two subjects are discussed. The first one deals with direct measurements by fission chambers. A short presentation of the different usual techniques is given. Then, those last ones are applied through the example of doubling time measurements on the EOLE facility during the MISTRAL 1 experimental programme. Two calibration devices of fission chambers are developed: a thermal column located in the central part of the MINERVE facility, and a calibration cell using a pulsed high flux neutron generator and based on the discrimination of the energy of the neutrons with a time-of-flight method. This second device will soon allow to measure the mass of fission chambers with a precision of about 1 %. Finally, the necessity of those calibrations will be shown through spectral indices measurements in core MISTRAL 1 (UO 2 ) and MISTRAL 2 (MOX) of the EOLE facility. In each case, the associated calculation schemes, performed using the Monte Carlo MCNP code with the ENDF-BV library, will be validated. Concerning the second one, the goal is to develop a method for measuring the modified conversion ratio of 238 U (defined as the ratio of 238 U capture rate to total fission rate) by gamma-ray spectrometry of fuel rods. Within the framework of the MISTRAL 1 and MISTRAL 2 programmes, the measurement device, the experimental results and the spectrometer calibration are described. Furthermore, the MCNP calculations of neutron self-shielding and gamma self-absorption are validated. It is finally shown that measurement uncertainties are better than 1 %. The extension of this technique to future modified conversion ratio measurements for 242 Pu (on MOX rods) and 232 Th (on

  5. Safety effects of road design standards in Europe.

    NARCIS (Netherlands)

    Wegman, F.C.M. & Slop, M.

    2003-01-01

    This paper deals with the result of a study carried out for the European Commission by the SWOV Institute for Road Safety Research, in cooperation with a number of other European institutes, and which was reported in 1994. The title of the study is "Safety Effects of Road Design Standards." The aims

  6. Design Standardized Web-Components for e-Learning

    OpenAIRE

    Belonogov, Andrey

    2007-01-01

    In this paper a flexible approach to design LMS with QTI Ready component based on the e-Learning standards AICC and IMS QTI is described. This system and component permits a dynamic learning and assessment process. QTI Ready component can provide these facilities to other real world virtual learning management system.

  7. Approaching standard by designing a basic safety function

    OpenAIRE

    Baudoin , James; Bello , Jean-Paul

    2014-01-01

    This document is intended to guide designers to perform machinery control systems with only one or a few "basic safety functions such as emergency stop or movable guard.Among the available standards for machinery design, EN ISO 13849-1 is the one providing recommendations to design safety related parts of control systems (SRP/CS) implementing different types of energy such as electric, hydraulic or pneumatic.This document is based on the implementation of the simplified method of EN ISO 13849...

  8. Screen Speed Designations: A Need For Standardization And Some Suggestions

    Science.gov (United States)

    Zweig, Gilbert

    1981-07-01

    Anyone who has tried to interchange different intensifying screens for a given procedure while maintaining consistent image density, appreciates the problem resulting from the lack of standardized screen speed designations. The problem has resulted, in part, from the variety of product names which we manufactur-ers have coined for our screens to establish screen brand identity and differentiation. These names, in most cases, give no indication of relative screen speed. Presently, there are no standard measuring procedures which the radiographer can use for routinely determining screen speed. The greater non-linear KVp response of the rare-earth phosphors, in fact, makes the use of single number designations deceptive. Different methods for designating screen speeds will be examined and a technique for transposing between different screens will be discussed.

  9. Design Performance Standards for Large Scale Wind Farms

    DEFF Research Database (Denmark)

    Gordon, Mark

    2009-01-01

    This document presents, discusses and provides a general guide on electrical performance standard requirements for connection of large scale onshore wind farms into HV transmission networks. Experiences presented here refer mainly to technical requirements and issues encountered during the process...... of connection into the Eastern Australian power system under the Rules and guidelines set out by AEMC and NEMMCO (AEMO). Where applicable some international practices are also mentioned. Standards are designed to serve as a technical envelope under which wind farm proponents design the plant and maintain...... ongoing technical compliance of the plant during its operational lifetime. This report is designed to provide general technical information for the wind farm connection engineer to be aware of during the process of connection, registration and operation of wind power plants interconnected into the HV TSO...

  10. A basis for designing digital library maturity model: Meta-synthesis method application

    Directory of Open Access Journals (Sweden)

    Fatemeh Sheikhshoaei

    2017-06-01

    Full Text Available Digital Library (DL development is faced with many challenges which cannot be overcome all at once. In such cases which are so complex, maturity models are utilized. In a maturity model, features of a phenomenon are classified into few levels so that improving or realizing the features of each level is the prerequisite of going to the next level. DL can also be approached by maturity model more efficiently and effectively. Since the maturity model for DL has not been designed yet, first, a literature review of the DL and maturity models using a qualitative approach and meta-synthesis method was done. According to the findings of the literature review, the maturity characteristics of DL are proposed to be a basis for designing DL maturity model. Since the concept of maturity and DL is extensive and has several dimensions, meta-synthesis has been found as a suitable method for comprehensive integration of the models offered in other areas with the existing literature in the field of DL based on their interpretation. To do so, 68 papers (38 in the field of DL and 30 in the field of maturity models in various fields were selected from the available resources. By analyzing these papers, three categories, seven concepts, and 35 codes obtained as DL maturity features. Among these findings, the focuses of previous studies have been on the use of software/ hardware systems as supporter and enabler of DL and the DL content. The found features, in addition to be a basis for designing of digital library model, can be a tool in the hands of project managers of DL for assessing the status of their projects and planning to achieve higher levels of maturity.

  11. SNL/CA Facilities Management Design Standards Manual

    Energy Technology Data Exchange (ETDEWEB)

    Rabb, David [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Clark, Eva [Sandia National Lab. (SNL-CA), Livermore, CA (United States)

    2014-12-01

    At Sandia National Laboratories in California (SNL/CA), the design, construction, operation, and maintenance of facilities is guided by industry standards, a graded approach, and the systematic analysis of life cycle benefits received for costs incurred. The design of the physical plant must ensure that the facilities are "fit for use," and provide conditions that effectively, efficiently, and safely support current and future mission needs. In addition, SNL/CA applies sustainable design principles, using an integrated whole-building design approach, from site planning to facility design, construction, and operation to ensure building resource efficiency and the health and productivity of occupants. The safety and health of the workforce and the public, any possible effects on the environment, and compliance with building codes take precedence over project issues, such as performance, cost, and schedule.

  12. 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

  13. Design Methodology of a New Wavelet Basis Function for Fetal Phonocardiographic Signals

    Science.gov (United States)

    Chourasia, Vijay S.; Tiwari, Anil Kumar

    2013-01-01

    Fetal phonocardiography (fPCG) based antenatal care system is economical and has a potential to use for long-term monitoring due to noninvasive nature of the system. The main limitation of this technique is that noise gets superimposed on the useful signal during its acquisition and transmission. Conventional filtering may result into loss of valuable diagnostic information from these signals. This calls for a robust, versatile, and adaptable denoising method applicable in different operative circumstances. In this work, a novel algorithm based on wavelet transform has been developed for denoising of fPCG signals. Successful implementation of wavelet theory in denoising is heavily dependent on selection of suitable wavelet basis function. This work introduces a new mother wavelet basis function for denoising of fPCG signals. The performance of newly developed wavelet is found to be better when compared with the existing wavelets. For this purpose, a two-channel filter bank, based on characteristics of fPCG signal, is designed. The resultant denoised fPCG signals retain the important diagnostic information contained in the original fPCG signal. PMID:23766693

  14. Standardization of green building technologies for environment design

    Directory of Open Access Journals (Sweden)

    Benuzh Andrey

    2016-01-01

    Full Text Available The article describes the structure and field of standardization ISO / TC 205 “Building environment design”, provides examples of green building technologies. The main purpose of the article is to show the interaction between international ISO / TC 205 “Building environment design” and created in Russia in 2016 the Technical Committee of Standardization № 366 “Green technology of the build environment and green innovative products”. Both of these technical committees promote green building technologies for environment design, thereby deal with the negative impact on the environment and the reasons of global warming. Instead of buildings that attempt to suppress and overcome nature, why not design buildings that integrate with the environment, on every possible level? The international standardization work which ISO/TC 205 “Building environment design” performs seeks, in addition to lowering trade barriers for engineering design, to promote and facilitate the design of high performance buildings: higher performing as economic assets for their owners, higher performing as buildings that provide amenable indoor environment for their occupants, and higher performing with respect to resource utilization and environmental impact.

  15. Criteria for calculating the efficiency of HEPA filters during and after design basis accidents

    International Nuclear Information System (INIS)

    Bergman, W.; First, M.W.; Anderson, W.L.; Gilbert, H.; Jacox, J.W.

    1994-12-01

    We have reviewed the literature on the performance of high efficiency particulate air (HEPA) filters under normal and abnormal conditions to establish criteria for calculating the efficiency of HEPA filters in a DOE nonreactor nuclear facility during and after a Design Basis Accident (DBA). The literature review included the performance of new filters and parameters that may cause deterioration in the filter performance such as filter age, radiation, corrosive chemicals, seismic and rough handling, high temperature, moisture, particle clogging, high air flow and pressure pulses. The deterioration of the filter efficiency depends on the exposure parameters; in severe exposure conditions the filter will be structurally damaged and have a residual efficiency of 0%. Despite the many studies on HEPA filter performance under adverse conditions, there are large gaps and limitations in the data that introduce significant error in the estimates of HEPA filter efficiencies under DBA conditions. Because of this limitation, conservative values of filter efficiency were chosen when there was insufficient data

  16. Design Basis Knowledge Management for New Build Projects & Ageing Plants - A Perspective

    International Nuclear Information System (INIS)

    Weightman, Mike

    2013-01-01

    Summary: • KM for Design Basis of New and Ageing nuclear facilities is at a crossroads; • Needs leadership, vision, cultural change and resources; • Outcome of this workshop is vital; • Information is not knowledge; • Knowledge includes the WHAT, the HOW, the WHY, the Environment and, importantly, Application; • In general, Industry and Regulators are behind the curve; • Develop and apply the principles rigorously; • Keep it simple - focus first on Leadership, values (e.g. questioning attitude), culture, and prioritise – risk informed; • KM is a complex organic creature and needs to be nurtured, fed, learn, grow, evolve in response to a changing environment, and discharge what is not needed to prosper

  17. Facts learnt from the Hanshin-Awaji disaster and consideration on design basis earthquake

    Energy Technology Data Exchange (ETDEWEB)

    Shibata, Heki [Yokohama National Univ. (Japan). Faculty of Engineering

    1997-03-01

    This paper will deal with how to establish the concept of the design basis earthquake for critical industrial facilities such as nuclear power plants in consideration of disasters induced by the 1995 Hyogoken-Nanbu Earthquake (Southern Hyogo-prefecture Earthquake-1995), so-called Kobe earthquake. The author once discussed various DBEs at 7 WCEE. At that time, the author assumed that the strongest effective PGA would be 0.7 G, and compared to the values of accelerations to a structure obtained by various codes in Japan and other countries. The maximum PGA observed by an instrument at the Southern Hyogo-pref. Earthquake-1995 exceeded the previous assumption of the author, even though the evaluation results of the previous paper had been pessimistic. According to the experience of Kobe event, the author will point out the necessity of the third earthquake S{sub s} adding to S{sub 1} and S{sub 2}, previous DBEs. (author)

  18. Facts learnt from the Hanshin-Awaji disaster and consideration on design basis earthquake

    International Nuclear Information System (INIS)

    Shibata, Heki

    1997-01-01

    This paper will deal with how to establish the concept of the design basis earthquake for critical industrial facilities such as nuclear power plants in consideration of disasters induced by the 1995 Hyogoken-Nanbu Earthquake (Southern Hyogo-prefecture Earthquake-1995), so-called Kobe earthquake. The author once discussed various DBEs at 7 WCEE. At that time, the author assumed that the strongest effective PGA would be 0.7 G, and compared to the values of accelerations to a structure obtained by various codes in Japan and other countries. The maximum PGA observed by an instrument at the Southern Hyogo-pref. Earthquake-1995 exceeded the previous assumption of the author, even though the evaluation results of the previous paper had been pessimistic. According to the experience of Kobe event, the author will point out the necessity of the third earthquake S s adding to S 1 and S 2 , previous DBEs. (author)

  19. Toxic industrial chemicals (TICs) as asymmetric weapons: the design basis threat

    International Nuclear Information System (INIS)

    Skinner, L.

    2009-01-01

    Asymmetric warfare concepts relate well to the use of improvised chemical weapons against urban targets. Sources of information on toxic industrial chemicals (TICs) and lists of high threat chemicals are available that point to likely choices for an attack. Accident investigations can be used as a template for attacks, and to judge the possible effectiveness of an attack using TICs. The results of a chlorine rail car accident in South Carolina, USA and the Russian military assault on a Moscow theater provide many illustrative points for similar incidents that mighty be carried out deliberately. Computer modeling of outdoor releases shows how an attack might take into consideration issues of stand-off distance and dilution. Finally, the preceding may be used to estimate with some accuracy the design basis threat posed by the used of TICs as weapons.(author)

  20. An overview of the UK regulatory expectation for design basis accident analysis

    International Nuclear Information System (INIS)

    Trimble, Andy

    2013-01-01

    The UK Health and Safety Executive published its most recent regulatory expectations in the 2006 version of it's safety assessment principles (SAPs). This built on experience regulating the full range of facilities for which it is responsible. Thus the principles underpinning all regulatory safety case assessment are the same but the implementation differs depending on the application. This paper will describe the published design basis accident analysis (DBAA) logic in context with other technical aspects of the regulatory expectation for safety cases. It will further illustrate the DBAA methodology with practical examples from actual experience on reprocessing plant gained over the last 15 years or so. Among the examples will be the relevance of conventional safety fault initiators to nuclear safety assessment. It will further demonstrate the derivation of facility limits and conditions necessary for nuclear safety. (authors)

  1. 78 FR 31614 - Implementation of Regulatory Guide 1.221 on Design-Basis Hurricane and Hurricane Missiles

    Science.gov (United States)

    2013-05-24

    ...-Basis Hurricane and Hurricane Missiles AGENCY: Nuclear Regulatory Commission. ACTION: Interim staff... regarding the application of Regulatory Guide (RG) 1.221, ``Design-Basis Hurricane and Hurricane Missiles... NRC-2012-0247 when contacting the NRC about the availability of information regarding this document...

  2. Will the changes proposed to the conceptual framework’s definitions and recognition criteria provide a better basis for the IASB standard setting?

    NARCIS (Netherlands)

    Brouwer, A.; Hoogendoorn, M.; Naarding, E.

    2015-01-01

    In this paper we evaluate the International Accounting Standards Board’s (IASB) efforts, in a discussion paper (DP) of 2013, to develop a new conceptual framework (CF) in the light of its stated ambition to establish a robust and consistent basis for future standard setting, thereby guiding standard

  3. American National Standard: nuclear data sets for reactor design calculations

    International Nuclear Information System (INIS)

    1983-01-01

    This standard identifies and describes the specifications for developing, preparing, and documenting nuclear data sets to be used in reactor design calculations. The specifications include criteria for acceptance of evaluated nuclear data sets, criteria for processing evaluated data and preparation of processed continuous data and averaged data sets, and identification of specific evaluated, processed continuous, and averaged data sets which meet these criteria for specific reactor types

  4. American National Standard nuclear data sets for reactor design calculations

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    A standard is presented which identifies and describes the specifications for developing, preparing, and documenting nuclear data sets to be used in reactor design calculations. The specifications include (a) criteria for acceptance of evaluated nuclear data sets, (b) criteria for processing evaluated data and preparation of processed continuous data and averaged data sets, and (c) identification of specific evaluated, processed continuous, and averaged data sets which meet these criteria for specific reactor types

  5. Considerations on Fail Safe Design for Design Basis Accident (DBA) vs. Design Extension Condition (DEC): Lesson Learnt from the Fukushima Accident

    International Nuclear Information System (INIS)

    Ha, Jun Su; Kim, Sungyeop

    2014-01-01

    The fail safety design is referred to as an inherently safe design concept where the failure of an SSC (System, Structure or Component) leads directly to a safe condition. Usually the fail safe design has been devised based on the design basis accident (DBAs), because the nuclear safety has been assured by securing the capability to safely cope with DBAs. Currently regards have been paid to the DEC (Design Extension Condition) as an extended design consideration. Hence additional attention should be paid to the concept of the fail safe design in order to consider the DEC, accordingly. In this study, a case chosen from the Fukushima accident is studied to discuss the issue associated with the fail safe design in terms of DBA and DEC standpoints. For the fail safe design to be based both on the DBA and the DEC, a Mode Changeable Fail Safe Design (MCFSD) is proposed in this study. Additional discussions on what is needed for the MCFSD to be applied in the nuclear safety are addressed as well. One of the lessons learnt from the Fukushima accident should include considerations on the fail-safe design in a changing regulatory framework. Currently the design extension condition (DEC) including severe accidents should be considered during designing and licensing NPPs. Hence concepts on the fail safe design need to be changed to be based on not only the DBA but also the DEC. In this study, a case on a fail-safe design chosen from the Fukushima accident is studied to discuss the issue associated with the fail safe design in terms of DBA and DEC conditions. For the fail safe design to be based both on the DBA and the DEC, a Mode Changeable Fail Safe Design (MCFSD) is proposed in this study. Additional discussions on what is needed for the MCFSD to be applied in the nuclear safety are addressed as well

  6. Comparison of deterministic and stochastic techniques for estimation of design basis floods for nuclear power plants

    International Nuclear Information System (INIS)

    Solomon, S.I.; Harvey, K.D.

    1982-12-01

    The IAEA Safety Guide 50-SG-S10A recommends that design basis floods be estimated by deterministic techniques using probable maximum precipitation and a rainfall runoff model to evaluate the corresponding flood. The Guide indicates that stochastic techniques are also acceptable in which case floods of very low probability have to be estimated. The paper compares the results of applying the two techniques in two river basins at a number of locations and concludes that the uncertainty of the results of both techniques is of the same order of magnitude. However, the use of the unit hydrograph as the rainfall runoff model may lead in some cases to nonconservative estimates. A distributed non-linear rainfall runoff model leads to estimates of probable maximum flood flows which are very close to values of flows having a 10 6 - 10 7 years return interval estimated using a conservative and relatively simple stochastic technique. Recommendations on the practical application of Safety Guide 50-SG-10A are made and the extension of the stochastic technique to ungauged sites and other design parameters is discussed

  7. Application of the MELCOR code to design basis PWR large dry containment analysis.

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, Jesse; Notafrancesco, Allen (USNRC, Office of Nuclear Regulatory Research, Rockville, MD); Tills, Jack Lee (Jack Tills & Associates, Inc., Sandia Park, NM)

    2009-05-01

    The MELCOR computer code has been developed by Sandia National Laboratories under USNRC sponsorship to provide capability for independently auditing analyses submitted by reactor manufactures and utilities. MELCOR is a fully integrated code (encompassing the reactor coolant system and the containment building) that models the progression of postulated accidents in light water reactor power plants. To assess the adequacy of containment thermal-hydraulic modeling incorporated in the MELCOR code for application to PWR large dry containments, several selected demonstration designs were analyzed. This report documents MELCOR code demonstration calculations performed for postulated design basis accident (DBA) analysis (LOCA and MSLB) inside containment, which are compared to other code results. The key processes when analyzing the containment loads inside PWR large dry containments are (1) expansion and transport of high mass/energy releases, (2) heat and mass transfer to structural passive heat sinks, and (3) containment pressure reduction due to engineered safety features. A code-to-code benchmarking for DBA events showed that MELCOR predictions of maximum containment loads were equivalent to similar predictions using a qualified containment code known as CONTAIN. This equivalency was found to apply for both single- and multi-cell containment models.

  8. Approach to developing a ground-motion design basis for facilities important to safety at Yucca Mountain

    Energy Technology Data Exchange (ETDEWEB)

    King, J.L.

    1990-04-01

    The Department of Energy has proposed a methodology for developing a ground-motion design basis for prospective facilities at Yucca Mountain that are important to safety. The methodology utilizes a quasi-deterministic construct that is designed to provide a conservative, robust, and reproducible estimate of ground motion that has a one-in-ten chance of occurring during the preclosure period. This estimate is intended to define a ground-motion level for which the seismic design would ensure minimal disruption to operations; engineering analyses to ensure safe performance in the unlikely event that the design basis is exceeded are a part of the proposed methodology. 8 refs.

  9. Design and utilisation of protocols to characterise dynamic PET uptake of two tracers using basis pursuit

    Science.gov (United States)

    Bell, Christopher; Puttick, Simon; Rose, Stephen; Smith, Jye; Thomas, Paul; Dowson, Nicholas

    2017-06-01

    Imaging using more than one biological process using PET could be of great utility, but despite previously proposed approaches to dual-tracer imaging, it is seldom performed. The alternative of performing multiple scans is often infeasible for clinical practice or even in research studies. Dual-tracer PET scanning allows for multiple PET radiotracers to be imaged within the same imaging session. In this paper we describe our approach to utilise the basis pursuit method to aid in the design of dual-tracer PET imaging experiments, and later in separation of the signals. The advantage of this approach is that it does not require a compartment model architecture to be specified or even that both signals are distinguishable in all cases. This means the method for separating dual-tracer signals can be used for many feasible and useful combinations of biology or radiotracer, once an appropriate scanning protocol has been decided upon. Following a demonstration in separating the signals from two consecutively injected radionuclides in a controlled experiment, phantom and list-mode mouse experiments demonstrated the ability to test the feasibility of dual-tracer imaging protocols for multiple injection delays. Increases in variances predicted for kinetic macro-parameters V D and K I in brain and tumoral tissue were obtained when separating the synthetically combined data. These experiments confirmed previous work using other approaches that injections delays of 10-20 min ensured increases in variance were kept minimal for the test tracers used. On this basis, an actual dual-tracer experiment using a 20 min delay was performed using these radio tracers, with the kinetic parameters (V D and K I) extracted for each tracer in agreement with the literature. This study supports previous work that dual-tracer PET imaging can be accomplished provided certain constraints are adhered to. The utilisation of basis pursuit techniques, with its removed need to specify a model

  10. Low power RF circuit design in standard CMOS technology

    CERN Document Server

    Alvarado, Unai; Adín, Iñigo

    2012-01-01

    Low Power Consumption is one of the critical issues in the performance of small battery-powered handheld devices. Mobile terminals feature an ever increasing number of wireless communication alternatives including GPS, Bluetooth, GSM, 3G, WiFi or DVB-H. Considering that the total power available for each terminal is limited by the relatively slow increase in battery performance expected in the near future, the need for efficient circuits is now critical. This book presents the basic techniques available to design low power RF CMOS analogue circuits. It gives circuit designers a complete guide of alternatives to optimize power consumption and explains the application of these rules in the most common RF building blocks: LNA, mixers and PLLs. It is set out using practical examples and offers a unique perspective as it targets designers working within the standard CMOS process and all the limitations inherent in these technologies.

  11. Design basis and design features of WWER-440 model 213 nuclear power plants. Reference plant: Bohunice V2 (Slovakia)

    International Nuclear Information System (INIS)

    1994-05-01

    The prime objective of the IAEA Technical Co-operation Project on Evaluation of Safety Aspects of WWER-440 model 213 NPPs is to co-ordinate and to integrate assistance to national organizations in studying selected aspects of safety for the same type of reactors. Consequently, the study integrated the results generated by national activities carried out in the Czech Republic, Hungary, Slovakia and Ukraine and co-ordinated through the IAEA. Valuable assistance in carrying out the tasks was also provided by Bulgaria and Poland. A set of publications is being prepared to present the results of the project. The publications are intended to facilitate the review and utilization of the results of the project. They are also providing assistance in further refinement and/or extension of plant specific safety evaluation of model 213 NPPs. This Technical Document addressing the design basis and safety related design features of WWER-440 model 213 plants is the first of the series to be published. It is hoped that this document will be useful to anyone working in the field of WWER safety, and in particular to experts planning, executing or reviewing studies related to the subject. Refs, 36 figs, tabs

  12. Development, use and maintenance of the design basis threat. Implementing guide

    International Nuclear Information System (INIS)

    2009-01-01

    threat to those assets. As described in this publication, an understanding of the threat can lead to a detailed description of potential adversaries (the design basis threat), which, in turn, is the basis of an appropriately designed physical protection system. This direct link gives confidence that protection would be effective against an adversary attack. International experience in using a design basis threat to protect assets of high consequence is largely based on the protection of nuclear material and facilities. Furthermore, the nuclear security documents defining and recommending that physical protection be based upon the threat - The Physical Protection Objectives and Fundamental Principles (GOV/2001/41/ Attachment), the Recommendations on the Physical Protection of Nuclear Facilities and Nuclear Material (INFCIRC/225/Rev. 4 (corrected)), and the Convention on Physical Protection of Nuclear Facilities and Nuclear Material as Amended (INFCIRC/274) (adopted on 8 July 2005; (GOV/2005/57)) - do so exclusively for the protection of nuclear material and facilities. Given the historical background, and its continuing contemporary relevance, it has been necessary to draw on that nuclear protection experience in developing this publication. However, the general approach can also be applied to protecting other assets that require a high degree of confidence in the effectiveness of their protection, such as high-activity radioactive material. Specialists from France, Germany, Japan, the Russian Federation, Spain, the United Kingdom, and the United States of America assisted the IAEA in preparing this publication. A draft was presented to an open-ended technical meeting in December 2006, and subsequently circulated for comment to all Member States. This publication is consistent with The Physical Protection Objectives and Fundamental Principles; the Convention on Physical Protection of Nuclear Facilities and Nuclear Material as Amended; and the Recommendations on the

  13. Development, Use and Maintenance of the Design Basis Threat. Implementing Guide (Arabic Edition)

    International Nuclear Information System (INIS)

    2009-01-01

    threat to those assets. As described in this publication, an understanding of the threat can lead to a detailed description of potential adversaries (the design basis threat), which, in turn, is the basis of an appropriately designed physical protection system. This direct link gives confidence that protection would be effective against an adversary attack. International experience in using a design basis threat to protect assets of high consequence is largely based on the protection of nuclear material and facilities. Furthermore, the nuclear security documents defining and recommending that physical protection be based upon the threat. The Physical Protection Objectives and Fundamental Principles, the Recommendations on the Physical Protection of Nuclear Facilities and Nuclear Material, and the Convention on Physical Protection of Nuclear Facilities and Nuclear Material as Amended - do so exclusively for the protection of nuclear material and facilities. Given the historical background, and its continuing contemporary relevance, it has been necessary to draw on that nuclear protection experience in developing this publication. However, the general approach can also be applied to protecting other assets that require a high degree of confidence in the effectiveness of their protection, such as high-activity radioactive material. Specialists from France, Germany, Japan, the Russian Federation, Spain, the United Kingdom, and the United States of America assisted the IAEA in preparing this publication. A draft was presented to an open-ended technical meeting in December 2006, and subsequently circulated for comment to all Member States. This publication is consistent with The Physical Protection Objectives and Fundamental Principles; the Convention on Physical Protection of Nuclear Facilities and Nuclear Material as Amended; and the Recommendations on the Physical Protection of Nuclear Facilities and Nuclear Material.

  14. SRS BEDROCK PROBABILISTIC SEISMIC HAZARD ANALYSIS (PSHA) DESIGN BASIS JUSTIFICATION (U)

    Energy Technology Data Exchange (ETDEWEB)

    (NOEMAIL), R

    2005-12-14

    This represents an assessment of the available Savannah River Site (SRS) hard-rock probabilistic seismic hazard assessments (PSHAs), including PSHAs recently completed, for incorporation in the SRS seismic hazard update. The prior assessment of the SRS seismic design basis (WSRC, 1997) incorporated the results from two PSHAs that were published in 1988 and 1993. Because of the vintage of these studies, an assessment is necessary to establish the value of these PSHAs considering more recently collected data affecting seismic hazards and the availability of more recent PSHAs. This task is consistent with the Department of Energy (DOE) order, DOE O 420.1B and DOE guidance document DOE G 420.1-2. Following DOE guidance, the National Map Hazard was reviewed and incorporated in this assessment. In addition to the National Map hazard, alternative ground motion attenuation models (GMAMs) are used with the National Map source model to produce alternate hazard assessments for the SRS. These hazard assessments are the basis for the updated hard-rock hazard recommendation made in this report. The development and comparison of hazard based on the National Map models and PSHAs completed using alternate GMAMs provides increased confidence in this hazard recommendation. The alternate GMAMs are the EPRI (2004), USGS (2002) and a regional specific model (Silva et al., 2004). Weights of 0.6, 0.3 and 0.1 are recommended for EPRI (2004), USGS (2002) and Silva et al. (2004) respectively. This weighting gives cluster weights of .39, .29, .15, .17 for the 1-corner, 2-corner, hybrid, and Greens-function models, respectively. This assessment is judged to be conservative as compared to WSRC (1997) and incorporates the range of prevailing expert opinion pertinent to the development of seismic hazard at the SRS. The corresponding SRS hard-rock uniform hazard spectra are greater than the design spectra developed in WSRC (1997) that were based on the LLNL (1993) and EPRI (1988) PSHAs. The

  15. Ideal flow theory for the double – shearing model as a basis for metal forming design

    Science.gov (United States)

    Alexandrov, S.; Trung, N. T.

    2018-02-01

    In the case of Tresca’ solids (i.e. solids obeying the Tresca yield criterion and its associated flow rule) ideal flows have been defined elsewhere as solenoidal smooth deformations in which an eigenvector field associated everywhere with the greatest principal stress (and strain rate) is fixed in the material. Under such conditions all material elements undergo paths of minimum plastic work, a condition which is often advantageous for metal forming processes. Therefore, the ideal flow theory is used as the basis of a procedure for the preliminary design of such processes. The present paper extends the theory of stationary planar ideal flow to pressure dependent materials obeying the double shearing model and the double slip and rotation model. It is shown that the original problem of plasticity reduces to a purely geometric problem. The corresponding system of equations is hyperbolic. The characteristic relations are integrated in elementary functions. In regions where one family of characteristics is straight, mapping between the principal lines and Cartesian coordinates is determined by linear ordinary differential equations. An illustrative example is provided.

  16. iROCS: Integrated accident management framework for coping with beyond-design-basis external events

    International Nuclear Information System (INIS)

    Kim, Jaewhan; Park, Soo-Yong; Ahn, Kwang-Il; Yang, Joon-Eon

    2016-01-01

    Highlights: • An integrated mitigating strategy to cope with extreme external events, iROCS, is proposed. • The strategy aims to preserve the integrity of the reactor vessel as well as core cooling. • A case study for an extreme damage state is performed to assess the effectiveness and feasibility of candidate mitigation strategies under an extreme event. - Abstract: The Fukushima Daiichi accident induced by the Great East Japan earthquake and tsunami on March 11, 2011, poses a new challenge to the nuclear society, especially from an accident management viewpoint. This paper presents a new accident management framework called an integrated, RObust Coping Strategy (iROCS) to cope with beyond-design-basis external events (BDBEEs). The iROCS approach is characterized by classification of various plant damage conditions (PDCs) that might be impacted by BDBEEs and corresponding integrated coping strategies for each of PDCs, aiming to maintain and restore core cooling (i.e., to prevent core damage) and to maintain the integrity of the reactor pressure vessel if it is judged that core damage may not be preventable in view of plant conditions. From a case study for an extreme damage condition, it showed that candidate accident management strategies should be evaluated from the viewpoint of effectiveness and feasibility against accident scenarios and extreme damage conditions of the site, especially when employing mobile or portable equipment under BDBEEs within the limited time available to achieve desired goals such as prevention of core damage as well as a reactor vessel failure.

  17. iROCS: Integrated accident management framework for coping with beyond-design-basis external events

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jaewhan; Park, Soo-Yong; Ahn, Kwang-Il, E-mail: kiahn@kaeri.re.kr; Yang, Joon-Eon

    2016-03-15

    Highlights: • An integrated mitigating strategy to cope with extreme external events, iROCS, is proposed. • The strategy aims to preserve the integrity of the reactor vessel as well as core cooling. • A case study for an extreme damage state is performed to assess the effectiveness and feasibility of candidate mitigation strategies under an extreme event. - Abstract: The Fukushima Daiichi accident induced by the Great East Japan earthquake and tsunami on March 11, 2011, poses a new challenge to the nuclear society, especially from an accident management viewpoint. This paper presents a new accident management framework called an integrated, RObust Coping Strategy (iROCS) to cope with beyond-design-basis external events (BDBEEs). The iROCS approach is characterized by classification of various plant damage conditions (PDCs) that might be impacted by BDBEEs and corresponding integrated coping strategies for each of PDCs, aiming to maintain and restore core cooling (i.e., to prevent core damage) and to maintain the integrity of the reactor pressure vessel if it is judged that core damage may not be preventable in view of plant conditions. From a case study for an extreme damage condition, it showed that candidate accident management strategies should be evaluated from the viewpoint of effectiveness and feasibility against accident scenarios and extreme damage conditions of the site, especially when employing mobile or portable equipment under BDBEEs within the limited time available to achieve desired goals such as prevention of core damage as well as a reactor vessel failure.

  18. Calculation of particulate dispersion in a design-basis tornadic storm from Westinghouse PFDL, Cheswick, Pennsylvania

    International Nuclear Information System (INIS)

    Pepper, D.W.

    1978-07-01

    A three-dimensional numerical model is used to calculate ground-level air concentration and deposition (due to precipitation scavenging) after a hypothetical tornado strike at the Westinghouse Plutonium Fuel Development Laboratory (PFDL) at Cheswick, Pennsylvania. Plutonium particles less than 20 μm in diameter are assumed to be lifted into the tornadic storm cell by the vortex. The rotational characteristics of the tornadic storm are embedded within the larger mesoscale flow of the storm system. The design-basis translational wind values are based on probabilities associated with existing records of tornado strikes in the vicinity of the plant site. Turbulence exchange coefficients are based on empirical values deduced from experimental data in severe storms and from theoretical assumptions obtained from the literature. The method of moments is used to incorporate subgrid-scale resolution of the concentration within a grid cell volume. This method is a quasi-Lagrangian scheme which minimizes numerical error associated with advection. In all case studies, the effects of updrafts and downdrafts, coupled with scavenging of the particulates by precipitation, account for most of the material being deposited within 20-45 km downwind of the plant site. Ground-level isopleths in the x-y plane show that most of the material is deposited behind and slightly to the left of the centerline trajectory of the storm. Approximately 5% of the material is dispersed into the stratosphere and anvil section of the storm

  19. Usability standards meet scenario-based design: challenges and opportunities.

    Science.gov (United States)

    Vincent, Christopher J; Blandford, Ann

    2015-02-01

    The focus of this paper is on the challenges and opportunities presented by developing scenarios of use for interactive medical devices. Scenarios are integral to the international standard for usability engineering of medical devices (IEC 62366:2007), and are also applied to the development of health software (draft standard IEC 82304-1). The 62366 standard lays out a process for mitigating risk during normal use (i.e. use as per the instructions, or accepted medical practice). However, this begs the question of whether "real use" (that which occurs in practice) matches "normal use". In this paper, we present an overview of the product lifecycle and how it impacts on the type of scenario that can be practically applied. We report on the development and testing of a set of scenarios intended to inform the design of infusion pumps based on "real use". The scenarios were validated by researchers and practitioners experienced in clinical practice, and their utility was assessed by developers and practitioners representing different stages of the product lifecycle. These evaluations highlighted previously unreported challenges and opportunities for the use of scenarios in this context. Challenges include: integrating scenario-based design with usability engineering practice; covering the breadth of uses of infusion devices; and managing contradictory evidence. Opportunities included scenario use beyond design to guide marketing, to inform purchasing and as resources for training staff. This study exemplifies one empirically grounded approach to communicating and negotiating the realities of practice. Copyright © 2014 The Authors. Published by Elsevier Inc. All rights reserved.

  20. A study on the rate-of-loading applied in design basis performance evaluation for motor operated valves

    International Nuclear Information System (INIS)

    Kang, S. C.; Jung, R. H.; Lee, D. H.; Park, S. K.; Hong, S. E.

    2002-01-01

    Rate-of-loading(ROL) is defined as the characteristics of change in stem thrust of Motor Operated Valves (MOVs). ROL can cause leakage through disk because the valve is not closed fully under differential pressure conditions (design basis conditions) if the Torque Switch Trip (TST) setpoint is conducted under static conditions. Dynamic and static test should be implemented to quantify ROL, value. Design basis performance evaluation for MOVs is implemented in other to address the regulatory recommendation issued by the ministry of science and technology. In the evaluation the uncertainty value of ROL, 10% is applied for the valves that their design basis differential pressure is less than 50 psid or can not be tested dynamically. The value had been used in the design basis performance evaluation of U.S. In order to confirm the applicability of 10% value statistic analysis was conducted based on the ROL values evaluated from the valves that both static and dynamic tests were conducted. The applicability of the values for current design basis performance evaluation was confirmed because confidence distribution of values was ranged from 90% to 95%

  1. Evaluation of Standard Concepts Design of Library Interior Physical Environment

    Directory of Open Access Journals (Sweden)

    Debri Harindya Putri

    2018-01-01

    Full Text Available Currently the function of a room is not only used as a shelter, the function of the room itself to be increased as a refreshing or relaxation area for users to follow the development of creativity and technology in the field of design. The comfortable factor becomes the main factor that indicates a successful process of creating a space. No exception library. The nature of library seemed stiff because of its function as a place to read, now can be developed and made into more dynamic with the special design concepts or color patterns used. Libraries can be created a special concept that suits the characteristics of the users themselves. Most users of the library, especially in college libraries are teenagers. Naturally, teenagers like to gather with their friends and we have to facilitate this activity in our library design concept. In addition we can also determine the needs of users through research by questionnaire method. The answers of users can be mapped and drawn conclusions. To explore the research, the author reviewed some literature about library interior design and observed the library of Ma Chung University as a case study. The combined results of the method can be concluded and the discovery of ideal standards of physical environment. So, the library can be made as a comfortable reading environment so as to increased interest in reading behavior and the frequent visits of students in the library

  2. Standard guide for design criteria for plutonium gloveboxes

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This guide defines criteria for the design of glovebox systems to be used for the handling of plutonium in any chemical or physical form or isotopic composition or when mixed with other elements or compounds. Not included in the criteria are systems auxiliary to the glovebox systems such as utilities, ventilation, alarm, and waste disposal. Also not addressed are hot cells or open-face hoods. The scope of this guide excludes specific license requirements relating to provisions for criticality prevention, hazards control, safeguards, packaging, and material handling. Observance of this guide does not relieve the user of the obligation to conform to all federal, state, and local regulations for design and construction of glovebox systems. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. 1.3 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user...

  3. Standard-D hydrogen monitoring system, system design description

    International Nuclear Information System (INIS)

    Schneider, T.C.

    1996-01-01

    During most of the year, it is assumed that the vapor space in the 177 radioactive waste tanks on the Hanford Project site contain a uniform mixture of gases. Several of these waste tanks (currently twenty-five, 6 Double Shell Tanks and 19 Single Shell Tanks) were identified as having the potential for the buildup of gasses to a flammable level. An active ventilation system in the Double Shell Tanks and a passive ventilation system in the Single Shell Tanks provides a method of expelling gasses from the tanks. A gas release from a tank causes a temporary rise in the tank pressure, and a potential for increased concentration of hydrogen gas in the vapor space. The gas is released via the ventilation systems until a uniform gas mixture in the vapor space is once again achieved. The Standard Hydrogen Monitoring System (SHMS) is designed to monitor and quantify the percent hydrogen concentration during these potential gas releases. This document describes the design of the Standard-D Hydrogen Monitoring System, (SHMS-D) and its components as it differs from the original SHMS

  4. The renewable portfolio standard: design considerations and an implementation survey

    International Nuclear Information System (INIS)

    Berry, T.; Jaccard, M.

    2001-01-01

    Renewables have social and environmental benefits compared to conventional electricity sources, but are rarely competitive on a strict financial cost basis. This is because conventional sources are sometimes subsidized, their full pollution costs are ignored, and renewables involve newer, higher-cost technologies whose relative costs will fall with commercialization. Governments use several mechanisms to support renewables, including direct financial support (grants, loans), indirect support (R and D, demonstrations), reform of financial costs of conventional sources (subsidy removal, pollution taxes), and the Renewable Portfolio Standard (RPS). The RPS requires a minimum share of electricity from renewable energy sources. Its use is spreading because it maintains an incentive for renewable producers to reduce costs, links the regulated market outcome to an environmental target, and reduces government involvement. Although it is too early to evaluate fully its effectiveness, the survey for this study explored implementation issues in three European countries, nine US states, and Australia, and found the following. The RPS target is usually set to have environmental benefits without causing significant price increases (cost caps are sometimes used). Most jurisdictions limit eligibility to grid-connected, domestic renewables. The RPS is usually applied to producers rather than consumers, and to energy output not capacity. Flexibility mechanisms are desired but a challenge to implement. Administration in the US and Australia is by government with delegation to independent utility regulators, while in Europe it is more the responsibility of government. Everywhere, the RPS is applied alongside other mechanisms of renewables support. (author)

  5. Common basis of establishing safety standards and other safety decision-making levels for different sources of health risk

    International Nuclear Information System (INIS)

    Demin, V.F.

    2002-01-01

    Current approaches in establishing safety standards and other decision-making levels for different sources of health risk are critically analysed. To have a common basis for this decision-making a specific risk index R is recommended. In the common sense R is quantitatively defined as LLE caused by the annual exposure to the risk source considered: R = annual exposure, damage (LLE) from the exposure unit. This common definition is also rewritten in specific forms for a set of different risk sources (ionising radiation, chemical pollutants, etc): for different risk sources the exposure can be measured with different quantities (the probability of death, the exposure dose, etc.). R is relative LLE: LLE in years referred to 1 year under the risk. The dimension of this value is [year/year]. In the statistical sense R is conditionally the share of the year, which is lost due to exposure to a risk source during this year. In this sense R can be called as the relative damage. Really lifetime years are lost after the exposure. R can be in some conditional sense considered as a dimensionless quantity. General safety standards R n for the public and occupational workers have been suggested in terms of this index: R n = 0.0007 and 0.01 accordingly. Secondary safety standards are derived for a number of risk sources (ionising radiation, environmental chemical pollutants, etc). Values of R n are chosen in such a way that to have the secondary radiation BSS being equivalent to the current one's. Other general and derived levels for safety decision-making are also proposed including the de-minimus levels. Their possible dependence on the national or regional health-demographic data (HDD) is considered. Such issues as the ways of the integration and averaging of risk indices considered through the national or regional HDD for different risk sources and the use of non-threshold linear exposure - response relationships for ionising radiation and chemical pollutants are analysed

  6. Design scope and level for standard design certification under a two step licensing process

    Energy Technology Data Exchange (ETDEWEB)

    Huh, Chang Wook; Suh, Nam Duk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2012-08-15

    A small integral reactor SMART (System Integrated Modular Advanced ReacTor), being developed in Korea since late 1990s and targeted to obtaining a standard design approval by the end of 2011, is introduced. The design scope and level for design certification (DC) is well described in the U.S. NRC SECY documents published the early 1990s. However, the documents are valid for a one-step licensing process called a combined operating license (COL) by the U.S. NRC, while Korea still uses a two-step licensing process. Thus, referencing the concept of the SECY documents, we have established the design scope and level for the SMART DC using the contexts of the standard review plan (SRP). Some examples of the results and issues raised during our review are briefly presented in this paper. The same methodology will be applied to other types of reactor under development in Korea, such as future VHTR reactors.

  7. State Energy Efficiency Resource Standards: Design, Status, and Impacts

    Energy Technology Data Exchange (ETDEWEB)

    Steinberg, D.; Zinaman, O.

    2014-05-01

    An energy efficiency resource standard (EERS) is a policy that requires utilities or other entities to achieve a specified amount of energy savings through customer energy efficiency programs within a specified timeframe. EERSs may apply to electricity usage, natural gas usage, or both. This paper provides an overview of the key design features of EERSs for electricity, reviews the variation in design of EERSs across states, and provides an estimate of the amount of savings required by currently specified EERSs in each state. As of December, 2013, 23 states have active and binding EERSs for electricity. We estimate that state EERSs will require annual electricity savings of approximately 8-11% of total projected demand by 2020 in states with EERSs, however the level of savings targeted by the policies varies significantly across states. In addition to the variation in targeted savings, the design of EERSs varies significantly across states leading to differences in the suite of incentives created by the policy, the flexibility of compliance with the policy, the balance of benefits and costs of the policy between producers and consumers, and the certainty with which the policy will drive long-term savings.

  8. 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

  9. 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.

  10. Criteria for calculating the efficiency of deep-pleated HEPA filters with aluminum separators during and after design basis accidents

    Energy Technology Data Exchange (ETDEWEB)

    Bergman, W.; First, M.W.; Anderson, W.L. [Lawrence Livermore National Laboratory, CA (United States)] [and others

    1995-02-01

    We have reviewed the literature on the performance of HEPA filters under normal and abnormal conditions to establish criteria for calculating the efficiency of HEPA filters in a DOE nonreactor nuclear facility during and after a Design Basis Accident (DBA). This study is only applicable to the standard deep-pleated HEPA filter with aluminum separators as specified in ASME N509[1]. Other HEPA filter designs such as the mini-pleat and separatorless filters are not included in this study. The literature review included the performance of new filters and parameters that may cause deterioration in the filter performance such as filter age, radiation, corrosive chemicals, seismic and rough handling, high temperature, moisture, particle clogging, high air flow and pressure pulses. The deterioration of the filter efficiency depends on the exposure parameters; in severe exposure conditions the filter will be damaged and have a residual efficiency of 0%. There are large gaps and limitations in the data that introduce significant error in the estimates of HEPA filter efficiencies under DBA conditions. Because of this limitation, conservative values of filter efficiency were chosen. The estimation of the efficiency of the HEPA filters under DBA conditions involves three steps: (1) The filter pressure drop and environmental parameters are determined during and after the DBA, (2) Comparing the filter pressure drop to a set of threshold values above which the filter is damaged. There is a different threshold value for each combination of environmental parameters, and (3) Determining the filter efficiency. If the filter pressure drop is greater than the threshold value, the filter is damaged and is assigned 0% efficiency. If the pressure drop is less, then the filter is not damaged and the efficiency is determined from literature values of the efficiency at the environmental conditions.

  11. Criteria for calculating the efficiency of deep-pleated HEPA filters with aluminum separators during and after design basis accidents

    International Nuclear Information System (INIS)

    Bergman, W.; First, M.W.; Anderson, W.L.

    1995-01-01

    We have reviewed the literature on the performance of HEPA filters under normal and abnormal conditions to establish criteria for calculating the efficiency of HEPA filters in a DOE nonreactor nuclear facility during and after a Design Basis Accident (DBA). This study is only applicable to the standard deep-pleated HEPA filter with aluminum separators as specified in ASME N509[1]. Other HEPA filter designs such as the mini-pleat and separatorless filters are not included in this study. The literature review included the performance of new filters and parameters that may cause deterioration in the filter performance such as filter age, radiation, corrosive chemicals, seismic and rough handling, high temperature, moisture, particle clogging, high air flow and pressure pulses. The deterioration of the filter efficiency depends on the exposure parameters; in severe exposure conditions the filter will be damaged and have a residual efficiency of 0%. There are large gaps and limitations in the data that introduce significant error in the estimates of HEPA filter efficiencies under DBA conditions. Because of this limitation, conservative values of filter efficiency were chosen. The estimation of the efficiency of the HEPA filters under DBA conditions involves three steps: (1) The filter pressure drop and environmental parameters are determined during and after the DBA, (2) Comparing the filter pressure drop to a set of threshold values above which the filter is damaged. There is a different threshold value for each combination of environmental parameters, and (3) Determining the filter efficiency. If the filter pressure drop is greater than the threshold value, the filter is damaged and is assigned 0% efficiency. If the pressure drop is less, then the filter is not damaged and the efficiency is determined from literature values of the efficiency at the environmental conditions

  12. E-learning course: Basis of Harvest and Preservation of Tissues – design and initial experience

    Directory of Open Access Journals (Sweden)

    Pavel Měřička

    2014-05-01

    Full Text Available Background: The design and initial experience with the e-learning course “Basis of Harvest and Preservation of Tissues” used as a support of an elective subject is presented. The aim of the e-learning course was to enable the students to learn the theoretical principles of the subject individually and to present the gained knowledge at the final seminar. Methods: All functions of the course were operated in Moodle, local application of the Charles University in Prague, Faculty of Medicine in Hradec Králové. The course was divided into 3 main topics corresponding with topics of lectures: 1. Principles of tissue and organ donation, 2. Low temperature preservation of cells, tissues and organs, 3. Quality and safety assurance in practice of tissue and procurement establishments. A test consisting of 5 questions selected randomly from the bank of questions followed each topic. If the student answers correctly at least 3 questions he is allowed to pass to the next topic. The fourth topic “Basic processes in the tissue establishment and principles of their validation” was added into the electronic version as a tool for repeating and improving of knowledge. The fifth topic was represented by a database for uploading theses presented by students at the final seminar. The final test consisted of 15 questions (5 ones from each basic topic. It was necessary to answer correctly at least 10 questions to receive a certificate of completing the course. Results: The course was put into operation during the summer term of the academic year 2012/2013. To the date 15 of September the total of 23 students enrolled (17, i.e. all students of the elective subject in the Czech version, 2 students of this subject in the English version, 2 postgraduate students and 2 medical doctors. All enrolled students used the course for on-line learning, downloading, or printing course study materials. All undergraduate students were obliged to use it for preparation

  13. Evaluation of the Swedish biogas standard - basis for a future audit; Utvaerdering av svensk biogasstandard - underlag foer en framtida revision

    Energy Technology Data Exchange (ETDEWEB)

    Svensson, Mattias

    2011-04-15

    This report is intended to constitute a basis for a future revision of the SS 15 54 38, 'Motor fuels - Biogas as fuel for high-speed otto engines.' When it was published in 1999, it was not deemed appropriate to source compressed biomethane from landfill gas, because of its wider range of trace elements, often in relatively high concentrations, such as siloxanes and halogenated hydrocarbons. Siloxanes are also present in the gas from waste water treatment plants, but the assessment was made that upgrading methods available at the time reduced these levels sufficiently. By putting a maximum limit on the nitrogen content, landfill gas was effectively shut out. Technical Development (cryogenic upgrading making it possible to clean landfill gas to biomethane quality; stricter emissions standards for vehicles that has led to a higher level of sophistication in engine and aftertreatment technologies) has now made it necessary to better control the levels of all trace elements. The state of standardization is not satisfactory for CNG in general and renewable CNG (biomethane) in particular. Standardization at the international level is mostly qualitative. Most standards are at the national level and with the exception of Sweden biomethane is only standardized for injection on the natural gas network. A mandate (M/475, 2010) from the European Commission to develop the CEN standards for biomethane fed into the grid, or used directly as renewable CNG, may change this, and the issue will be addressed in a new committee (CEN/TC408 'Project Committee - Biogas for use in transportation and injection into natural gas pipelines'). A variety of trace elements has been discussed for inclusion in the new standards, where countries such as Holland and France stand out as supporters of more stringent and comprehensive regulations. This report's working group considers it like the regulation of substances such as siloxanes and halogenated hydrocarbons will lead

  14. Implementation of an Industrial-Based Case Study as the Basis for a Design Project in an Introduction to Mechanical Design Course

    Science.gov (United States)

    Lackey, Ellen

    2011-01-01

    The purpose of this paper is to discuss the implementation of an industrial-based case study as the basis for a design project for the Spring 2009 Introduction to Mechanical Design Course at the University of Mississippi. Course surveys documented the lack of student exposure in classes to the types of projects typically experienced by engineers…

  15. Structural Basis for Escape of Human Astrovirus from Antibody Neutralization: Broad Implications for Rational Vaccine Design

    Energy Technology Data Exchange (ETDEWEB)

    Bogdanoff, Walter A.; Perez, Edmundo I.; López, Tomás; Arias, Carlos F.; DuBois, Rebecca M. (UNAM-Mexico); (UCSC)

    2017-10-25

    ABSTRACT

    Human astroviruses are recognized as a leading cause of viral diarrhea worldwide in children, immunocompromised patients, and the elderly. There are currently no vaccines available to prevent astrovirus infection; however, antibodies developed by healthy individuals during previous infection correlate with protection from reinfection, suggesting that an effective vaccine could be developed. In this study, we investigated the molecular mechanism by which several strains of human astrovirus serotype 2 (HAstV-2) are resistant to the potent HAstV-2-neutralizing monoclonal antibody PL-2 (MAb PL-2). Sequencing of the HAstV-2 capsid genes reveals mutations in the PL-2 epitope within the capsid's spike domain. To understand the molecular basis for resistance from MAb PL-2 neutralization, we determined the 1.35-Å-resolution crystal structure of the capsid spike from one of these HAstV-2 strains. Our structure reveals a dramatic conformational change in a loop within the PL-2 epitope due to a serine-to-proline mutation, locking the loop in a conformation that sterically blocks binding and neutralization by MAb PL-2. We show that mutation to serine permits loop flexibility and recovers MAb PL-2 binding. Importantly, we find that HAstV-2 capsid spike containing a serine in this loop is immunogenic and elicits antibodies that neutralize all HAstV-2 strains. Taken together, our results have broad implications for rational selection of vaccine strains that do not contain prolines in antigenic loops, so as to elicit antibodies against diverse loop conformations.

    IMPORTANCEHuman astroviruses (HAstVs) infect nearly every person in the world during childhood and cause diarrhea, vomiting, and fever. In this study, we investigated how several strains of HAstV are resistant to a virus-neutralizing monoclonal antibody. We determined the crystal structure of the capsid protein spike domain from one of these HAstV strains and found that

  16. Semitrailer chassis design against fatigue on the basis of field test data

    NARCIS (Netherlands)

    M. van Klink; Joop Pauwelussen; L. Horn; D. van Rhee; G. ten Ham; R. Alderliesten

    2012-01-01

    During the previous HVTT conference in Melbourne, results have been presented of a project FORWARD, including eleven different trailer manufacturers, involving testing and modeling activities to establish a practical basis for realistic fatigue assessment as a step towards an improved light-weight

  17. 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

  18. American National Standard: design requirements for light-water-reactor fuel-handling systems

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    This standard defines the required functions of fuel handling systems at light water reactor nuclear power plants. It provides minimum design requirements for equipment and tools for safe handling of nuclear fuel and control components at light water reactor nuclear power plants. The fuel handling system covered by this standard consists of handling equipment used for receiving and inspecting fuel containing new and recycled uranium; transporting on-site and loading fuel containing new and recycled uranium or irradiated fuel and control components in the reactor; removing from the reactor, transporting to storage, and inspecting irradiated fuel and loading casks for shipment of irradiated fuel from the site. It includes basic requirements and configuration for design, fabrication, maintenance, and operation. The basis of this standard is that the intended function of the equipment will be performed in an efficient and economical manner that assures protection to plant personnel and to the public, and that any radiation exposurers are maintained as low as reasonably achievable

  19. Multi dimensional analysis of Design Basis Events using MARS-LMR

    International Nuclear Information System (INIS)

    Woo, Seung Min; Chang, Soon Heung

    2012-01-01

    Highlights: ► The one dimensional analyzed sodium hot pool is modified to a three dimensional node system, because the one dimensional analysis cannot represent the phenomena of the inside pool of a big size pool with many compositions. ► The results of the multi-dimensional analysis compared with the one dimensional analysis results in normal operation, TOP (Transient of Over Power), LOF (Loss of Flow), and LOHS (Loss of Heat Sink) conditions. ► The difference of the sodium flow pattern due to structure effect in the hot pool and mass flow rates in the core lead the different sodium temperature and temperature history under transient condition. - Abstract: KALIMER-600 (Korea Advanced Liquid Metal Reactor), which is a pool type SFR (Sodium-cooled Fast Reactor), was developed by KAERI (Korea Atomic Energy Research Institute). DBE (Design Basis Events) for KALIMER-600 has been analyzed in the one dimension. In this study, the one dimensional analyzed sodium hot pool is modified to a three dimensional node system, because the one dimensional analysis cannot represent the phenomena of the inside pool of a big size pool with many compositions, such as UIS (Upper Internal Structure), IHX (Intermediate Heat eXchanger), DHX (Decay Heat eXchanger), and pump. The results of the multi-dimensional analysis compared with the one dimensional analysis results in normal operation, TOP (Transient of Over Power), LOF (Loss of Flow), and LOHS (Loss of Heat Sink) conditions. First, the results in normal operation condition show the good agreement between the one and multi-dimensional analysis. However, according to the sodium temperatures of the core inlet, outlet, the fuel central line, cladding and PDRC (Passive Decay heat Removal Circuit), the temperatures of the one dimensional analysis are generally higher than the multi-dimensional analysis in conditions except the normal operation state, and the PDRC operation time in the one dimensional analysis is generally longer than

  20. Technical basis for the ITER detailed design report, cost review and safety analysis (DDR)

    International Nuclear Information System (INIS)

    1997-01-01

    The ITER Detailed Design Report (DDR), Cost Review and Safety Analysis is the 3rd major milestone representing the progress made in the ITER Engineering Design Activities. With the approval of the Interim Design Report (IDR), it has been possible to freeze the main concepts and system approaches for ITER and to develop the design in more detail for the individual components and sub-systems. This report, although designed to be fully understandable as a separate document, focusses particularly on the main changes since the IDR

  1. 75 FR 52860 - Final Airworthiness Design Standards for Acceptance Under the Primary Category Rule; Orlando...

    Science.gov (United States)

    2010-08-30

    ... DEPARTMENT OF TRANSPORTATION Federal Aviation Administration 14 CFR Part 21 Final Airworthiness Design Standards for Acceptance Under the Primary Category Rule; Orlando Helicopter Airways (OHA), Inc... Existence of Proposed Airworthiness Design Standards for Acceptance Under the Primary Category Rule; Orlando...

  2. Designing scalable product families by the radial basis function-high-dimensional model representation metamodelling technique

    Science.gov (United States)

    Pirmoradi, Zhila; Haji Hajikolaei, Kambiz; Wang, G. Gary

    2015-10-01

    Product family design is cost-efficient for achieving the best trade-off between commonalization and diversification. However, for computationally intensive design functions which are viewed as black boxes, the family design would be challenging. A two-stage platform configuration method with generalized commonality is proposed for a scale-based family with unknown platform configuration. Unconventional sensitivity analysis and information on variation in the individual variants' optimal design are used for platform configuration design. Metamodelling is employed to provide the sensitivity and variable correlation information, leading to significant savings in function calls. A family of universal electric motors is designed for product performance and the efficiency of this method is studied. The impact of the employed parameters is also analysed. Then, the proposed method is modified for obtaining higher commonality. The proposed method is shown to yield design solutions with better objective function values, allowable performance loss and higher commonality than the previously developed methods in the literature.

  3. Retrofitting a spent fuel pool spray system for alternative cooling as a strategy for beyond design basis events

    Energy Technology Data Exchange (ETDEWEB)

    Hartmann, Christoph; Vujic, Zoran [Westinghouse Electric Germany GmbH, Mannheim (Germany)

    2017-06-15

    Due to requirements for nuclear power plants to withstand beyond design basis accidents, including events such as happened in 2011 in the Fukushima Daiichi Nuclear Power Plant in Japan, alternative cooling of spent fuel is needed. Alternative spent fuel cooling can be provided by a retrofitted spent fuel pool spray system based on the AP1000 plant design. As part of Krsko Nuclear Power Plant's Safety Upgrade Program, Krsko Nuclear Power Plant decided on, and Westinghouse successfully designed a retrofit of the AP1000 {sup registered} plant spent fuel pool spray system to provide alternative spent fuel cooling.

  4. Standard-B Hydrogen Monitoring System, system design description

    International Nuclear Information System (INIS)

    Schneider, T.C.

    1995-01-01

    During most of the year, it is assumed that the vapor in the 177 radioactive waste tanks on the Hanford Project site contain a uniform mixture of gases. Several of these waste tanks (currently twenty five, 6 Double Shell Tanks and 19 Single Shell Tanks) were identified as having the potential for the buildup of gases to a flammable level. An active ventilation system in the Double Shell Tanks and a passive ventilation system in the Single Shell Tanks provides a method of expelling gases from the tanks. A gas release from a tank causes a temporary rise in the tank pressure, and a potential for increased concentration of hydrogen gas in the vapor space. The gas is released via the ventilation systems until a uniform gas mixture in the vapor space is once again achieved. This document describes the design of the Standard-B Hydrogen Monitoring System, (SHMS) and its components as it differs from the original SHMS. The differences are derived from changes made to improve the system performance but not implemented in all the installed enclosures

  5. Reference design for the standard mirror hybrid reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bender, D.J.; Fink, J.H.; Galloway, T.R.; Kastenberg, W.E.; Lee, J.D.; Devoto, R.S.; Neef, W.S. Jr.; Schultz, K.R.; Culver, D.W.; Rao, S.B.; Rao, S.R.

    1978-05-22

    This report describes the results of a two-year study by Lawrence Livermore Laboratory and General Atomic Co. to develop a conceptual design for the standard (minimum-B) mirror hybrid reactor. The reactor parameters have been chosen to minimize the cost of producing nuclear fuel (/sup 239/Pu) for consumption in fission power reactors (light water reactors). The deuterium-tritium plasma produces approximately 400 MW of fusion power with a plasma Q of 0.64. The fast-fission blanket, which is fueled with depleted uranium and lithium, generates sufficient tritium to run the reactor, has a blanket energy multiplication of M = 10.4, and has a net fissile breeding ratio of Pu/n = 1.51. The reactor has a net electrical output of 600 MWe, a fissile production of 2000 kg of plutonium per year (at a capacity factor of 0.74), and a net plant efficiency of 0.18. The plasma-containment field is generated by a Yin-Yang magnet using NbTi superconductor, and the neutral beam system uses positive-ion acceleration with beam direct conversion. The spherical blanket is based on gas-cooled fast reactor technology. The fusion components, blanket, and primary heat-transfer loop components are all contained within a prestressed-concrete reactor vessel, which provides magnet restraint and supports the primary heat-transfer loop and the blanket.

  6. Reference design for the standard mirror hybrid reactor

    International Nuclear Information System (INIS)

    Bender, D.J.; Fink, J.H.; Galloway, T.R.; Kastenberg, W.E.; Lee, J.D.; Devoto, R.S.; Neef, W.S. Jr.; Schultz, K.R.; Culver, D.W.; Rao, S.B.; Rao, S.R.

    1978-01-01

    This report describes the results of a two-year study by Lawrence Livermore Laboratory and General Atomic Co. to develop a conceptual design for the standard (minimum-B) mirror hybrid reactor. The reactor parameters have been chosen to minimize the cost of producing nuclear fuel ( 239 Pu) for consumption in fission power reactors (light water reactors). The deuterium-tritium plasma produces approximately 400 MW of fusion power with a plasma Q of 0.64. The fast-fission blanket, which is fueled with depleted uranium and lithium, generates sufficient tritium to run the reactor, has a blanket energy multiplication of M = 10.4, and has a net fissile breeding ratio of Pu/n = 1.51. The reactor has a net electrical output of 600 MWe, a fissile production of 2000 kg of plutonium per year (at a capacity factor of 0.74), and a net plant efficiency of 0.18. The plasma-containment field is generated by a Yin-Yang magnet using NbTi superconductor, and the neutral beam system uses positive-ion acceleration with beam direct conversion. The spherical blanket is based on gas-cooled fast reactor technology. The fusion components, blanket, and primary heat-transfer loop components are all contained within a prestressed-concrete reactor vessel, which provides magnet restraint and supports the primary heat-transfer loop and the blanket

  7. Design solutions for water treatment plants constructed on the basis of membrane technologies

    Science.gov (United States)

    Panteleev, A. A.; Ryabchikov, B. E.; Zhadan, A. V.; Khoruzhii, O. V.

    2012-07-01

    Two process circuits for demineralizing makeup water for power units at thermal power stations are considered. One of them is constructed on the basis of a combined plant comprising reverse-osmosis and ion-exchange apparatuses and the other comprises reverse-osmosis and electric deionization apparatuses. The considered circuits are analyzed by way of comparing them with the traditional chemical water demineralization system. Advantages and drawbacks of the new technologies for treating natural water are pointed out.

  8. A design basis for the development of advanced CANDU control centres

    International Nuclear Information System (INIS)

    Feher, M.P.; Davey, E.C.; Lupton, L.R.

    1995-01-01

    The basic design for current CANDU control centres was established in the early 1970's. Plants constructed since then have, for the most part, retained the same basic design. Several factors have led to the need to re-examine CANDU control centre design for plants to be built beyond the year 2000. These factors include the changing roles and responsibilities for the operations staff, an improved understanding of operational issues associated with supervisory control, an improved understanding of human error in operational situations, the opportunity for improved plant performance through the introduction of new technologies, and marketing pressures. This paper describes the proposed design bases for the development of advanced control centres to be implemented in CANDU plants beyond the year 2000. Four areas have been defined covering design goals, design principles, operational bases, and plant functional bases. (author)

  9. 36 CFR 1281.4 - What are the architectural and design standards for Presidential libraries?

    Science.gov (United States)

    2010-07-01

    ... § 1281.4 What are the architectural and design standards for Presidential libraries? The Archivist is required by 44 U.S.C. 2112(a)(2) to promulgate architectural and design standards for Presidential libraries. The standards address the architectural, design, and structural requirements of a new...

  10. Demonstration of a Basis for Tall Wind Turbine Design, EUDP Project Final Report

    DEFF Research Database (Denmark)

    Natarajan, Anand; Dimitrov, Nikolay Krasimirov; Madsen, Peter Hauge

    Wind turbine design using calibrated wind models have been proposed to be used in conjunction with load cases which lead to reduced uncertainties in the design of wind turbines with hub heights above 60m. These recommended wind profiles have been made for shear, wind directional change and turbul......Wind turbine design using calibrated wind models have been proposed to be used in conjunction with load cases which lead to reduced uncertainties in the design of wind turbines with hub heights above 60m. These recommended wind profiles have been made for shear, wind directional change...

  11. THEORETICAL CONTENT FOUNDATION OF PREPARING TEACHERS OF LABOR TRAINING TO TEACHING BASIS OF DESIGN

    Directory of Open Access Journals (Sweden)

    Ihor Savenko

    2016-06-01

    Full Text Available In the article the basic principles of shaping the content of training future teachers of technology education to realize design activity in schools have been considered. Formation of the basic core knowledge, abilities and skills of future teachers should be provided in the fundamental scientific, general and cultural and professional training that is subjected to certain principles of pedagogical design. Design education as a powerful educative potential aimed at designing and providing humanitarian and cultural orientation of a student has been revealed. The design is a valued feature of professional education of future teachers of labor studies and promotes the development of a special type of culture and thinking that directs to educational values and determines the individual educational strategy of professional development.

  12. Materials for Consideration in Standardized Canister Design Activities.

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, Charles R.; Ilgen, Anastasia Gennadyevna; Enos, David George; Teich-McGoldrick, Stephanie; Hardin, Ernest

    2014-10-01

    This document identifies materials and material mitigation processes that might be used in new designs for standardized canisters for storage, transportation, and disposal of spent nuclear fuel. It also addresses potential corrosion issues with existing dual-purpose canisters (DPCs) that could be addressed in new canister designs. The major potential corrosion risk during storage is stress corrosion cracking of the weld regions on the 304 SS/316 SS canister shell due to deliquescence of chloride salts on the surface. Two approaches are proposed to alleviate this potential risk. First, the existing canister materials (304 and 316 SS) could be used, but the welds mitigated to relieve residual stresses and/or sensitization. Alternatively, more corrosion-resistant steels such as super-austenitic or duplex stainless steels, could be used. Experimental testing is needed to verify that these alternatives would successfully reduce the risk of stress corrosion cracking during fuel storage. For disposal in a geologic repository, the canister will be enclosed in a corrosion-resistant or corrosion-allowance overpack that will provide barrier capability and mechanical strength. The canister shell will no longer have a barrier function and its containment integrity can be ignored. The basket and neutron absorbers within the canister have the important role of limiting the possibility of post-closure criticality. The time period for corrosion is much longer in the post-closure period, and one major unanswered question is whether the basket materials will corrode slowly enough to maintain structural integrity for at least 10,000 years. Whereas there is extensive literature on stainless steels, this evaluation recommends testing of 304 and 316 SS, and more corrosion-resistant steels such as super-austenitic, duplex, and super-duplex stainless steels, at repository-relevant physical and chemical conditions. Both general and localized corrosion testing methods would be used to

  13. Probabilistic risk assessment for the Los Alamos Meson Physics Facility worst-case design-basis accident

    International Nuclear Information System (INIS)

    Sharirli, M.; Butner, J.M.; Rand, J.L.; Macek, R.J.; McKinney, S.J.; Roush, M.L.

    1992-01-01

    This paper presents results from a Los Alamos National Laboratory Engineering and Safety Analysis Group assessment of the worse-case design-basis accident associated with the Clinton P. Anderson Meson Physics Facility (LAMPF)/Weapons Neutron Research (WNR) Facility. The primary goal of the analysis was to quantify the accident sequences that result in personnel radiation exposure in the WNR Experimental Hall following the worst-case design-basis accident, a complete spill of the LAMPF accelerator 1L beam. This study also provides information regarding the roles of hardware systems and operators in these sequences, and insights regarding the areas where improvements can increase facility-operation safety. Results also include confidence ranges to incorporate combined effects of uncertainties in probability estimates and importance measures to determine how variations in individual events affect the frequencies in accident sequences

  14. The Concept of Fashion Design on the Basis of Color Coordination Using White LED Lighting

    Science.gov (United States)

    Mizutani, Yumiko; Taguchi, Tsunemasa

    This thesis focuses on the development of fashion design, especially a dress coordinated with White LED Lighting (=LED). As for the design concept a fusion of the advanced science and local culture was aimed for. For such a reason this development is a very experimental one. Here in particular I handled an Imperial Court dinner dress for the last Japanese First Lady, Mrs. Akie Abe who wore it at the Imperial Court dinner for the Indonesian First Couple held on November 2006 to. This dress made by Prof. T. Taguchi and I open up a new field in the dress design.

  15. Designing Smart Artifacts for Adaptive Mediation of Social Viscosity: Triadic Actor-Network Enactments as a Basis for Interaction Design

    Science.gov (United States)

    Salamanca, Juan

    2012-01-01

    With the advent of ubiquitous computing, interaction design has broadened its object of inquiry into how smart computational artifacts inconspicuously act in people's everyday lives. Although user-centered design approaches remains useful for exploring how people cope with interactive systems, they cannot explain how this new breed of…

  16. Design criteria and design basis for the 100-HR-3 and 100-KR-4 pump-and-treat projects

    International Nuclear Information System (INIS)

    McKinley, W.S.; Winters, J.N.

    1996-06-01

    The 100-HR-3 and 100-KR-4 Operable Units are located in the 100 Area at the Hanford Site in Richland, Washington. The document describes the project objectives and design criteria to be used for the 100-HR-3 and 100-KR-4 groundwater pump-and-treat design activities

  17. Pupil filter design by using a Bessel functions basis at the image plane.

    Science.gov (United States)

    Canales, Vidal F; Cagigal, Manuel P

    2006-10-30

    Many applications can benefit from the use of pupil filters for controlling the light intensity distribution near the focus of an optical system. Most of the design methods for such filters are based on a second-order expansion of the Point Spread Function (PSF). Here, we present a new procedure for designing radially-symmetric pupil filters. It is more precise than previous procedures as it considers the exact expression of the PSF, expanded as a function of first-order Bessel functions. Furthermore, this new method presents other advantages: the height of the side lobes can be easily controlled, it allows the design of amplitude-only, phase-only or hybrid filters, and the coefficients of the PSF expansion can be directly related to filter parameters. Finally, our procedure allows the design of filters with very different behaviours and optimal performance.

  18. Design basis and requirements for 241-SY Modular Exhauster concrete pad and retaining wall

    International Nuclear Information System (INIS)

    Kriskovich, J.R.

    1994-01-01

    The purpose of this document is to serve as the design and functional requirements for a concrete pad for the new 241-SY Modular Exhauster and for a retaining wall to be built near the new ventilation systems

  19. The neuroscientific basis of successful design how emotions and perceptions matter

    CERN Document Server

    Maiocchi, Marco

    2015-01-01

    The term “design” today encompasses attributes of artifacts that go beyond their intended functions, imbuing them with new meanings. Those meanings are deeply related to the emotions perceived by the users. This book investigates the findings deriving from the neurosciences that are relevant to design. Drawing upon up-to-date neuroscientific knowledge, the authors define what an emotion is, examine the relationship between perceptions and emotions, and discuss the role of metaphoric communication. Particular attention is paid to those elements of perception and metaphoric interpretation that cause the emotions to rise. Consequences for the design process are then considered, and a design process is proposed that takes into account emotional impacts as one of the goals. A solid scientific approach to the subject is maintained throughout, and understanding is facilitated by the inclusion of a rich collection of successful design artifacts, the emotional aspects of which are analyzed.

  20. Effect of standards on new equipment design by new international standards and industry restraints

    Science.gov (United States)

    Endelman, Lincoln L.

    1991-01-01

    The use of international standards to further trade is one of the objectives of creating a standard. By having form fit and function compatible the free interchange of manufactured goods can be handled without hindrance. Unfortunately by setting up standards that are peculiar to a particular country or district it is possible to exclude competition from a group of manufacturers. A major effort is now underway to develop international laser standards. In the May I 990 issue of Laser Focus World Donald R. Johnson the director of industrial technology services for the National Institute of Standards and Technology (NIST formerly the National Bureau of Standards) is quoted as follows: " The common means of protectionism has been through certification for the market place. " The article goes on to say " Mr. Johnson expects this tradition to continue and that the new European Community (EC) will demand not just safety standards but performance standards as well. . . . the American laser industry must move very quickly on this issue or risk being left behind the European standards bandwagon. " The article continues laser companies must get involved in the actual standards negotiating process if they are to have a say in future policy. A single set of standards would reduce the need to repeatedly recalibrate products for different national markets. " As a member of ISO TC-72 SC9 I am

  1. X-ray cinematographic determination of standard values of pharyngeal motility as a basis for diagnostic evaluation of pathologic changes

    International Nuclear Information System (INIS)

    Hannig, C.; Hess, U.

    1998-01-01

    The study was intended to reveal a normal bolus, yield standard values of the pharyngeal motility, define reference data and use them for verification with patient groups with known pathologic changes. Furthermore, the dependence of standard values on the physiological ageing process and various bolus volumina was tested. (orig./CB) [de

  2. SEDIMENT TOXICITY ASSESSMENT: COMPARISON OF STANDARD AND NEW TESTING DESIGNS

    Science.gov (United States)

    Standard methods of sediment toxicity testing are fairly well accepted; however, as with all else, evolution of these methods is inevitable. We compared a standard ASTM 10-day amphipod toxicity testing method with smaller, 48- and 96-h test methods using very toxic and reference ...

  3. Physics basis for an axicell design for the end plugs of MFTF-B

    Energy Technology Data Exchange (ETDEWEB)

    Baldwin, D.E.; Logan, B.G. (eds.)

    1982-04-21

    The primary motivation for conversion of MFTF-B to an axicell configuration lies in its engineering promise as a reactor geometry based on circular high-magnetic-field coils. In comparing this configuration to the previous A-cell geometry, we find a number of differences that might significantly affect the physics performance. The purpose of the present document is to examine those features and to assess their impact on the performance of the axicell, as compared to the A-cell configuration, for MFTF-B. In so doing, we address only those issues thought to be affected by the change in geometry and refer to the original report Physics Basis for MFTF-B, for discussion of those issues thought not to be affected. In Sec. 1, we summarize these physics issues. In Sec. 2, we describe operating scenarios in the new configuration. In the Appendices, we discuss those physics issues that require more detailed treatment.

  4. Target Area design basis and system performance for the National Ignition Facility. Revision 1

    International Nuclear Information System (INIS)

    Tobin, M.; Karpenko, V.; Hagans, K.; Anderson, A.; Latkowski, J.; Warren, R.; Wavrik, R.; Garcia, R.; Boyes, J.

    1994-10-01

    The NIF Target Area is designed to confine the ICF target experiments leading up to and including fusion ignition and gain. The Target Area will provide appropriate in-chamber conditions before, during, and after each shot. The repeated introduction of large amounts of laser energy into the chamber and emission of fusion energy from targets represents a new challenge in ICF facility design. Prior to a shot, the facility provides proper illumination geometry, target chamber vacuum, and a stable platform for the target and its diagnostics. During a shot, the impact of the energy introduced into the chamber is minimized, and workers and the public are protected from excessive prompt radiation doses. After the shot, the residual radioactivation is managed to allow required accessibility. Tritium and other radioactive wastes are confined and disposed of. Diagnostic data is also retrieved, and the facility is readied for the next shot. The Target Area will accommodate yields up to 20 MJ, and its design lifetime is 30 years. The Target Area provides the personnel access needed to support the use precision diagnostics. The annual shot mix for design purposes is shown. Designing to this experimental envelope ensures the ability and flexibility to move through the experimental campaign to ignition efficiently

  5. Control design on the basis of approximate nonlinear models: the inverted pendulum example

    DEFF Research Database (Denmark)

    Jouffroy, Jerome; Lottin, Jacques

    dealt with control of some classes of nonlinear systems. One of these families concerns flat systems for which it is possible to design reference trajectories that are admissible both for state variables and control input. However nonlinear plants may not exhibit such flatness properties since analysis...... is done in the whole state space. Since in many situations the process evolution is confined in a reduced domain, one solution consists in building an equivalent nonlinear model which exhibits flatness properties in order to use related control design tools. The inverted pendulum system is used...

  6. Higher Education Curricula Designing on the Basis of the Regional Labour Market Demands

    Science.gov (United States)

    Cai, Jing; Youngblood, Valery T.; Khodyreva, Elena A.; Khuziakhmetov, Anvar N.

    2017-01-01

    The relevance of the research problem is reasoned by the need to develop conceptual approaches and technologies for designing educational curricula based on current and prospective order for specialists' training from educational services' consumers--regional entities of the labor market. The goal of the article lies in justification of the…

  7. Path-Goal Models as a Basis for the Design of Organization Reward Systems.

    Science.gov (United States)

    Galbraith, Jay R.

    The purpose of this paper has been to argue the usefulness of path-goal models in theoretical research and practical design of organization reward systems. The reasoning is that the policy choices can be easily related to path-goal attitudes which, in turn, are related to behavior. The major policy choices were identified and related to path-goal…

  8. A Review of Knowledge Based Problem Solving as a Basis for a Genetics Experiment Designing System.

    Science.gov (United States)

    1977-03-01

    knowledge base. [Section IV.3.3.LI] 17. Ru l e acquisition has usea the problem solving context as well as a rule model to guide the acquisition of a 4...the design process continues , for example , cutting may become an exonuclease or separation may become electrophoresis . It is not too surprising that

  9. Reducing Production Basis Risk through Rainfall Intensity Frequency (RIF) Indexes: Global Sensitivity Analysis' Implication on Policy Design

    Science.gov (United States)

    Muneepeerakul, Chitsomanus; Huffaker, Ray; Munoz-Carpena, Rafael

    2016-04-01

    The weather index insurance promises financial resilience to farmers struck by harsh weather conditions with swift compensation at affordable premium thanks to its minimal adverse selection and moral hazard. Despite these advantages, the very nature of indexing causes the presence of "production basis risk" that the selected weather indexes and their thresholds do not correspond to actual damages. To reduce basis risk without additional data collection cost, we propose the use of rain intensity and frequency as indexes as it could offer better protection at the lower premium by avoiding basis risk-strike trade-off inherent in the total rainfall index. We present empirical evidences and modeling results that even under the similar cumulative rainfall and temperature environment, yield can significantly differ especially for drought sensitive crops. We further show that deriving the trigger level and payoff function from regression between historical yield and total rainfall data may pose significant basis risk owing to their non-unique relationship in the insured range of rainfall. Lastly, we discuss the design of index insurance in terms of contract specifications based on the results from global sensitivity analysis.

  10. Environment as a basis for the design of advertising structures by forming

    Science.gov (United States)

    Khmelevsky, Y. P.; Seryakov, V. A.; Mamontov, G. Y.; Tsarenko, D. T.

    2017-01-01

    A few different neighbouring styles of architectural forms are quite frequent in the cities of great historical past. As a result, a designer or architect has to solve the complex problem while designing the objects within such environment, i.e. one has to fit them naturally into the existing site development. Often, form making is found to be hard, due to the fact that the existing architectural forms of totally different stylistic execution coexist in the visual proximity. Presently, placement of the advertising bills in urban environment is both an urgent and debatable issue. On the one hand, advertising providers are keen to present their product bigger and brighter, on the other hand, the overall and eye-catching exhibition stands can be disharmonious with the surrounding architectural ensemble of the city. This situation is relevant for every cultural city.

  11. Modeling of Li-Ion Battery Packs as Basis for Design of Battery Thermal Management Systems

    DEFF Research Database (Denmark)

    Coman, Paul Tiberiu

    Li-ion batteries are one of the most popular battery types on the market, due to their prime properties such as high capacity, low self-discharge rate, zero-maintenance, high energy density and long lifetime. However, safety still remains a major drawback, due to overheating and thermal runaway...... conservation equations, and the results were compared against experimental data from the open literature; 2. A simplified thermal runaway model for investigating the propagation of thermal runaway in a battery pack designed by NASA for astronaut spacesuits. A simplified model was initially built for single...... battery cells with an internal short circuit device (ISCD) implanted inside, used for triggering thermal runaway at low temperatures. The simplified lumped model was then coupled with a 2D thermal FEM for investigating the pack design. The simplification consists of implementing an efficiency factor term...

  12. Beyond design basis external flooding. Generic design assessment and lessons learned from the Fukushima Dai-ichi accident

    International Nuclear Information System (INIS)

    MacLeod, Tanya; Smith, Leslie; Allmark, Tim; Ford, Peter

    2017-01-01

    New reactors intended for construction in GB undergo the Office for Nuclear Regulation's (ONR's) Generic Design Assessment (GDA). GDA is a pre-licensing process that provides requesting parties with the opportunity to demonstrate at an early stage that the design is capable of meeting the legal requirements of Great Britain. During GDA, the intended reactor site may not yet be known. Therefore, requesting parties usually define a 'Generic Site' with characteristics typical for Great Britain. These characteristics should, as far as possible, bound the characteristics of known potential sites so that reactors of the proposed type could potentially be built at various suitable locations. This paper critically reviews ONR's approach to ensuring that external flooding is appropriately addressed at the GDA stage and covers: An overview of ONR's approach to post-Fukushima assessment. Changes to ONR's SAPs (Safety Assessment Principles) related to External Flooding. Two examples of post-Fukushima GDA approaches to External Flooding. Uncertainty and the provision of adequate safety measures. The paper concludes that the identification of potential vulnerabilities in the design to external flooding combined with a consideration of post-Fukushima resilience enhancements has led to increased regulatory confidence in the robustness of new reactor designs in GB against external flooding. (author)

  13. Creep-Fatigue Life Design with Various Stress and Temperature Conditions on the Basis of Lethargy Coefficient

    International Nuclear Information System (INIS)

    Park, Jung Eun; Yang, Sung Mo; Han, Jae Hee; Yu, Hyo Sun

    2011-01-01

    High temperature and stress are encounted in power plants and vehicle engines. Therefore, determination of the creep-fatigue life of a material is necessary prior to fabricating equipment. In this study, life design was determined on the basis of the lethargy coefficient for different temperatures, stress and rupture times. SP-Creep test data was compared with computed data. The SP-Creep test was performed to obtain the rupture time for X20CrMoV121 steel. The integration life equation was considered for three cases with various load, temperature and load-temperature. First, the lethargy coefficient was calculated by using the obtained rupture stress and the rupture time that were determined by carrying out the SP-Creep test. Next, life was predicted on the basis of the temperature condition. Finally, it was observed that life decreases considerably due to the coupling effect that results when fatigue and creep occur simultaneously

  14. Eulerian Circles (Venn Diagrams) as model for modern economy education on the basis of Russian professional standards

    Science.gov (United States)

    Sharonov, M. A.; Sharonova, O. V.; Sharonova, V. P.

    2018-03-01

    The article is an attempt to create a model built using Eulerian circles (Venn diagrams) to illustrate the methodological impact of recent Federal Law 283-FZ “On the independent evaluation of qualifications” and new Federal State Educational Standards of higher education of generation 3++ on educational process in Russia. In modern economic conditions, the ability to correctly assess the role of professional standards, as a matter of fact, some set, the degree of intersection with the approximate basic educational program and the Federal State Educational Standards becomes an important factor on which in the future will depend not only the demand of graduates in the labor market, but also the possibility of passing the professional and public accreditation of the proposed program.

  15. 40 CFR 264.1101 - Design and operating standards.

    Science.gov (United States)

    2010-07-01

    ... to prevent the migration of hazardous constituents into the barrier (e.g., a geomembrane covered by a... containment system including a secondary barrier designed and constructed to prevent migration of hazardous...-site a certification by a qualified Professional Engineer that the containment building design meets...

  16. Windmills by Design: Purposeful Curriculum Design to Meet Next Generation Science Standards in a 9-12 Physics Classroom

    Science.gov (United States)

    Concannon, James; Brown, Patrick L.

    2017-01-01

    The "Next Generation Science Standards" (NGSS) challenges science teachers to think beyond specific content standards when considering how to design and implement curriculum. This lesson, "Windmills by Design," is an insightful lesson in how science teachers can create and implement a cross-cutting lesson to teach the concepts…

  17. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-18

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake`s ground motion is a function of the earthquake`s magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. Therefore, empirically based approaches that are used for other regions, such as Western North America, are not appropriate for Eastern North America. Moreover, recent advances in science and technology have now made it possible to combine theoretical and empirical methods to develop new procedures and models for estimating ground motion. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. Specifically considered are magnitudes M from 5 to 8, distances from 0 to 500 km, and frequencies from 1 to 35 Hz.

  18. Theoretical basis for unified analysis of experimental data and design of swelling-resistant alloys

    International Nuclear Information System (INIS)

    Mansur, L.K.; Lee, E.H.

    1991-01-01

    Essential aspects of the theory of radiation-induced swelling are reviewed. In particular, concepts central to the understanding of experimental data and the control of swelling by alloy design are discussed. The knowledge that a critical number of gas atoms is required in a cavity before point defect-driven swelling can begin is a most important contribution of theory. The mathematical expression that have been derived for calculating this critical quantity are given in terms of materials parameters and irradiation conditions. After swelling begins, its magnitude as a function of dose is governed strongly by the relative sink strengths for point defects of dislocations and cavities, expressed in terms of an index of the microstructure, Q. Hich swelling and low swelling microstructures can be categorized into four types based on this index. Wide ranges of experimental swelling results covering ferritic/martensite and austenitic alloys, neutron and ion irradiations and a variety of compositions and irradiation conditions are analyzed and found to be explained consistently within this framework. Based on the understanding gained, approaches to alloy design for swelling resistance are recommended. (orig.)

  19. Protein structures in Alzheimer's disease: The basis for rationale therapeutic design.

    Science.gov (United States)

    Montoliu-Gaya, Laia; Villegas, Sandra

    2015-12-15

    Alzheimer's disease (AD) is a neurodegenerative disorder that affects memory, behavior, thinking and emotion. Current therapies to treat AD patients are only capable for temporarily slowing-down the cognitive decline, as they are focused on ameliorating symptoms instead of targeting its underlying causes. The aim of this review is to describe what is known about the protein structures implicated in AD pathogenesis, amyloid cascade members, as well as those structures involved in Aβ clearance. Thus, structural information available for APP, α- β- and γ-secretases, CTFβ and derived Aβ peptides, AICDs, apoE and apoJ, LRP-1 and RAGE, and neprilysin and insulin-degrading enzyme is provided. The recently solved structure for the γ-secretase complex opens the rational design of a new generation of inhibitors, whereas that for Aβ oligomers offers a putative mechanism explaining why monoclonal antibodies targeted to the N-terminus are effective. Then, an overview on therapies targeting some of these molecules presents their benefits and drawbacks. As a general conclusion our knowledge on the protein structures involved in AD has recently substantially advanced, allowing for the rational design of different therapeutic approaches. Hopefully, we are getting closer to finding a strong disease-modifying drug to cure this devastating disease. Copyright © 2015 Elsevier Inc. All rights reserved.

  20. Design basis and requirements for 241-SY modular exhauster mechanical installation

    International Nuclear Information System (INIS)

    Kriskovich, J.R.

    1994-01-01

    A new ventilation system is being installed to serve as the K-1 primary exhauster. The existing K-1 primary exhauster will then become the backup. This ventilation system services waste tanks 241-SY-101, 102 and 103. The nominal flow rate through the ventilation system is 1,000 cfm. The new ventilation system will contain a moisture eliminator, a heater, a prefilter, two stages of HEPA filtration, an exhaust fan, a stack and stack sampling system. The purpose of this document is to serve as the design and functional requirements for the mechanical installation of the new 241-SY modular exhauster. The mechanical installation will include modifying the existing ductwork (i.e., installing a ''T'' to connect the new exhauster to the existing system), modifying the existing condensate drain lines to accommodate the new lines associated with the new exhauster, a maintenance platform near the stack of the new exhauster, guy wires and guy wire footings to support the stack of the new exhauster, as well as other miscellaneous tasks associated with the mechanical installation design effort

  1. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions

    International Nuclear Information System (INIS)

    1993-01-01

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake's ground motion is a function of the earthquake's magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. Therefore, empirically based approaches that are used for other regions, such as Western North America, are not appropriate for Eastern North America. Moreover, recent advances in science and technology have now made it possible to combine theoretical and empirical methods to develop new procedures and models for estimating ground motion. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. Specifically considered are magnitudes M from 5 to 8, distances from 0 to 500 km, and frequencies from 1 to 35 Hz

  2. Communication Standards Suitable for MES Systems Designed for SMES

    Directory of Open Access Journals (Sweden)

    Ondřej WINKLER

    2009-06-01

    Full Text Available A MES (Manufacturing Execution System is a system that large companies use to measure or control critical production activities. Individual parts of this system can be used as a model for development of tools suitable for small and medium enterprises (SMEs. It can demonstrate how manufacturing systems works and which communication standards are usable. The communication standards enable data acquisition, data processing, storing and their conversion for any production report. Furthermore, interfaces for web clients allow displaying the raw or transformed data as a text or a graphic chart. The development of tools for an access to the data retrieved from MES software is described in this paper.

  3. 7 CFR 1792.103 - Seismic design and construction standards for new buildings.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 12 2010-01-01 2010-01-01 false Seismic design and construction standards for new..., REGULATIONS, AND EXECUTIVE ORDERS Seismic Safety of Federally Assisted New Building Construction § 1792.103 Seismic design and construction standards for new buildings. (a) In the design and construction of...

  4. 40 CFR 267.1101 - What design and operating standards must my containment building meet?

    Science.gov (United States)

    2010-07-01

    ... dust emissions under § 267.1102(d). (2) The unit is designed and operated in a fashion that assures... 40 Protection of Environment 26 2010-07-01 2010-07-01 false What design and operating standards... FACILITIES OPERATING UNDER A STANDARDIZED PERMIT Containment buildings § 267.1101 What design and operating...

  5. Military Housing: Status of the Services' Implementation of the Current Barracks Design Standard

    National Research Council Canada - National Science Library

    1999-01-01

    .... In November 1995, DOD adopted a new barracks construction standard, referred to as the 1+1 design standard, that called for more space and increased privacy in new barracks for service members permanently assigned to an installation...

  6. Modeling of the Reactor Core Isolation Cooling Response to Beyond Design Basis Operations - Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Ross, Kyle [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Cardoni, Jeffrey N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wilson, Chisom Shawn [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Morrow, Charles [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Osborn, Douglas [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gauntt, Randall O. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-01

    Efforts are being pursued to develop and qualify a system-level model of a reactor core isolation (RCIC) steam-turbine-driven pump. The model is being developed with the intent of employing it to inform the design of experimental configurations for full-scale RCIC testing. The model is expected to be especially valuable in sizing equipment needed in the testing. An additional intent is to use the model in understanding more fully how RCIC apparently managed to operate far removed from its design envelope in the Fukushima Daiichi Unit 2 accident. RCIC modeling is proceeding along two avenues that are expected to complement each other well. The first avenue is the continued development of the system-level RCIC model that will serve in simulating a full reactor system or full experimental configuration of which a RCIC system is part. The model reasonably represents a RCIC system today, especially given design operating conditions, but lacks specifics that are likely important in representing the off-design conditions a RCIC system might experience in an emergency situation such as a loss of all electrical power. A known specific lacking in the system model, for example, is the efficiency at which a flashing slug of water (as opposed to a concentrated jet of steam) could propel the rotating drive wheel of a RCIC turbine. To address this specific, the second avenue is being pursued wherein computational fluid dynamics (CFD) analyses of such a jet are being carried out. The results of the CFD analyses will thus complement and inform the system modeling. The system modeling will, in turn, complement the CFD analysis by providing the system information needed to impose appropriate boundary conditions on the CFD simulations. The system model will be used to inform the selection of configurations and equipment best suitable of supporting planned RCIC experimental testing. Preliminary investigations with the RCIC model indicate that liquid water ingestion by the turbine

  7. Basis for the safety approach for design and assessment of Generation IV nuclear systems

    International Nuclear Information System (INIS)

    Fiorini, G.L.; Leahy, T.

    2009-01-01

    The primary objective of the RSWG is the implementation of a harmonized approach on long-term safety, and to address risk and regulatory issues in development of the next generation of nuclear systems. To this end, the group is proposing safety goals and evaluation methodology applicable for the design and assessment of future systems. The paper resumes the content of the first RSWG report which provides insights for the safety approach and assists the GIF Systems Steering Committee as well as the GIF Experts Group and the GIF Policy Group for the definition of the most adequate safety related Gen IV R and D. The document is also an essential contributor to help identifying the needed supportive crosscut R and D effort (i.e. applicable to all the innovative nuclear technologies). Although the report presents a number of thoughts and recommendations, it really represents only the start of the efforts for the RSWG. (author)

  8. TRAC analysis of design basis events for the accelerator production of tritium target/blanket

    International Nuclear Information System (INIS)

    Lin, J.C.; Elson, J.

    1997-01-01

    A two-loop primary cooling system with a residual heat removal system was designed to mitigate the heat generated in the tungsten neutron source rods inside the rungs of the ladders and the shell of the rungs. The Transient Reactor Analysis Code (TRAC) was used to analyze the thermal-hydraulic behavior of the primary cooling system during a pump coastdown transient; a cold-leg, large-break loss-of-coolant accident (LBLOCA); a hot-leg LBLOCA; and a target downcomer LBLOCA. The TRAC analysis results showed that the heat generated in the tungsten neutron source rods can be mitigated by the primary cooling system for the pump coastdown transient and all the LBLOCAs except the target downcomer LBLOCA. For the target downcomer LBLOCA, a cavity flood system is required to fill the cavity with water at a level above the large fixed headers

  9. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions. Volume 2, Appendices

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-18

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake`s ground motion is a function of the earthquake`s magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. This document, Volume II, contains Appendices 2, 3, 5, 6, and 7 covering the following topics: Eastern North American Empirical Ground Motion Data; Examination of Variance of Seismographic Network Data; Soil Amplification and Vertical-to-Horizontal Ratios from Analysis of Strong Motion Data From Active Tectonic Regions; Revision and Calibration of Ou and Herrmann Method; Generalized Ray Procedure for Modeling Ground Motion Attenuation; Crustal Models for Velocity Regionalization; Depth Distribution Models; Development of Generic Site Effects Model; Validation and Comparison of One-Dimensional Site Response Methodologies; Plots of Amplification Factors; Assessment of Coupling Between Vertical & Horizontal Motions in Nonlinear Site Response Analysis; and Modeling of Dynamic Soil Properties.

  10. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions

    International Nuclear Information System (INIS)

    1993-01-01

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake's ground motion is a function of the earthquake's magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. This document, Volume II, contains Appendices 2, 3, 5, 6, and 7 covering the following topics: Eastern North American Empirical Ground Motion Data; Examination of Variance of Seismographic Network Data; Soil Amplification and Vertical-to-Horizontal Ratios from Analysis of Strong Motion Data From Active Tectonic Regions; Revision and Calibration of Ou and Herrmann Method; Generalized Ray Procedure for Modeling Ground Motion Attenuation; Crustal Models for Velocity Regionalization; Depth Distribution Models; Development of Generic Site Effects Model; Validation and Comparison of One-Dimensional Site Response Methodologies; Plots of Amplification Factors; Assessment of Coupling Between Vertical ampersand Horizontal Motions in Nonlinear Site Response Analysis; and Modeling of Dynamic Soil Properties

  11. A comparison of the consequences of the design basis accident of the Greek Research Reactor with those of a serious realistic accident

    International Nuclear Information System (INIS)

    Kollas, J.G.; Anoussis, J.N.

    1985-12-01

    An analysis of the radiological consequences of the design basis and the coolant flow blockage accidents of the Greek Research Reactor is presented. The results indicate that the consequences of the coolant flow blockage accident are practically trivial being 1-2 orders of magnitude lower than the corresponding consequences of the design basis accident. (author)

  12. Design and testing of multi-standard waveguide couplers.

    Science.gov (United States)

    Beeson, S; Neuber, A

    2012-03-01

    Most applications that use waveguides are designed for a single frequency or single band of frequency, and thus the waveguide dimensions are chosen for single mode operation. In special cases where multiple frequencies across multiple bands are needed (i.e., probing the temporal response of decaying plasma using a cw source that is generated by a pulsed source), special techniques must be used in order to implement both sources into a single waveguide structure. This paper presents two types of couplers designed to implement x-band frequencies into an s-band system with a large coupling coefficient ( -10 dB) at the design frequency of 11 GHz. Along with a discussion on the design procedure, a detailed description on the parameter optimization and initial values estimation is presented. The custom waveguide structures were tested utilizing an Agilent E8364B PNA network analyzer, and showed reasonable agreement with the simulated performance over the frequency range of interest.

  13. History of Road Design Standards in LADOTD : Research Project Capsule

    Science.gov (United States)

    2012-10-01

    According to the Louisiana Statewide Transportation Plan, Louisianas highway : network is comprised of over 60,000 miles, of which over 16,000 miles are : maintained by the state. The roadways were designed and constructed : according to the desig...

  14. 40 CFR 265.1201 - Design and operating standards.

    Science.gov (United States)

    2010-07-01

    ... as designed and that releases that may adversely impact human health or the environment are not... products, or contaminated run-off, to the soil, ground water, surface water, and atmosphere; (2) Provide a...

  15. SOA and Web services interface design principles, techniques, and standards

    CERN Document Server

    Bean, James

    2009-01-01

    SOA offers solutions to the most intractable business problems faced by every enterprise, but getting the SOA service interface right requires the practical design knowledge this book uniquely delivers

  16. Romanian experience and approach in developing the design basis threat concept

    International Nuclear Information System (INIS)

    Ionescu, D.S.

    2002-01-01

    Full text: Physical protection systems required to protect the nuclear facilities and materials has to be able to respond at least to the design base threat (DBT). First, the DBT is defined as a minimum set of characteristics of a probable adversary in order to give to the security designer the necessary information to design the Physical Protection System (PPS) subsystems at least at the level to assure complete protection of the nuclear material and facilities against certain attacks. The secondary role of a DBT is to evaluate the effectiveness of an already built PPS facing with a threat having the general characteristic described by DBT. Romanian process to define the natural DBT started effectively with a workshop organized by AIEA and the Romanian Nuclear Regulatory Commission (CNCAN). There participated all the Romanian institution involved in the field of protection of nuclear material and facilities (Romanian Intelligence, Military, Police, CNCAN) as well the representatives of main nuclear operators. The workshop scope was to emphasize the methodology to build a DBT instead to define that. The participants were able to understand the necessary steps to define DBT and the importance of the teamwork. After that meeting, under CNCAN coordination started a process to achieve information from the state institution and nuclear operators. Various meeting has been held to refine the information achieved. Those meetings constituted an important step in the process, helping the parts to understand each other (before that, due to the different organizations where the participants come from was difficult to achieve a common language in this respect). Lots of specific or general analyses and materials have been evaluated, refined and integrated in a special report. Two main constrains of DBT has been identified: the DBT must be 'strong' enough to permit a powerful response of the PPS to any credible attack; also the DBT should consider the equilibrium between the

  17. Session 1 theme: Various forms of design basis knowledge and effects of its loss on Safety. Views from EDF

    International Nuclear Information System (INIS)

    Servière, Georges

    2013-01-01

    Design basis knowledge - What happens or may happen and corresponding required knowledge: • Unexpected events or failures of equipment; • Spare part issues (no longer availaible,…); • Change in applicable regulations / requirements; • Change of operating conditions; • Change of plant performances; • Evolution of external environment and conditions; • Events and accidents on other plants, worldwide; • New knowledge availaible; • Periodic safety reviews and upgrades; • Extension of plant operation life; • Decommissioning and dismantling; • Some of those you may choose not to do, but most of them have to be faced and need appropriate knowledge

  18. Passive dynamics is a good basis for robot design and control, not!

    Science.gov (United States)

    Ruina, Andy

    Many airplanes can, or nearly can, glide stably without control. So, it seems natural that the first successful powered flight followed from mastery of gliding. Many bicycles can, or nearly can, balance themselves when in motion. Bicycle design seems to have evolved to gain this feature. Also, we can make toys and 'robots' that, like a stable glider or coasting bicycle, stably walk without motors or control in a remarkably human-like way. Again, it seems to make sense to use `passive-dynamics' as a core for developing the control of walking robots and to gain understanding of the control of walking people. That's what I used to think. But, so far, this has not led to robust walking robots. What about human evolution? We didn't evolve dynamic bodies and then learn to control them. Rather, people had elaborate control systems way back when we were fish and even worms. However: if control is paramount, why is it that uncontrolled passive-dynamic walkers walk so much like humans? It seems that energy optimal, yet robust, control, perhaps a proxy for evolutionary development, arrives at solutions that have some features in common with passive-dynamics. Rather than thinking of good powered walking as passive walking with a small amount of control added, I now think of good powered walking, human or robotic, as highly controlled, while optimized for, in part, minimal actuator use. Thus, much of the motor effort, always at the ready, is usually titrated out.

  19. Contribution of the VISTA ITL program for the standard design approval of the SMART design

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun Sik; Chung, Young Jong; Joo, Hyung Kook; Lee, Won Jae; Kim, Hark Rho; Song, Chul Hwa; Yi, Sung Jae [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    A small scale integral effect test (IET) program had been performed by the Korea Atomic Energy Research Institute (KAERI) using the VISTA integral test loop (VISTA ITL). It has the simulation capability of small break loss of coolant accident (SBLOCA), complete loss of reactor coolant system (RCS) flow (CLOF) and passive residual heat removal system (PRHRS) performance for the SMART design. The reference plant of the VISTA ITL is a 330 MWth integral pressurized water reactor (iPWR), SMART, which was developed by KAERI. Its standard design had been approved by Korean regulatory authority on July 2012. The SMART reactor is characterized by the introduction of simplified and improved safety systems such as passive residual heat removal system (PRHRS) and its integral arrangement of the reactor vessel assembly. Integral reactor design eliminates the large size pipe connections between major components. Thus, it excludes the occurrence of a large break loss of coolant accident (LBLOCA), and a SBLOCA is one of major concerns for safety analysis. Therefore, the VISTA ITL was used to investigate various thermal hydraulic phenomena during the SBLOCA. The break flow rate, safety injection flow rate, and thermal hydraulic behaviors of major components were measured for a typical break size and break locations. The acquired data was used to validate related thermal hydraulic models of the safety analysis code, TASS/SMR S which is used to validate the safety of the SMART in coping with the SBLOCA scenarios. A set of tests for SBLOCAs, CLOF and PRHRS performance was performed to understand the general behavior and to assess its safety of the SMART design using the VISTA ITL facility. The test results were used to validate the TASS/SMR S code. This paper also introduces regulatory issues concerning the VISTA ITL tests and how they were resolved. The scoping analysis was performed in resolving regulatory issues using a best estimate system analysis code, MARS KS developed by KAERI.

  20. Design and Characterization of Vertical Mesh Capacitors in Standard CMOS

    DEFF Research Database (Denmark)

    Christensen, Kåre Tais

    2001-01-01

    This paper shows how good RF capacitors can be made in a standard digital CMOS process. The capacitors which are also well suited for binary weighted switched capacitor banks show very good RF performance: Q-values of 57 at 4.0 GHz, a density of 0.27 fF/μ2, 2.2 μm wide shielded unit capacitors, 6...

  1. Strategy for standardization of preeclampsia research study design.

    Science.gov (United States)

    Myatt, Leslie; Redman, Christopher W; Staff, Anne Cathrine; Hansson, Stefan; Wilson, Melissa L; Laivuori, Hannele; Poston, Lucilla; Roberts, James M

    2014-06-01

    Preeclampsia remains a major problem worldwide for mothers and babies. Despite intensive study, we have not been able to improve the management or early recognition of preeclampsia. At least part of this is because of failure to standardize the approach to studying this complex syndrome. It is possible that within the syndrome there may be different phenotypes with pathogenic pathways that differ between the subtypes. The capacity to recognize and to exploit different subtypes is of obvious importance for prediction, prevention, and treatment. We present a strategy for research to study preeclampsia, which will allow discrimination of such possible subtypes and also allow comparison and perhaps combinations of findings in different studies by standardized data and biosample collection. To make studies relevant to current clinical practice, the definition of preeclampsia can be that currently used and accepted. However, more importantly, sufficient data should be collected to allow other diagnostic criteria to be used and applied retrospectively. To that end, we present what we consider to be the minimum requirements for a data set in a study of preeclampsia that will facilitate comparisons. We also present a comprehensive or optimal data set for in-depth investigation of pathophysiology. As we approach the definition of phenotypes of preeclampsia by clinical and biochemical criteria, adherence to standardized protocols will hasten our understanding of the causes of preeclampsia and development of targeted treatment strategies.

  2. Design basis for the copper/steel canister. Stage four. Final report

    International Nuclear Information System (INIS)

    Bowyer, W.H.

    1998-06-01

    The development of the copper/iron canister which has been proposed by SKB for the containment of high level nuclear waste has been studied from the points of view of choice of materials, manufacturing technology and quality assurance. Cast steel has been rejected in favour of cast iron as a candidate material for the load bearing liner. Nodular (or ductile) iron is selected and this is capable of providing mechanical properties which are equally suitable as those of the originally selected high strength low alloy steel. The material specified for the overpack is Oxygen free copper with 50 ppm of phosphorus added. Corrosion studies supported by SKB indicate that in the absence of mechanical failure or accelerated localised corrosion the overpack should provide corrosion shielding of the canister for its full design life. Published work claiming that the nodular iron liner would have corrosion characteristics similar to the carbon steel which had been examined in depth is flawed since the microstructures of the iron and carbon steel specimens used were not investigated. It is highly unlikely that nodular irons in the form used for the experiments would have similar structures to nodular iron in the canisters by chance. If the overpack were breached during the aerobic period of the repository life then very rapid penetration of the inner liner could occur. It has been recognised that the roll forming method is not suitable for serial production and alternatives are being sought. The electron beam welding process has been explored with tenacity but has so far failed to produce a satisfactory lid weld. A new welder is being developed for supply to the SKB pilot plant where development will be continued. An alternative welding process, friction stir welding, is being examined as a candidate for attaching lids. Surface breaking defects may be detected using eddy current methods but there is currently no reliable way of detecting small sub surface defects in the overpack

  3. Design basis for the copper/steel canister. Stage five. Final report

    International Nuclear Information System (INIS)

    Bowyer, W.H.

    1999-05-01

    The development of the copper/iron canister which has been proposed by SKB for the containment of high level nuclear waste in the Swedish Program, has been studied by the present author from the points of view of choice of materials, manufacturing technology and quality assurance. This report describes the observations on progress that has been made between May-1-1998 and April-30-1999 and the result of further literature studies. Cast steel has been rejected in favour of cast iron as a candidate material for the load bearing liner. The nodular iron that was selected has been the subject of casting trials at several foundries. Early trials, using uphill feeding, met with limited success owing to difficulties feeding during solidification. Lessons from this trial led to a modification to the casting design to include extra cores that have the effect of reducing the need for feeding in the heaviest sections. Results using the new design and direct (downhill) casting are very promising. Castings appear to be sound and mechanical test results cast-on bars are within specification. Tensile test results from specimens cut from the casting have reduced ductility compared with the cast-on bars and this may be evidence of microstructural variations within the casting. The material specified for the overpack is OF (Oxygen Free) copper with 50 ppm of phosphorus added. Concentration limits have now been placed on impurity elements which are below those allowed in the OF specification. All current trials are using material from Outokompu produced from cathode on their OF(E) line, which delivers total impurity levels of less than 30 ppm excluding silver and phosphorus. The phosphorus addition is made using a master alloy added to the launder and this does not give good control of phosphorus level either within or between castings. Phosphorus is added to improve creep rates and creep strain to failure. The level is limited to 50 ppm in order to avoid difficulties, which it might

  4. Inter-regional Knowledge Management Workshop on Life-cycle Management of Design Basis Information – Issues, Challenges, Approaches. Presentations

    International Nuclear Information System (INIS)

    2013-01-01

    This Workshop had a strategic focus on identifying and clarifying long-term issues and objectives related to our collective responsibilities to ensure that both existing nuclear facilities and future new build projects properly address life-cycle management of plant design basis knowledge (i.e. from design to decommissioning). The workshop attempted to bring together key stakeholders and build a better collective understanding, recognizing that very different perspectives exist and there are a wide range of national contexts and approaches. The various issues and challenges related to this topic and facing the nuclear energy sector both today and in the long-term were discussed in a senior management context and at strategic level

  5. Critical analysis of accident scenario and consequences modelling applied to light-water reactor power plants for accident categories beyond the design basis accident (DBA)

    International Nuclear Information System (INIS)

    Brofferio, C.; Cagnetti, P.; Ferrara, V.; Manilia, E.; Pietrangeli, G.; Sennis, C.

    1985-01-01

    A critical analysis and sensitivity study of the modelling of accident scenarios and environmental consequences are presented, for light-water reactor accident categories beyond the standard design-basis-accident category. The first chapter, on ''source term'' deals with the release of fission products from a damaged core inventory and their migration within the primary circuit and the reactor containment. Particular attention is given to the influence of engineering safeguards intervention and of the chemical forms of the released fission products. The second chapter deals with their release to the atmosphere, transport and wet or dry deposition, outlining relevant partial effects and confronting short-duration or prolonged releases. The third chapter presents a variability analysis, for environmental contamination levels, for two extreme hypothetical scenarios, evidencing the importance of plume rise. A numerical plume rise model is outlined

  6. Designation Of The Standard Stratotype And Age Of Nsukka ...

    African Journals Online (AJOL)

    The type locality of Nsukka Formation was designated north of Nsukka in an area along Nadu River, without any formal description of the type section. Field mapping of the type locality was undertaken with the intention to formally define the type section. The thickest and best exposed is a 40 meter thick, stream section at ...

  7. The development of an ergonomics standard for the design of operator interfaces

    International Nuclear Information System (INIS)

    Kirwan, B.; Reed, J.; Litherland, M.

    1990-01-01

    BNFL has realised the need to take a consistent approach to the ergonomic design of operator interfaces. Towards this aim, a design standard document has been produced under the direction of a principal design engineer based on the key ergonomics aspects of plant design. The standard was requested by the designers, and the original standard was produced by ergonomists working on BNFL projects. This standard was then reviewed by a large number of key design and operations personnel, and a series of multidisciplinary meetings produced the final version. The standard contains six sections (ergonomics requirements for the design of Control Rooms, Consoles and Panels Design, Labelling, VDU Systems, Alarm Systems and Colour Coding) containing approximately 180 guidelines in text format or supplemented by diagrams and tables. Each guideline is classified as either mandatory or advisory. A high proportion of effort concentrated on making the document usable by designers. The standard is not intended to be fully comprehensive, since the range of possible variations in the designs of interfaces makes such a task intractable at this stage. However, the document does ensure that account is taken of ergonomics throughout the design phase, and particularly in the early phases whilst design change is still cost-effective, and that designers are aware of the important issues and principles. (author)

  8. Russian standards and design practice of ensuring NPP reliability under severe external loading conditions

    International Nuclear Information System (INIS)

    Birbraer, A.N.

    1993-01-01

    Russian Standards and design practice of ensuring NPP reliability under severe external loading conditions are described. The main attention is paid to the seismic design requirements. Explosions, aircraft impact, and tornado are briefly examined too (author)

  9. Designing a program for developing professional teacher-training reflection of futureteachers on the basis of a reflexive activity approach

    Directory of Open Access Journals (Sweden)

    Aset A. Bekhoeva

    2017-03-01

    Full Text Available The paper describes the experience of designing a program for developing professional teacher-training reflection and its practical approbation. The main trends of the study of professional teacher-training reflection in Russian psychological pedagogical science are described, the approaches to the description of methods and techniques that contribute to the development of professional teacher-training reflection in students are disclosed, and the conditions for its development are listed on the basis of literary data. Based on the review of the available research, it is necessary to search for a theoretical and methodological foundations for designing the development of professional teacher-training reflection in future teachers. The author proposes a reflexive activity approach. The program developed on the basis of this approach assumes a change in modeling classes on the main subjects of the psychological and pedagogical cycle, and on the other hand, the introduction of an innovative educational complex aimed at consolidating the competences received. The complex received the title of «Fundamentals of Personality-Oriented Learning». The paper describes the technology of modeling training sessions and the principles of building an educational complex. Approbation of the program was held on the basis of Khetagurov North Ossetian State University. The control and experimental group included third and fourth year university students (N= 342. A diagnostic tool was developed to assess the levels of reflection, reflexive abilities and self-esteem. Analysing experimental work has shown that the students of the experimental group have a significant increase in the level of each of the reflection components, which confirms the effectiveness of the proposed approach to the development of professional teacher-training reflection of future teachers.

  10. Design and Characterization of Vertical Mesh Capacitors in Standard CMOS

    OpenAIRE

    Christensen, Kåre Tais

    2001-01-01

    This paper shows how good RF capacitors can be made in a standard digital CMOS process. The capacitors which are also well suited for binary weighted switched capacitor banks show very good RF performance: Q-values of 57 at 4.0 GHz, a density of 0.27 fF/μ2, 2.2 μm wide shielded unit capacitors, 6% bottom plate capacitance, better than 3-5% process variation and negligible series inductance. Further, a simple yet accurate method is presented that allows hand calculation of the capacitance valu...

  11. A preliminary study on the design in architecture of nuclear and radiation safety standard system

    International Nuclear Information System (INIS)

    Song Dahu; Zhang Chi; Yang Lili; Li Bin; Liu Yingwei; An Hongzhen; Gao Siyi; Liu Ting; Meng De

    2014-01-01

    The connotation and function of nuclear and radiation safety standards are analyzed, and their relationships with the relevant laws and regulations are discussed in the paper. Some suggestions and blue print of overall architecture to build nuclear and radiation safety standard system are proposed, on the basis of researching the application status quo, existing problems and needs for nuclear and radiation safety standards in China. This work is a beneficial exploration and attempt to establish China's nuclear and radiation safety standards. (authors)

  12. Correcting bias from the standard linear adjustment of weaning weight to an age-constant basis for beef calves.

    Science.gov (United States)

    Rossi, D J; Kress, D D; Tess, M W; Burfening, P J

    1992-05-01

    Standard linear adjustment of weaning weight to a constant age has been shown to introduce bias in the adjusted weight due to nonlinear growth from birth to weaning of beef calves. Ten years of field records from the five strains of Beefbooster Cattle Alberta Ltd. seed stock herds were used to investigate the use of correction factors to adjust standard 180-d weight (WT180) for this bias. Statistical analyses were performed within strain and followed three steps: 1) the full data set was split into an estimation set (ES) and a validation set (VS), 2) WT180 from the ES was used to develop estimates of correction factors using a model including herd (H), year (YR), age of dam (DA), sex of calf (S), all two and three-way interactions, and any significant linear and quadratic covariates of calf age at weaning deviated from 180 d (DEVCA) and interactions between DEVCA and DA, S or DA x S, and 3) significant DEVCA coefficients were used to correct WT180 from the VS, then WT180 and the corrected weight (WTCOR) from the VS were analyzed with the same model as in Step 2 and significance of DEVCA terms were compared. Two types of data splitting were used. Adjusted R2 was calculated to describe the proportion of total variation of DEVCA terms explained for WT180 from the ES. The DEVCA terms explained .08 to 1.54% of the total variation for the five strains. Linear and quadratic correction factors were both positive and negative. Bias in WT180 from the ES within 180 +/- 35 d of age ranged from 2.8 to 21.7 kg.(ABSTRACT TRUNCATED AT 250 WORDS)

  13. Predicting casualty-accident count by highway design standards compliance

    Directory of Open Access Journals (Sweden)

    Arief Rizaldi

    2017-09-01

    This study has several findings. First, the constant values of the prediction model are relatively close to the average number of accident which implies that the mere compliance to current standard cannot warrant the safeness of Indoensian highways. Second, the number of median opening per unit length and disturbance level to pedestrian and road reserve area are the features that having positive relationships with total accident count. Meanwhile, the ROW disturbance, conformance of intersection and of road marking also show significant value but negative relationship with total accident count. Third, significant variables for each type of crash may have different sign. For example, in right angle crash, median width has positive relation with the number of accident, while in run off and rear end crash, median width compliance is shown to have negative relation.

  14. PWR-related integral safety experiments in the PKL 111 test facility SBLOCA under beyond-design-basis accident conditions

    Energy Technology Data Exchange (ETDEWEB)

    Weber, P.; Umminger, K.J.; Schoen, B. [Siemens AG Power Generation Group (KWU), Erlangen (France)

    1995-09-01

    The thermal hydraulic behavior of a PWR during beyond-design-basis accident scenarios is of vital interest for the verification and optimization of accident management procedures. Within the scope of the German reactor safety research program experiments were performed in the volumetrically scaled PKL 111 test facility by Siemens/KWU. This highly instrumented test rig simulates a KWU-design PWR (1300 MWe). In particular, the latest tests performed related to a SBLOCA with additional system failures, e.g. nitrogen entering the primary system. In the case of a SBLOCA, it is the goal of the operator to put the plant in a condition where the decay heat can be removed first using the low pressure emergency core cooling system and then the residual heat removal system. The experimental investigation presented assumed the following beyond-design-basis accident conditions: 0.5% break in a cold leg, 2 of 4 steam generators (SGs) isolated on the secondary side (feedwater- and steam line-valves closed), filled with steam on the primary side, cooldown of the primary system using the remaining two steam generators, high pressure injection system only in the two loops with intact steam generators, if possible no operator actions to reach the conditions for residual heat removal system activation. Furthermore, it was postulated that 2 of the 4 hot leg accumulators had a reduced initial water inventory (increased nitrogen inventory), allowing nitrogen to enter the primary system at a pressure of 15 bar and nearly preventing the heat transfer in the SGs ({open_quotes}passivating{close_quotes} U-tubes). Due to this the heat transfer regime in the intact steam generators changed remarkably. The primary system showed self-regulating system effects and heat transfer improved again (reflux-condenser mode in the U-tube inlet region).

  15. Design of nuclear spectroscopy electronics based on the EUROsystem standard

    International Nuclear Information System (INIS)

    Pahor, J.

    1987-11-01

    The development of modular nuclear instruments in the EUROcard system has been continued by the design of a staircase generator; such an instrument is needed for accurate testing of spectroscopy amplifiers. The generator provides very precisely defined steps with the period between them varying from 8 to 50 microseconds, the output voltage continuously variable from 2 to 5 V, and attenuated ion steps between 1 and 100. Great care was taken that individual steps exhibit no overshot, thus providing a very clean signal to the input of a tested amplifier. The circuitry is kept simple, and it can be easily constructed in any electronics laboratory. Figs

  16. 75 FR 63462 - Smart Grid Interoperability Standards; Notice of Docket Designation for Smart Grid...

    Science.gov (United States)

    2010-10-15

    ... Energy Regulatory Commission Smart Grid Interoperability Standards; Notice of Docket Designation for Smart Grid Interoperability Standards October 7, 2010. 1. The Energy Independence and Security Act of... interoperability of smart grid devices and systems, including protocols and model standards for information...

  17. How Adults Learn Forms the Foundation of the Learning Designs Standard

    Science.gov (United States)

    Drago-Severson, Eleanor

    2011-01-01

    Learning Forward's new Learning Designs standard is an important reminder that shaping professional learning as opportunities for adults to learn and grow is essential and that one's understanding of how adults learn is an essential component of this pressing goal. This article discusses the three strands of the Learning Designs standard: (1)…

  18. Design and analysis of control charts for standard deviation with estimated parameters

    NARCIS (Netherlands)

    Schoonhoven, M.; Riaz, M.; Does, R.J.M.M.

    2011-01-01

    This paper concerns the design and analysis of the standard deviation control chart with estimated limits. We consider an extensive range of statistics to estimate the in-control standard deviation (Phase I) and design the control chart for real-time process monitoring (Phase II) by determining the

  19. 23 CFR 661.53 - What standards should be used for bridge design?

    Science.gov (United States)

    2010-04-01

    ... 23 Highways 1 2010-04-01 2010-04-01 false What standards should be used for bridge design? 661.53... TRAFFIC OPERATIONS INDIAN RESERVATION ROAD BRIDGE PROGRAM § 661.53 What standards should be used for bridge design? (a) Replacement—A replacement structure must meet the current geometric, construction and...

  20. Standard guide for general design considerations for hot cell equipment

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    1.1 Intent: 1.1.1 The intent of this guide is to provide general design and operating considerations for the safe and dependable operation of remotely operated hot cell equipment. Hot cell equipment is hardware used to handle, process, or analyze nuclear or radioactive material in a shielded room. The equipment is placed behind radiation shield walls and cannot be directly accessed by the operators or by maintenance personnel because of the radiation exposure hazards. Therefore, the equipment is operated remotely, either with or without the aid of viewing. 1.1.2 This guide may apply to equipment in other radioactive remotely operated facilities such as suited entry repair areas, canyons or caves, but does not apply to equipment used in commercial power reactors. 1.1.3 This guide does not apply to equipment used in gloveboxes. 1.2 Applicability: 1.2.1 This guide is intended for persons who are tasked with the planning, design, procurement, fabrication, installation, or testing of equipment used in rem...

  1. C. F. Braun. Standard turbine island design, safety analysis report

    International Nuclear Information System (INIS)

    1974-01-01

    A standard turbine island used with a BWR is described. It consists of the turbine-generator; steam system; condensate storage, cleanup, and transfer systems; control and instrumentation; water treatment plant; make-up demineralizer; potable and waste water systems; and a compressed air system. The turbine-generator is a tandem-compound nuclear-type turbine with one double-flow high-pressure section and a six-flow low-pressure section in three double-flow low-pressure casings. The turbine is direct connected to an 1800 rpm synchronous a-c generator. A combined moisture separator and two-stage reheater is provided. The main steam system delivers the steam generated in a BWR to the main turbine stop valves. The condensate system maintains proper water inventory. Protective features prevent loss of the system due to electrical failure of a component and isolates faults to ensure continuity of a power supply from alternate sources. (U.S.)

  2. Conceptual design considerations for providing hook-up type schemes for tracking beyond design basis events (BDBE) for 700 MWe PHWR project

    International Nuclear Information System (INIS)

    Vhora, S.F.; Inder Jit; Bhardwaj, S.A.

    2005-01-01

    A broad review of major nuclear accidents such as Chernobyl reveals that provision of access to the reactor core for cooling purpose had to be made from outside the reactor building by tunneling. Also the NAPS fire incident could be mitigated once the fire water injection to the steam generators could be ensured. In this case the boiler room which was outside the primary containment was accessible relatively easily for mitigation after the initial period. Both of the above had accident scenarios which can be termed Beyond Design Basis (BDBE) since the accident initiation/scenario did not fit into the events under postulated initiating events (PIES) or Design Basis Events (DBEs). These accidents or events reveal that some sort of access to the core or the components inside the Reactor building becomes necessary. It is also to be noted that manual intervention beyond the initial period of half an hour or earlier in the Emergency operating procedure (EOP) is inevitably called for as a recovery action in order to mitigate the severity and minimize long term consequences. This paper attempts to discuss the type of concepts which can give access to the core or associated systems which can then provide continued heat sink. The discussions would include the criteria for design of such concepts and give examples of such concepts already implemented and proposes schemes to be implemented in the 700 MWe Project. (author)

  3. Accuracy of Gallagher’s Classification in Detecting Overweightness and Obesity on the Basis of World Health Organization Gold Standards Cutoff Points

    Directory of Open Access Journals (Sweden)

    A.S. Jahanlou

    2015-04-01

    Full Text Available Introduction & Objective: In the year 2000, Gallagher presented a new classification for body mass on the basis of the Percentile of Body Fat (PBF, age, and sex. The World Health Organization defines gold standard for obesity as PBF>25% in men and >35% in women. The primary purpose of the study was to evaluate the accuracy of Gallagher’s classification in detecting overweightness and obesity on the basis of WHO gold standard cutoff points. Materials & Methods: In this cross sectional- descriptive study the sample consisted of 20163 adults. Body composition measures were obtained, using the Bioelectrical Impedance Analysis (BIA. The detection of obesity was done by computing sensitivity, specificity, Positive Predictive Power (PPV and Negative Predictive Power (NPV for various age and sex groups. Results: There were 14270 women and 5893 men, ranging in age from 18 to 85 years, who participated in the study between 2009 and 2014. On the basis of Gallagher’s classification, 2549 (43.2% men and 2992 (21% women were obese. The WHO gold standard cutoff points showed that 7126 (49.9% women and 3208 men (54.4% met the criteria for being classified as obese. The sensitivity ranged from 53.9% to 100% in males and 38% to 85% in females. The range of specificity among males was from 99.4% to 100%; it was 100% among females. The NPV ranged from 29.8% to 100% in males and 14.1% to 84.3% in females.The PPV ranged from 99.8% to 100 in males and it was 100% in females. Among females, the increase in age was associated with decrease in sensitivity and NPV. Conclusion: Gallagher’s classification is accurate in detecting overweightness and obesity among males between the ages of 18 and 40; however, it is questionable among females. (Sci J Hamadan Univ Med Sci 2015; 22 (1:48-54

  4. NASA-STD-4005 and NASA-HDBK-4006, LEO Spacecraft Solar Array Charging Design Standard

    Science.gov (United States)

    Ferguson, Dale C.

    2007-01-01

    Two new NASA Standards are now official. They are the NASA LEO Spacecraft Charging Design Standard (NASA-STD-4005) and the NASA LEO Spacecraft Charging Design Handbook (NASA-HDBK-4006). They give the background and techniques for controlling solar array-induced charging and arcing in LEO. In this paper, a brief overview of the new standards is given, along with where they can be obtained and who should be using them.

  5. Developing Standards for Breakthrough Therapy Designation in Oncology

    Science.gov (United States)

    Horning, Sandra J.; Haber, Daniel A.; Selig, Wendy K.D.; Ivy, S. Percy; Roberts, Samantha A.; Allen, Jeff D.; Sigal, Ellen V.; Sawyers, Charles L.

    2013-01-01

    In July 2012, Congress passed the Food and Drug Administration Safety and Innovation Act (FDASIA). The Advancing Breakthrough Therapies for Patients Act was incorporated into a Title of FDASIA to expedite clinical development of new, potential “breakthrough” drugs or treatments that show dramatic responses in early phase studies. Using this regulatory pathway, once a promising new drug candidate is designated as a “Breakthrough Therapy”, the FDA and sponsor would collaborate to determine the best path forward to abbreviate the traditional three-phase approach to drug development. The breakthrough legislation requires that an FDA Guidance be drafted that details specific requirements of the bill to aid FDA in implementing requirements of the Act. In this article, we have proposed criteria to define a product as a Breakthrough Therapy, and discussed critical components of the development process that would require flexibility in order to enable expedited development of a Breakthrough Therapy. PMID:23719260

  6. Exemplary Design Envelope Specification for Standard Modular Hydropower Technology

    Energy Technology Data Exchange (ETDEWEB)

    Witt, Adam M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Smith, Brennan T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Tsakiris, Achilleas [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States); Papanicolaou, Thanos [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States); Pries, Jason L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Burress, Timothy A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Stewart, Kevin M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Lee, Kyutae [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); DeNeale, Scott T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bevelhimer, Mark S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Pracheil, Brenda M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); McManamay, Ryan A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ekici, Kivanc [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States); Kutz, Benjamin [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States); Curd, Shelaine L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bishop, Norm [Knight Piesold, Denver, CO (United States); Welch, Tim [U.S. Department of Energy (DOE), Washington, DC (United States). Office of Energy Efficiency and Renewable Energy (EERE); Rabon, Daniel [U.S. Department of Energy (DOE), Washington, DC (United States). Office of Energy Efficiency and Renewable Energy (EERE); Fernandez, Alisha [McKeown and Associates, Moberly, MO (United States)

    2017-02-01

    Hydropower is an established, affordable renewable energy generation technology supplying nearly 18% of the electricity consumed globally. A hydropower facility interacts continuously with the surrounding water resource environment, causing alterations of varying magnitude in the natural flow of water, energy, fish, sediment, and recreation upstream and downstream. A universal challenge in facility design is balancing the extraction of useful energy and power system services from a stream with the need to maintain ecosystem processes and natural environmental function. On one hand, hydroelectric power is a carbon-free, renewable, and flexible asset to the power system. On the other, the disruption of longitudinal connectivity and the artificial barrier to aquatic movement created by hydraulic structures can produce negative impacts that stress fresh water environments. The growing need for carbon-free, reliable, efficient distributed energy sources suggests there is significant potential for hydropower projects that can deploy with low installed costs, enhanced ecosystem service offerings, and minimal disruptions of the stream environment.

  7. Design basis threat analysis and implementation of the physical protection system at Nuclear Facility of BATAN Yogyakarta

    International Nuclear Information System (INIS)

    Syarip

    2005-01-01

    An analysis to determine the design basis threat (DBT) and its follow-up through the implementation of physical protection system at the nuclear facility of BATAN Yogyakarta has been done. Methodology used for the analysis is based on the IAEA guidance for the development and maintenance of a DBT. Based on the analysis results, it can be concluded that the threat motivation is influenced by political situation (related to the government policy), criminal, sabotage and theft. The characteristics of threats are: not so well organized, terror, theft of materials information, involving insider (collusion), and intimidation to workers. Potential threat could from guests/students who take a practical job or laboratory exercise. Therefore, it is necessary to be anticipated the possibility and its impact of turmoil/demonstrators such as destruction of: lighting, road, fence, sabotage on the electric and communication lines, surrounding the Yogyakarta nuclear facility

  8. Extending the application range of a fuel performance code from normal operating to design basis accident conditions

    International Nuclear Information System (INIS)

    Van Uffelen, P.; Gyori, C.; Schubert, A.; Laar, J. van de; Hozer, Z.; Spykman, G.

    2008-01-01

    Two types of fuel performance codes are generally being applied, corresponding to the normal operating conditions and the design basis accident conditions, respectively. In order to simplify the code management and the interface between the codes, and to take advantage of the hardware progress it is favourable to generate a code that can cope with both conditions. In the first part of the present paper, we discuss the needs for creating such a code. The second part of the paper describes an example of model developments carried out by various members of the TRANSURANUS user group for coping with a loss of coolant accident (LOCA). In the third part, the validation of the extended fuel performance code is presented for LOCA conditions, whereas the last section summarises the present status and indicates needs for further developments to enable the code to deal with reactivity initiated accident (RIA) events

  9. Calculation of particulate dispersion in a design-basis tornadic storm from the Battelle Memorial Institute, Columbus, Ohio

    International Nuclear Information System (INIS)

    Pepper, D.W.

    1980-10-01

    A three-dimensional numerical model is used to calculate ground-level air concentration and deposition (due to precipitation scavenging) after a hypothetical tornado strike at the Battelle Memorial Institute at Columbus, Ohio. Plutonium particles less than 20 μm in diameter are assumed to be lifted into the tornadic storm cell by the vortex. The rotational characteristics of the tornadic storm are embedded within the larger mesoscale flow of the storm system. The design-basis translational wind value is based on probabilities associated with existing records of tornado strikes in the vicinity of the plant site. Turbulence exchange coefficients are based on empirical values deduced from experimental data in severe storms and from theoretical assumptions obtained from the literature. The method of moments is used to incorporate subgrid-scale resolution of the concentration within a grid cell volume

  10. Calculation of particulate dispersion in a design-basis tornadic storm from the Babcock and Wilcox Plant, Leechburg, Pennsylvania

    International Nuclear Information System (INIS)

    Pepper, D.W.

    1978-03-01

    A three-dimensional numerical model is used to calculate ground-level air concentration and deposition (due to precipitation scavenging) after a hypothetical tornado strike at the Babcock and Wilcox Plutonium Fabrication Facility at Leechburg, Pennsylvania. Plutonium particles lss than 20 μm in diameter are assumed to be lifted into the tornadic storm cell by the vortex. The rotational characteristics of the tornadic storm are embedded within the larger mesoscale flow of the storm system. The design-basis translational wind values are based on probabilities associated with existing records of tornado strikes in the vicinity of the plant site. Turbulence exchange coefficients are based on empirical values deduced from experimental data in severe storms and from theoretical assumptions obtained from the literature. The quasi-Lagrangian method of moments is used to model the transport of concentration within a grid cell volume

  11. Regulatory analysis for the resolution of Generic Issue 82, ''Beyond design basis accidents in spent fuel pools''

    International Nuclear Information System (INIS)

    Throm, E.D.

    1989-04-01

    Generic Issue 82, ''Beyond Design Basis Accidents in Spent Fuel Pools,'' addresses the concerns with the use of high density storage racks for the storage of spent fuel, and is applicable to all Light Water Reactor spent fuel pools. This report presents the regulatory analysis for Generic Issue 82. It includes (1) a summary of the issue, (2) a summary of the technical findings, (3) the proposed technical resolution, (4) alternative resolutions considered by the Nuclear Regulatory Commission, (5) an assessment of the benefits and cost of the alternatives considered, (6) the decision rationale, and (7) the relationships between Generic Issue 82 and other NRC programs and requirements. Based on this evaluation, the NRC staff concludes that no new regulatory requirements are warranted concerning the use of high density storage racks. 48 refs., 32 tabs

  12. After Action Report:Idaho National Laboratory (INL) 2014 Multiple Facility Beyond Design Basis (BDBE) Evaluated Drill October 21, 2014

    Energy Technology Data Exchange (ETDEWEB)

    Barnes, V. Scott [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-12-01

    On October 21, 2014, Idaho National Laboratory (INL), in coordination with local jurisdictions, and Department of Energy (DOE) Idaho Operations Office (DOE ID) conducted an evaluated drill to demonstrate the ability to implement the requirements of DOE O 151.1C, “Comprehensive Emergency Management System” when responding to a beyond design basis event (BDBE) scenario as outlined in the Office of Health, Safety, and Security Operating Experience Level 1 letter (OE-1: 2013-01). The INL contractor, Battelle Energy Alliance, LLC (BEA), in coordination with CH2M-WG Idaho, LLC (CWI), and Idaho Treatment Group LLC (ITG), successfully demonstrated appropriate response measures to mitigate a BDBE event that would impact multiple facilities across the INL while protecting the health and safety of personnel, the environment, and property. Offsite response organizations participated to demonstrate appropriate response measures.

  13. Calculation of stricken to mortality and incidence cancers due to beyond design basis accidents of the Esfahan Fuel Production Factory

    International Nuclear Information System (INIS)

    Heydari Azar, A.; Shahshahani, M.; Roshanzamir, M.; Sabouhi, R.

    2008-01-01

    In this investigation the amount of absorbed doses by the different pathways of Cloud shine, Ground shine, deposition of radioactive materials on skin and cloths, ingestion, inhalation and the consequences of radioactive material releases due to Beyond Design Basis Accidents such as fire, sintering furnace explosion, criticality and earthquake in Esfahan Fuel Production factory by the residents are evaluated. The calculations related to atomic cloud distribution, estimation of delivered dose and decay chains are performed by PCCOSYMA dose. These computations are based on radioactive source terms, distribution height of radioactive materials. actions for reducing the absorbed dose, human body physiological characteristics, metrological condition and population distribution. Finally, the number of peoples who are stricken to mortality and morbidity cancers and risk values are calculated for 1 year and 50 years

  14. Design of serum-free medium for suspension culture of CHO cells on the basis of general commercial media.

    Science.gov (United States)

    Miki, Hideo; Takagi, Mutsumi

    2015-08-01

    The design of serum-free media for suspension culture of genetically engineered Chinese hamster ovary (CHO) cells using general commercial media as a basis was investigated. Subcultivation using a commercial serum-free medium containing insulin-like growth factor (IGF)-1 with or without FCS necessitated additives other than IGF-1 to compensate for the lack of FCS and improve cell growth. Suspension culture with media containing several combinations of growth factors suggested the effectiveness of addition of both IGF-1 and the lipid signaling molecule lysophosphatidic acid (LPA) for promoting cell growth. Subcultivation of CHO cells in suspension culture using the commercial serum-free medium EX-CELL™302, which contained an IGF-1 analog, supplemented with LPA resulted in gradually increasing specific growth rate comparable to the serum-containing medium and in almost the same high antibody production regardless of the number of generations. The culture with EX-CELL™302 supplemented with LPA in a jar fermentor with pH control at 6.9 showed an apparently higher cell growth rate than the cultures without pH control and with pH control at 6.8. The cell growth in the medium supplemented with aurintricarboxylic acid (ATA), which was much cheaper than IGF-1, in combination with LPA was synergistically promoted similarly to that in the medium supplemented with IGF-1 and LPA. In conclusion, the serum-free medium designed on the basis of general commercial media could support the growth of CHO cells and antibody production comparable to serum-containing medium in suspension culture. Moreover, the possibility of cost reduction by the substitution of IGF-1 with ATA was also shown.

  15. Performance of Broiler Chickens Fed Low Protein, Limiting Amino Acid Supplemented Diets Formulated Either on Total or Standardized Ileal Digestible Amino Acid Basis

    Directory of Open Access Journals (Sweden)

    C. Basavanta Kumar

    2016-11-01

    Full Text Available The aim of present experiment was to investigate the effect of protein reduction in commercial broiler chicken rations with incorporation of de-oiled rice bran (DORB and supplementation of limiting amino acids (valine, isoleucine, and/or tryptophan with ration formulation either on total amino acid (TAA or standardized ileal digestible amino acids (SIDAA. The experimental design consisted of T1, TAA control; T2 and T3, 0.75% and 1.5% protein reduction by 3% and 6% DORB incorporation, respectively by replacing soybean meal with supplemental limiting amino acids to meet TAA requirement; T4, SIDAA control, T5 and T6, 0.75% and 1.5% protein reduction by DORB incorporation (3% and 6% with supplemental limiting amino acids on SIDAA basis. A total of 360 d-old fast growing broiler chicks (Vencobb-400 were divided into 36 homogenous groups of ten chicks each, and six dietary treatments described were allocated randomly with six replications. During 42 days trial, the feed intake was significantly (p<0.05 reduced by TAA factor compared to SIDAA factor and protein factor significantly (p<0.05 reduced the feed intake at 1.5% reduction compared to normal protein group. This was observed only during pre-starter phase but not thereafter. The cumulative body weight gain (BWG was significantly (p<0.05 reduced in TAA formulations with protein step-down of 1.5% (T3, 1,993 g compared to control (T1, 2,067 g, while under SIDAA formulations, BWG was not affected with protein reduction of 1.5% (T6, 2,076 g compared to T4 (2,129 g. The feed conversion ratio (FCR was significantly (p<0.05 reduced in both TAA and SIDAA formulations with 1.5% protein step-down (T3, 1.741; T6, 1.704 compared to respective controls (T1, 1.696; T4, 1.663. The SIDAA formulation revealed significantly (p<0.05 higher BWG (2,095 g and better FCR (1.684 compared to TAA formulation (2,028 g; 1.721. Intake of crude protein and all limiting amino acids (SID basis was higher in SIDAA group than TAA

  16. An automated tool for evaluating compliance and providing assistance with building energy standards during design

    Energy Technology Data Exchange (ETDEWEB)

    Quadrel, R.W.; Brambley, M.R.; Stratton, R.C.

    1992-04-30

    In an effort to encourage the maximum cost-effective level of energy efficiency in new building design, energy-efficiency standards have become more location-specific and performance-based. As a result, standards often provide more than one path for ensuring and demonstrating that a design complies, but at the cost of increased complexity. In addition, the burden of remedying a noncompliant design rests on the designers` knowledge and experience, with only general guidance provided by the standards. As part of efforts in the US Department of Energy`s (DOE`s) Advanced Energy Design and Operation Technologies (AEDOT) project, a team at DOE`s Pacific Northwest Laboratory is developing a computer program known as the Energy Standards Intelligent Design Tool (ES-IDT). The ES-IDT is one component of a prototype computer-based building design environment. It performs automatic compliance checking for parts of ASHRAE/IES Standard 90.1-1989 and provides designers assistance in bringing noncomplying designs into compliance. This paper describes the ES-IDT, the functions it provides, and how it is integrated into the design process via the AEDOT prototype building design environment. 9 refs.

  17. An automated tool for evaluating compliance and providing assistance with building energy standards during design

    Energy Technology Data Exchange (ETDEWEB)

    Quadrel, R.W.; Brambley, M.R.; Stratton, R.C.

    1992-04-30

    In an effort to encourage the maximum cost-effective level of energy efficiency in new building design, energy-efficiency standards have become more location-specific and performance-based. As a result, standards often provide more than one path for ensuring and demonstrating that a design complies, but at the cost of increased complexity. In addition, the burden of remedying a noncompliant design rests on the designers' knowledge and experience, with only general guidance provided by the standards. As part of efforts in the US Department of Energy's (DOE's) Advanced Energy Design and Operation Technologies (AEDOT) project, a team at DOE's Pacific Northwest Laboratory is developing a computer program known as the Energy Standards Intelligent Design Tool (ES-IDT). The ES-IDT is one component of a prototype computer-based building design environment. It performs automatic compliance checking for parts of ASHRAE/IES Standard 90.1-1989 and provides designers assistance in bringing noncomplying designs into compliance. This paper describes the ES-IDT, the functions it provides, and how it is integrated into the design process via the AEDOT prototype building design environment. 9 refs.

  18. TECHNICAL BASIS FOR DOE STANDARD 3013 EQUIVALENCY SUPPORTING REDUCED TEMPERATURE STABILIZATION OF OXALATE-DERIVED PLUTONIUM OXIDE PRODUCED BY THE HB-LINE FACILITY AT SAVANNAH RIVER SITE

    Energy Technology Data Exchange (ETDEWEB)

    Duffey, J.; Livingston, R.; Berg, J.; Veirs, D.

    2012-07-02

    The HB-Line (HBL) facility at the Savannah River Site (SRS) is designed to produce high-purity plutonium dioxide (PuO{sub 2}) which is suitable for future use in production of Mixed Oxide (MOX) fuel. The MOX Fuel Fabrication Facility (MFFF) requires PuO{sub 2} feed to be packaged per the U.S. Department of Energy (DOE) Standard 3013 (DOE-STD-3013) to comply with the facility's safety basis. The stabilization conditions imposed by DOE-STD-3013 for PuO{sub 2} (i.e., 950 C for 2 hours) preclude use of the HBL PuO{sub 2} in direct fuel fabrication and reduce the value of the HBL product as MFFF feedstock. Consequently, HBL initiated a technical evaluation to define acceptable operating conditions for production of high-purity PuO{sub 2} that fulfills the DOE-STD-3013 criteria for safe storage. The purpose of this document is to demonstrate that within the defined operating conditions, the HBL process will be equivalent for meeting the requirements of the DOE-STD-3013 stabilization process for plutonium-bearing materials from the DOE complex. The proposed 3013 equivalency reduces the prescribed stabilization temperature for high-purity PuO{sub 2} from oxalate precipitation processes from 950 C to 640 C and places a limit of 60% on the relative humidity (RH) at the lowest material temperature. The equivalency is limited to material produced using the HBL established flow sheet, for example, nitric acid anion exchange and Pu(IV) direct strike oxalate precipitation with stabilization at a minimum temperature of 640 C for four hours (h). The product purity must meet the MFFF acceptance criteria of 23,600 {micro}g/g Pu (i.e., 2.1 wt %) total impurities and chloride content less than 250 {micro}g/g of Pu. All other stabilization and packaging criteria identified by DOE-STD-3013-2012 or earlier revisions of the standard apply. Based on the evaluation of test data discussed in this document, the expert judgment of the authors supports packaging the HBL product under a 3013

  19. 76 FR 14437 - Economic Simplified Boiling Water Reactor Standard Design: GE Hitachi Nuclear Energy; Issuance of...

    Science.gov (United States)

    2011-03-16

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0055] Economic Simplified Boiling Water Reactor Standard Design: GE Hitachi Nuclear Energy; Issuance of Final Design Approval The U.S. Nuclear Regulatory Commission has issued a final design approval (FDA) to GE Hitachi Nuclear Energy (GEH) for the economic...

  20. Combining economic and social goals in the design of production systems by using ergonomics standards

    NARCIS (Netherlands)

    J. Dul (Jan); H.J. de Vries (Henk); S. Verschoof (Sandra); W. Eveleens (Wietske); A. Feilzer (Albert)

    2004-01-01

    textabstractIn designing of production systems, economic and social goals can be combined, if ergonomics is integrated into the design process. More than 50 years of ergonomics research and practice have resulted in a large number of ergonomics standards for designing physical and organizational

  1. 75 FR 71033 - Air Quality Designations for the 2008 Lead (Pb) National Ambient Air Quality Standards

    Science.gov (United States)

    2010-11-22

    ... Nebraska. Street, Kansas City, KS 66101-2907, (913) 551-7606. Monica Morales, Leader, Air Quality Colorado..., C, and E are used in design value calculations.\\5\\ In some cases, states requested unclassifiable designations for areas around monitors with a design value exceeding the standard. EPA does not believe such a...

  2. Assessment of precast beam-column using capacity demand response spectrum subject to design basis earthquake and maximum considered earthquake

    Science.gov (United States)

    Ghani, Kay Dora Abd.; Tukiar, Mohd Azuan; Hamid, Nor Hayati Abdul

    2017-08-01

    Malaysia is surrounded by the tectonic feature of the Sumatera area which consists of two seismically active inter-plate boundaries, namely the Indo-Australian and the Eurasian Plates on the west and the Philippine Plates on the east. Hence, Malaysia experiences tremors from far distant earthquake occurring in Banda Aceh, Nias Island, Padang and other parts of Sumatera Indonesia. In order to predict the safety of precast buildings in Malaysia under near field ground motion the response spectrum analysis could be used for dealing with future earthquake whose specific nature is unknown. This paper aimed to develop of capacity demand response spectrum subject to Design Basis Earthquake (DBE) and Maximum Considered Earthquake (MCE) in order to assess the performance of precast beam column joint. From the capacity-demand response spectrum analysis, it can be concluded that the precast beam-column joints would not survive when subjected to earthquake excitation with surface-wave magnitude, Mw, of more than 5.5 Scale Richter (Type 1 spectra). This means that the beam-column joint which was designed using the current code of practice (BS8110) would be severely damaged when subjected to high earthquake excitation. The capacity-demand response spectrum analysis also shows that the precast beam-column joints in the prototype studied would be severely damaged when subjected to Maximum Considered Earthquake (MCE) with PGA=0.22g having a surface-wave magnitude of more than 5.5 Scale Richter, or Type 1 spectra.

  3. Design of cognitive engine for cognitive radio based on the rough sets and radial basis function neural network

    Science.gov (United States)

    Yang, Yanchao; Jiang, Hong; Liu, Congbin; Lan, Zhongli

    2013-03-01

    Cognitive radio (CR) is an intelligent wireless communication system which can dynamically adjust the parameters to improve system performance depending on the environmental change and quality of service. The core technology for CR is the design of cognitive engine, which introduces reasoning and learning methods in the field of artificial intelligence, to achieve the perception, adaptation and learning capability. Considering the dynamical wireless environment and demands, this paper proposes a design of cognitive engine based on the rough sets (RS) and radial basis function neural network (RBF_NN). The method uses experienced knowledge and environment information processed by RS module to train the RBF_NN, and then the learning model is used to reconfigure communication parameters to allocate resources rationally and improve system performance. After training learning model, the performance is evaluated according to two benchmark functions. The simulation results demonstrate the effectiveness of the model and the proposed cognitive engine can effectively achieve the goal of learning and reconfiguration in cognitive radio.

  4. Task to Training Matrix Design for Decommissioning Engineer on the basis of Systematic Approach to Training Methodology

    Energy Technology Data Exchange (ETDEWEB)

    Kwak, Jeong Keun [KHNP, Ulsan (Korea, Republic of)

    2016-10-15

    In nuclear history, before Chernobyl Accident, Three Mile Island (TMI) Accident was the severest accident. For this reason, to resolve the disclosed or potential possibilities of nuclear accident, more than one hundred countermeasures were proposed by United States Nuclear Regulatory Commission (USNRC). Among various recommendations by USNRC, one suggestion was related to training aspect. It was Systematic Approach to Training (SAT) and this event was the initiation of SAT methodology in the world. In Korea, upcoming June 2017, Kori Unit-1 NPP is scheduled to be shut down and it will experience NPP decommissioning for the first time. Present study aims to establish concrete training foundation for NPP decommissioning engineers based on Systematic Approach to Training (SAT) methodology, in particular, Task to Training Matrix (TTM). The objective of this paper is to organize TTM on the basis of SAT for NPP decommissioning engineer. For this reason, eighteen tasks are yielded through Job and Task Analysis (JTA) process. After that, for the settlement of Task to Training Matrix (TTM), various data are determined such as element, condition, standard, knowledge and skill, learning objective and training setting. When it comes to training in nuclear industry, SAT methodology has been the unwavering principle in Korea since NPPs export to UAE.

  5. Ergonomics standards and guidelines for computer workstation design and the impact on users' health - a review.

    Science.gov (United States)

    Woo, E H C; White, P; Lai, C W K

    2016-03-01

    This paper presents an overview of global ergonomics standards and guidelines for design of computer workstations, with particular focus on their inconsistency and associated health risk impact. Overall, considerable disagreements were found in the design specifications of computer workstations globally, particularly in relation to the results from previous ergonomics research and the outcomes from current ergonomics standards and guidelines. To cope with the rapid advancement in computer technology, this article provides justifications and suggestions for modifications in the current ergonomics standards and guidelines for the design of computer workstations. Practitioner Summary: A research gap exists in ergonomics standards and guidelines for computer workstations. We explore the validity and generalisability of ergonomics recommendations by comparing previous ergonomics research through to recommendations and outcomes from current ergonomics standards and guidelines.

  6. Reactor similarity for plasma–material interactions in scaled-down tokamaks as the basis for the Vulcan conceptual design

    International Nuclear Information System (INIS)

    Whyte, D.G.; Olynyk, G.M.; Barnard, H.S.; Bonoli, P.T.; Bromberg, L.; Garrett, M.L.; Haakonsen, C.B.; Hartwig, Z.S.; Mumgaard, R.T.; Podpaly, Y.A.

    2012-01-01

    Highlights: ► Discussion of similarity scalings for reduced-size tokamaks. ► Proposal of a new set of scaling laws for divertor similarity. ► Discussion of how the new scaling provides fidelity to a reactor. ► The new scaling is used as the basis for the Vulcan conceptual design. - Abstract: Dimensionless parameter scaling techniques are a powerful tool in the study of complex physical systems, especially in tokamak fusion experiments where the cost of full-size devices is high. It is proposed that dimensionless similarity be used to study in a small-scale device the coupled issues of the scrape-off layer (SOL) plasma, plasma–material interactions (PMI), and the plasma-facing material (PFM) response expected in a tokamak fusion reactor. Complete similarity is not possible in a reduced-size device. In addition, “hard” technological limits on the achievable magnetic field and peak heat flux, as well as the necessity to produce non-inductive scenarios, must be taken into account. A practical approach is advocated, in which the most important dimensionless parameters are matched to a reactor in the reduced-size device, while relaxing those parameters which are far from a threshold in behavior. “Hard” technological limits are avoided, so that the reduced-size device is technologically feasible. A criticism on these grounds is offered of the “P/R” model, in which the ratio of power crossing the last closed flux surface (LCFS), P, to the device major radius, R, is held constant. A new set of scaling rules, referred to as the “P/S” scaling (where S is the LCFS area) or the “PMI” scaling, is proposed: (i) non-inductive, steady-state operation; (ii) P is scaled with R 2 so that LCFS areal power flux P/S is constant; (iii) magnetic field B constant; (iv) geometry (elongation, safety factor q * , etc.) constant; (v) volume-averaged core density scaled as n≈n ¯ e ∼R −2/7 ; and (vi) ambient wall material temperature T W,0 constant. It is

  7. Methods for formulation of design basis accidents within a risk-informed approach to safety regulation of new nuclear power plants

    International Nuclear Information System (INIS)

    Beer, B.C.; Apostolakis, G.E.; Golay, M.W.

    2000-01-01

    Within a project sponsored by the U.S. Department of Energy (DOE) an investigation is being conducted into creating a risk-informed safety regulatory framework and design process based upon the use of probabilistic risk assessment (PRA). In conjunction with efforts to formulate an overall regulatory framework (i.e., reported in PSAM 5 by F. Duran, A. Camp, G. Apostolakis and M. Golay, 'A Framework for Regulatory Requirements and Industry Standards for New Nuclear Power Plants'), this paper addresses the potential role(s) of Design Basis Accidents (DBAs) within this new framework. Currently that role, if any, is unclear. In previous nuclear safety regulatory treatments, DBAs have been of great practical value for both designers and regulators. However, they have suffered from being inconsistently formulated, and lacking fundamental justification. Any DBA set is likely to be formulated uniquely for a specific reactor concept. The staff of any nuclear power plant (NPP) in the U.S. routinely calculates the likelihood of core damage, the likelihood of radioactive release and the likelihood of adverse health effects due to radioactive release. As the accuracy of such estimates improves industry-wide, safety regulators consider weighing these calculated risks more heavily than strict adherence to the prescriptive conservatisms of existing regulations, hence risk-informed regulation. DBAs, despite their prescriptive nature, can remain useful tools for regulators and designers in a risk-informed regulatory framework, providing that they can be formulated in a fashion consistent with the risk profiles of a plant. DBAs also offer the opportunity to take into account factors of uncertainty not captured in a PRA, which are typically addressed via defense-in-depth features and subjective judgements. Designers seeking only to create a plant having a calculated risk below a certain value, while minimizing cost, may find themselves in an inefficient trial-and-error process as they

  8. Including severe accidents in the design basis of nuclear power plants: An organizational factors perspective after the Fukushima accident

    International Nuclear Information System (INIS)

    Alvarenga, M.A.B.; Frutuoso e Melo, P.F.

    2015-01-01

    Highlights: • The Fukushima accident was man-made and not caused by natural phenomena. • Vulnerabilities were known by regulator and licensee but measures were not taken. • There was lack of independence and transparency of the regulatory body. • Laws and regulations have not been updated to international standards. • Organizational failures have played an important role in the Fukushima accident. - Abstract: The Fukushima accident was clearly an accident made by humans and not caused by natural phenomena as was initially thought. Vulnerabilities were known by both regulators and operator but they postponed measures. The emergency plan was not effective in protecting the public, because the involved parties were not sufficiently prepared to make the right decisions. The shortcomings and faults mentioned above resulted from the lack of independence and transparency of the regulatory body. Even laws and regulations, and technical standards, have not been upgraded to international standards. Regulators have not defined requirements and left for the operator to decide what would be more appropriate. In this aspect, there was clearly a lack of independence between these bodies and operator’s lobby power. The above situation raised the question of urgent updating of institutions, in particular those responsible for nuclear safety. The above evidences show that several nuclear safety principles were not followed. This paper intends to highlight some existing safety criteria that were developed from the operational experience of the severe accidents that occurred at TMI and Chernobyl that should be incorporated in the design of new nuclear power plants and to provide appropriate design changes (backfittings) for reactors that belong to the previous generation prior to the occurrence of these accidents, through the study of design vulnerabilities. Furthermore, the main criteria that define an effective regulatory agency are also discussed. Although these

  9. Seismic design of nuclear power plants in Japan with consideration of standardization

    International Nuclear Information System (INIS)

    Watabe, M.; Tanaka, H.; Kato, M.; Tohdo, M.

    1981-01-01

    This paper presents the aseismic design approach and process for prototypes of the standard Light Water Reactor, which have been conducted in the committee of the Ministry of International Trade and Industry. (orig./HP)

  10. 77 FR 3070 - Electric Engineering, Architectural Services, Design Policies and Construction Standards

    Science.gov (United States)

    2012-01-23

    ... Engineering, Architectural Services, Design Policies and Construction Standards AGENCY: Rural Utilities..., engineering services and architectural services for transactions above the established threshold dollar levels... Code of Federal Regulations as follows: PART 1724--ELECTRIC ENGINEERING, ARCHITECTURAL SERVICES AND...

  11. Modified Standard Penetration Test–based Drilled Shaft Design Method for Weak Rocks (Phase 2 Study)

    Science.gov (United States)

    2017-12-15

    In this project, Illinois-specific design procedures were developed for drilled shafts founded in weak shale or rock. In particular, a modified standard penetration test was developed and verified to characterize the in situ condition of weak shales ...

  12. Effect of the standard design of forest roads clearing limit on stand ...

    African Journals Online (AJOL)

    Aidin

    In this research the standard design of clearing limit was determined based on soil texture and hillside gradient. ... clearing limit as well as the difference between standard and existing trees stock growth in different slope classes and soil ..... clearings on movement patterns of understory rainforest birds in central Amazonia.

  13. Development of GRIF-SM: The code for analysis of beyond design basis accidents in sodium cooled reactors

    International Nuclear Information System (INIS)

    Chvetsov, I.; Kouznetsov, I.; Volkov, A.

    2000-01-01

    GRIF-SM code was developed at the IPPE fast reactor department in 1992 for the analysis of transients in sodium cooled fast reactors under severe accident conditions. This code provides solution of transient hydrodynamics and heat transfer equations taking into account possibility of coolant boiling, fuel and steel melting, reactor kinetics and reactivity feedback due to variations of the core components temperature, density and dimensions. As a result of calculation, transient distribution of the coolant velocity and density was determined as well as temperatures of the fuel pins, reactor core and primary circuit as a whole. Development of the code during further 6 years period was aimed at the modification of the models describing thermal hydraulic characteristics of the reactor, and in particular in detailed description of the sodium boiling process. The GRIF-SM code was carefully validated against FZK experimental data on steady state sodium boiling in the electrically heated tube; transient sodium boiling in the 7-pin bundle; transient sodium boiling in the 37-pin bundle under flow redaction simulating ULOF accident. To show the code capabilities some results of code application for beyond design basis accident analysis on BN-800-type reactor are presented. (author)

  14. Effects of irradiation and design basis accident conditions on thermal properties of epoxy coating system for nuclear power plant

    International Nuclear Information System (INIS)

    Park, Soo-Jin; Seo, Min-Kang; Lee, Jae-Rock

    2004-01-01

    In this work, the thermal properties of epoxy coating system on carbon steel liner in an atomic reactor container have been investigated in terms of irradiation and design basis accident (DBA) conditions. Two epoxy coating systems were irradiated by different dose rates, i.e. 1x10 6 and 5x10 5 rad/h in a total dosage of 2x10 8 rad/h. And, DBA tests were applied to them based on the specification. The glass transition temperature (T g ) and thermal stability of the epoxy coating systems after tests were measured by differential scanning calorimetry (DSC) and thermogravimetric analysis (TGA), respectively. As a result, the irradiation led to the fracture of internal structure in cured epoxy systems, resulting in significantly decreasing the thermal stability, as well as, the T g . Also, the higher dose rate made a relaxation of epoxy resins to reduce the hardening of the network system. Whereas, the DBA test made an important role in the thermal stability in the epoxy coating systems, resulting in post-curing of the uncured epoxy resins. Consequently, it could be found that the thermal properties of the epoxy coating system were greatly influenced on the irradiation and DBA tests, which were probably due to the modification of internal network structure of the epoxy resins

  15. California residential energy standards: problems and recommendations relating to implementation, enforcement, and design. [Thermal insulation

    Energy Technology Data Exchange (ETDEWEB)

    1977-08-01

    Documents relevant to the development and implementation of the California energy insulation standards for new residential buildings were evaluated and a survey was conducted to determine problems encountered in the implementation, enforcement, and design aspects of the standards. The impact of the standards on enforcement agencies, designers, builders and developers, manufacturers and suppliers, consumers, and the building process in general is summarized. The impact on construction costs and energy savings varies considerably because of the wide variation in prior insulation practices and climatic conditions in California. The report concludes with a series of recommendations covering all levels of government and the building process. (MCW)

  16. High-Affinity α-Conotoxin PnIA Analogs Designed on the Basis of the Protein Surface Topography Method.

    Science.gov (United States)

    Kasheverov, Igor E; Chugunov, Anton O; Kudryavtsev, Denis S; Ivanov, Igor A; Zhmak, Maxim N; Shelukhina, Irina V; Spirova, Ekaterina N; Tabakmakher, Valentin M; Zelepuga, Elena A; Efremov, Roman G; Tsetlin, Victor I

    2016-11-14

    Despite some success for small molecules, elucidating structure-function relationships for biologically active peptides - the ligands for various targets in the organism - remains a great challenge and calls for the development of novel approaches. Some of us recently proposed the Protein Surface Topography (PST) approach, which benefits from a simplified representation of biomolecules' surface as projection maps, which enables the exposure of the structure-function dependencies. Here, we use PST to uncover the "activity pattern" in α-conotoxins - neuroactive peptides that effectively target nicotinic acetylcholine receptors (nAChRs). PST was applied in order to design several variants of the α-conotoxin PnIA, which were synthesized and thoroughly studied. Among the best was PnIA[R9, L10], which exhibits nanomolar affinity for the α7 nAChR, selectivity and a slow wash-out from this target. Importantly, these mutations could hardly be delineated by "standard" structure-based drug design. The proposed combination of PST with a set of experiments proved very efficient for the rational construction of new bioactive molecules.

  17. Pseudo Open Drain IO Standards Based Energy Efficient Solar Charge Sensor Design on 20nm FPGA

    DEFF Research Database (Denmark)

    Kalia, K; Pandey, B; Nanda, K

    2015-01-01

    In this paper an approach is made to design Pseudo open drain IO standards Based Energy efficient solar charge sensor design on 20nm and 28nm technology. We have used LVCMOS18, POD10, POD10_DCI and POD12 I/O standard. In this design, we have taken two main parameters for analysis...... solar charge inverter. We also observed maximum total power reduction in LVCMOS18 (Artix-7 FPGA) as compared to other I/O standards at 10 GHz. Also there is maximum total power reduction in POD12 (Ultra Scale Kintex) as compared to other I/O standards at 2 GHz. There is also a significant change...... in device static, I/O power and Clock Power....

  18. A brief comparison of existing regional green building design standards in China

    Science.gov (United States)

    Wang, J.; Liu, Y.; Ren, J.; Cho, S.

    2017-03-01

    A large country with a variety of regional natural, cultural and economic conditions, China has established a number of green building design (GBD) standards both at national and regional (provincial and municipal) levels. Some researches have been conducted to review and compare such standards. The main aim was to provide valuable references for the establishment of new regionally specific GBD standards in different regions of the country. This paper introduces the preliminary results of the researches. The distribution, frameworks and content of the existing regional GBD standards are introduced and compared in relating to the regionally specific climate, resource, economic and cultural conditions. Conclusions are provided and further researches are recommended.

  19. Recent developments in the IAEA safety standards: design and operation of nuclear power plants

    International Nuclear Information System (INIS)

    Saito, Takehiko

    2004-01-01

    The IAEA has been publishing a wide variety of safety standards for nuclear and radiation related facilities and activities since 1978. In 1996, a more rigorously structured approach for the preparation and review of its safety standards was introduced. Currently, based on the approach, revision of most of the standards is in completion or near completion. The latest versions of the Safety Requirements for ''Design'' and ''Operation'' of nuclear power plants were respectively published in 2000. Currently, along with this revision of the Safety Requirements, many Safety Guides have been revised. In order to clarify the complicated revision procedure, an example of the entire revision process for a Safety Guide is provided. Through actual example of the revision process, enormous amount of work involved in the revision work is clearly indicated. The current status of all of the Safety Standards for Design and that for Operation of nuclear power plants are summarized. Summary of other IAEA safety standards currently revised and available related IAEA publications, together with information on the IAEA Web Site from where these documents can be downloaded, is also provided. The standards are reviewed to determine whether revision (or new issue) is necessary in five years following publication. The IAEA safety standards will continue to be updated through comprehensive and structured approach, collaboration of many experts of the world, and reflecting good practices of the world. The IAEA safety standards will serve to provide high level of safety assurance. (author)

  20. Design validation of the ITER EC upper launcher according to codes and standards

    Energy Technology Data Exchange (ETDEWEB)

    Spaeh, Peter, E-mail: peter.spaeh@kit.edu [Karlsruhe Institute of Technology, Institute for Applied Materials, Association KIT-EURATOM, P.O. Box 3640, D-76021 Karlsruhe (Germany); Aiello, Gaetano [Karlsruhe Institute of Technology, Institute for Applied Materials, Association KIT-EURATOM, P.O. Box 3640, D-76021 Karlsruhe (Germany); Gagliardi, Mario [Karlsruhe Institute of Technology, Association KIT-EURATOM, P.O. Box 3640, D-76021 Karlsruhe (Germany); F4E, Fusion for Energy, Joint Undertaking, Barcelona (Spain); Grossetti, Giovanni; Meier, Andreas; Scherer, Theo; Schreck, Sabine; Strauss, Dirk; Vaccaro, Alessandro [Karlsruhe Institute of Technology, Institute for Applied Materials, Association KIT-EURATOM, P.O. Box 3640, D-76021 Karlsruhe (Germany); Weinhorst, Bastian [Karlsruhe Institute of Technology, Institute for Neutron Physics and Reactor Technology, Association KIT-EURATOM, P.O. Box 3640, D-76021 Karlsruhe (Germany)

    2015-10-15

    Highlights: • A set of applicable codes and standards has been chosen for the ITER EC upper launcher. • For a particular component load combinations, failure modes and stress categorizations have been determined. • The design validation was performed in accordance with the “design by analysis”-approach of the ASME boiler and pressure vessel code section III. - Abstract: The ITER electron cyclotron (EC) upper launcher has passed the CDR (conceptual design review) in 2005 and the PDR (preliminary design review) in 2009 and is in its final design phase now. The final design will be elaborated by the European consortium ECHUL-CA with contributions from several research institutes in Germany, Italy, the Netherlands and Switzerland. Within this consortium KIT is responsible for the design of the structural components (the upper port plug, UPP) and also the design integration of the launcher. As the selection of applicable codes and standards was under discussion for the past decade, the conceptual and the preliminary design of the launcher structure were not elaborated in straight accordance with a particular code but with a variety of well-acknowledged engineering practices. For the final design it is compulsory to validate the design with respect to a typical engineering code in order to be compliant with the ITER quality and nuclear requirements and to get acceptance from the French regulator. This paper presents typical design validation of the closure plate, which is the vacuum and Tritium barrier and thus a safety relevant component of the upper port plug (UPP), performed with the ASME boiler and pressure vessel code. Rationales for choosing this code are given as well as a comparison between different design methods, like the “design by rule” and the “design by analysis” approach. Also the selections of proper load specifications and the identification of potential failure modes are covered. In addition to that stress categorizations, analyses

  1. A Standardized Rubric for Evaluating Webquest Design: Reliability Analysis of ZUNAL Webquest Design Rubric

    Science.gov (United States)

    Unal, Zafer; Bodur, Yasar; Unal, Aslihan

    2012-01-01

    Current literature provides many examples of rubrics that are used to evaluate the quality of web-quest designs. However, reliability of these rubrics has not yet been researched. This is the first study to fully characterize and assess the reliability of a webquest evaluation rubric. The ZUNAL rubric was created to utilize the strengths of the…

  2. NASA-STD-3001, Space Flight Human-System Standard and the Human Integration Design Handbook

    Science.gov (United States)

    Whitmore, Mihriban; Boyer, Jennifer; Holubec, Keith

    2012-01-01

    NASA-STD-3001 Space Flight Human-System Standard Volume 1, Crew Health, Volume 2, Human Factors, Habitability and Environmental Health, and the Human Integration Design Handbook (HIDH) have replaced the Man-Systems Integration Standards (MSIS), NASA-STD-3000. For decades, NASA-STD-3000 was a significant contribution to human spaceflight programs and to human-systems integration. However, with research program and project results being realized, advances in technology, and the availability of new information in a variety of topic areas, the time had arrived to update this extensive suite of standards and design information. NASA-STD-3001, Volume 2 contains the Agency level standards from the human and environmental factors disciplines that ensure human spaceflight operations are performed safely, efficiently, and effectively. The HIDH is organized in the same sequence and serves as the companion document to NASA-STD-3001, Volume 2, providing a compendium of human spaceflight history and knowledge. The HIDH is intended to aid interpretation of NASA-STD-3001, Volume 2 standards and to provide guidance for requirement writers and vehicle and habitat designers. Keywords Human Factors, Standards, Environmental Factors, NASA

  3. Contribution of thermal–hydraulic validation tests to the standard design approval of SMART

    Directory of Open Access Journals (Sweden)

    Hyun-Sik Park

    2017-10-01

    Full Text Available Many thermal–hydraulic tests have been conducted at the Korea Atomic Energy Research Institute for verification of the SMART (System-integrated Modular Advanced ReacTor design, the standard design approval of which was issued by the Korean regulatory body. In this paper, the contributions of these tests to the standard design approval of SMART are discussed. First, an integral effect test facility named VISTA-ITL (Experimental Verification by Integral Simulation of Transients and Accidents-Integral Test Loop has been utilized to assess the TASS/SMR-S (Transient and Set-point Simulation/Small and Medium safety analysis code and confirm its conservatism, to support standard design approval, and to construct a database for the SMART design optimization. In addition, many separate effect tests have been performed. The reactor internal flow test has been conducted using the SCOP (SMART COre flow distribution and Pressure drop test facility to evaluate the reactor internal flow and pressure distributions. An ECC (Emergency Core Coolant performance test has been carried out using the SWAT (SMART ECC Water Asymmetric Two-phase choking test facility to evaluate the safety injection performance and to validate the thermal–hydraulic model used in the safety analysis code. The Freon CHF (Critical Heat Flux test has been performed using the FTHEL (Freon Thermal Hydraulic Experimental Loop facility to construct a database from the 5 × 5 rod bundle Freon CHF tests and to evaluate the DNBR (Departure from Nucleate Boiling Ratio model in the safety analysis and core design codes. These test results were used for standard design approval of SMART to verify its design bases, design tools, and analysis methodology.

  4. Standardization Efforts for Mechanical Testing and Design of Advanced Ceramic Materials and Components

    Science.gov (United States)

    Salem, Jonathan A.; Jenkins, Michael G.

    2003-01-01

    Advanced aerospace systems occasionally require the use of very brittle materials such as sapphire and ultra-high temperature ceramics. Although great progress has been made in the development of methods and standards for machining, testing and design of component from these materials, additional development and dissemination of standard practices is needed. ASTM Committee C28 on Advanced Ceramics and ISO TC 206 have taken a lead role in the standardization of testing for ceramics, and recent efforts and needs in standards development by Committee C28 on Advanced Ceramics will be summarized. In some cases, the engineers, etc. involved are unaware of the latest developments, and traditional approaches applicable to other material systems are applied. Two examples of flight hardware failures that might have been prevented via education and standardization will be presented.

  5. Report on design rules of μ-tools for standard insert

    DEFF Research Database (Denmark)

    Tosello, Guido; Esmoris, Josa Ignacio; Quadroni, A.

    2011-01-01

    Tooling is one of the critical stages of the process chain for polymer micro products manufacture and in particular for the COTECH process chain. Therefore, within the scope of SP2 “Tooling”, the WP 2.2 “New tool-making solutions for μ-IM and HE” is designed to investigate, develop and standardize......-effectively, especially for micro injection moulding. This particular deliverable has the objective to present the design rules for high performance μ-tools and inserts manufacture based on the new standard manufacturing process chains established during the WP 2.2 work. In particular, the achievable features, surfaces...

  6. SSTL I/O Standard Based Green Communication Using Fibonacci Generator Design on Ultra Scale FPGA

    DEFF Research Database (Denmark)

    Nagah, Sumi; Kaur, Ravinder; Pandey, Bishwajeet

    2015-01-01

    In this paper six different available classes of Stub-Series Terminated Logic (SSTL) Input/output standard is used for the design of Green Fibonacci generator on 40nm FGPA. That green Fibonacci Generator is used to generate key for Wi-Fi Protected Access in order to make energy efficient communic......In this paper six different available classes of Stub-Series Terminated Logic (SSTL) Input/output standard is used for the design of Green Fibonacci generator on 40nm FGPA. That green Fibonacci Generator is used to generate key for Wi-Fi Protected Access in order to make energy efficient...

  7. Problem of probabilistic calculation of the design on linearly and non-linearly deformable basis with casual parameters

    Directory of Open Access Journals (Sweden)

    Mkrtychev Oleg Vartanovich

    Full Text Available In the article the problem of calculation of a construction basis system in case of earthquake is considered taking into account casual properties of basis soil in various points of the soil body. As a stochastic function in the calculation of linearly deformable basis, the deformation module, which accepts different values in the direction x, y, z, was chosen. In the calculation of the system on non-linearly deformable basis as incidentally distributed sizes the following parameters were accepted: deformation module, shear modulus, specific adhesion, angle of internal friction. The authors of the article offer to consider initial seismic influence in the form of casual stationary process. In order to solve such problems modern software systems are proposed that solve differential equations of motion via direct integration with explicit schemes. The calculation in this case will be held on the synthesized accelerograms. A short review of the task solution of the beam lying on elastic basis, which was received by D.N. Sobolev at casual distribution of pastel coefficient in the direction x, is provided in article. In order to define the objective, D.N. Sobolev gives expressions for a population mean and correlation function of stochastic function. As a result of the task solution population means and dispersions of function of movements and its derivatives were received. The problem formulation considered in the article is more complicated, but at the same time important from a practical standpoint.

  8. Math: Basic Skills Content Standards

    Science.gov (United States)

    CASAS - Comprehensive Adult Student Assessment Systems (NJ1), 2008

    2008-01-01

    This document presents content standards tables for math. [CASAS content standards tables are designed for educators at national, state and local levels to inform the alignment of content standards, instruction and assessment. The Content Standards along with the CASAS Competencies form the basis of the CASAS integrated assessment and curriculum…

  9. How the new optoelectronic design automation industry is taking advantage of preexisting EDA standards

    Science.gov (United States)

    Nesmith, Kevin A.; Carver, Susan

    2014-05-01

    With the advancements in design processes down to the sub 7nm levels, the Electronic Design Automation industry appears to be coming to an end of advancements, as the size of the silicon atom becomes the limiting factor. Or is it? The commercial viability of mass-producing silicon photonics is bringing about the Optoelectronic Design Automation (OEDA) industry. With the science of photonics in its infancy, adding these circuits to ever-increasing complex electronic designs, will allow for new generations of advancements. Learning from the past 50 years of the EDA industry's mistakes and missed opportunities, the photonics industry is starting with electronic standards and extending them to become photonically aware. Adapting the use of pre-existing standards into this relatively new industry will allow for easier integration into the present infrastructure and faster time to market.

  10. Applicability of ISO 9001: 2000 standard to design and research activities in nuclear objectives and installations

    International Nuclear Information System (INIS)

    Stamatopol, M.; Patticu, C.

    2001-01-01

    The ISO 9001: 2000 standard contains the results of the latest studies concerning the design and implementation of quality management systems. The continuous improvement of these systems required a new approach, namely, the process-based approach. A process-based model of quality management is presented in terms of client request, input data, management responsibility, resource management, product realisation, measurement / analysis and optimization, product, output data and client request fulfilment. Thus, the quality management system becomes an ensemble of interconnected or interacting processes. Consequently, to implement such a system the necessary processes have to be identified and their ISO 9001: 2000 standard based management ensured. Process based approach also allows better evidencing the input and output data specific to each process. Such an approach grants a wider applicability to the design and research activities in nuclear objectives and installations. This work aims at identifying additional requirements implied in design and research activities in nuclear field, as stipulated in the following standards / documents: - IAEA SG Q8 'Quality assurance in research and development'; - IAEA SG Q10 'Quality assurance in design'; - CAN / CSA N 286.2 - 00 'Design Quality Assurance for Nuclear Power Plants'; CAN 3 - CSA Z 299.1 'Quality Assurance Program - Category 1'; - NQA - 1, SUPPLEMENT 3S-1 'Supplementary requirements for design control'

  11. R and D issues in structural design standard for commercialized fast reactor components

    International Nuclear Information System (INIS)

    Shibamoto, Hiroshi; Tanaka, Yoshihiko; Inoue, Kazuhiko; Kasahara, Naoto; Morishita, Masaki

    2003-01-01

    Conceptual design studies of Japanese commercialized fast reactors (FRs) are carried out. With careful considerations on safety, economical improvement for practical use of these plants are aimed for, and the design of them is rationalized with adopting simple and innovative components, etc.. To certify the design concepts and validate structural integrity, research and development of Fast Reactor Structural Design Standard (FDS) for commercialized fast reactor components is now under way. Based on general characteristics of FRs and design needs of commercialized FRs, main subjects of R and D were identified. As for failure criteria, development for rational treatment of creep design region is dealt with. Ratcheting fatigue tests are conducted for the purpose of confirming the limit that ratcheting strain has negligible effects on structure strength. Besides, objecting to contribute to design rationalization through prediction of elasto-plastic and creep behaviors with high-precision, efforts to establish inelastic analysis methodologies for design are carried out. A guideline on inelastic analysis for design related to FDS, is prepared. This guideline is applied to evaluate the structural integrity of critical parts of components in conceptual design of commercialized FRs. Furthermore, aimed for mitigating thermal loads, a guideline on thermal loads modeling for design related to FDS is under developing. (author)

  12. IMS Learning Design: State of the art and research hot topics on eLearning standardization

    OpenAIRE

    Burgos, Daniel

    2006-01-01

    Burgos, D. (2006). IMS Learning Design: State of the art and research hot topics on eLearning standardization. Presentation at the 8th International Simposio of Educational Computer Science. October, 24-27, 2006, León, Spain: IEEE Technical Committee on Learning Technology.

  13. Study on Design and Implementation of JAVA Programming Procedural Assessment Standard

    Science.gov (United States)

    Tingting, Xu; Hua, Ma; Xiujuan, Wang; Jing, Wang

    2015-01-01

    The traditional JAVA course examination is just a list of questions from which we cannot know students' skills of programming. According to the eight abilities in curriculum objectives, we designed an assessment standard of JAVA programming course that is based on employment orientation and apply it to practical teaching to check the teaching…

  14. 76 FR 76048 - Air Quality Designations for the 2008 Lead (Pb) National Ambient Air Quality Standards

    Science.gov (United States)

    2011-12-06

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 81 [EPA-HQ-OAR-2009-0443; FRL-9492-3] RIN 2060-AR17 Air Quality Designations for the 2008 Lead (Pb) National Ambient Air Quality Standards Correction In rule document 2011-29460 appearing on pages 72097-72120 in the issues of Tuesday, November 22, 2011...

  15. Standard Error of Linear Observed-Score Equating for the NEAT Design with Nonnormally Distributed Data

    Science.gov (United States)

    Zu, Jiyun; Yuan, Ke-Hai

    2012-01-01

    In the nonequivalent groups with anchor test (NEAT) design, the standard error of linear observed-score equating is commonly estimated by an estimator derived assuming multivariate normality. However, real data are seldom normally distributed, causing this normal estimator to be inconsistent. A general estimator, which does not rely on the…

  16. 75 FR 29933 - Energy Efficiency and Sustainable Design Standards for New Federal Buildings

    Science.gov (United States)

    2010-05-28

    ... Price Indexes). If a new or replacement Federal building does not fit into one of these two categories... Efficiency and Sustainable Design Standards for New Federal Buildings AGENCY: Office of Energy Efficiency and... construction of new Federal buildings and major renovations of Federal buildings. This NOPR specifically...

  17. Quality Matters: New Roles for Librarians Using Standards for Online Course Design

    Science.gov (United States)

    Newby, Jill; Eagleson, Laurie; Pfander, Jeanne

    2014-01-01

    Quality Matters™ (QM) is a nationally recognized organization that certifies online courses for effective design, using an evidenced-based set of standards and a structured peer review process. In this paper, the authors demonstrate how academic librarians involved with online courses can adopt Quality Matters to build capacity for designing…

  18. 10 CFR 51.55 - Environmental report-standard design certification.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Environmental report-standard design certification. 51.55 Section 51.55 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC LICENSING AND RELATED REGULATORY FUNCTIONS National Environmental Policy Act-Regulations...

  19. 75 FR 34657 - Energy Efficiency and Sustainable Design Standards for New Federal Buildings

    Science.gov (United States)

    2010-06-18

    ... Efficiency and Sustainable Design Standards for New Federal Buildings AGENCY: Office of Energy Efficiency and... Federal buildings. This notice extends the comment period to August 12, 2010. DATES: DOE will hold a.... Department of Energy, Forrestal Building, Room 8E-089, 1000 Independence Avenue, SW., Washington, DC 20585...

  20. Design and Implementation of a Prototype with a Standardized Interface for Transducers in Ambient Assisted Living

    Directory of Open Access Journals (Sweden)

    Enrique Dorronzoro

    2015-01-01

    Full Text Available Solutions in the field of Ambient Assisted Living (AAL do not generally use standards to implement a communication interface between sensors and actuators. This makes these applications isolated solutions because it is so difficult to integrate them into new or existing systems. The objective of this research was to design and implement a prototype with a standardized interface for sensors and actuators to facilitate the integration of different solutions in the field of AAL. Our work is based on the roadmap defined by AALIANCE, using motes with TinyOS telosb, 6LoWPAN, sensors, and the IEEE 21451 standard protocol. This prototype allows one to upgrade sensors to a smart status for easy integration with new applications and already existing ones. The prototype has been evaluated for autonomy and performance. As a use case, the prototype has been tested in a serious game previously designed for people with mobility problems, and its advantages and disadvantages have been analysed.

  1. Testing keywords internationally to define and apply undergraduate assessment standards in art and design

    Directory of Open Access Journals (Sweden)

    Robert Harland

    2015-07-01

    Full Text Available What language should be featured in assessment standards for international students? Have universities adjusted their assessment methods sufficiently to match the increased demand for studying abroad? How might art and design benefit from a more stable definition of standards? These are some questions this paper seeks to address by reporting the results of recent pedagogic research at the School of the Arts, Loughborough University, in the United Kingdom. Language use is at the heart of this issue, yet it is generally overlooked as an essential tool that links assessment, feedback and action planning for international students. The paper reveals existing and new data that builds on research since 2009, aimed at improving students’ assessment literacy. Recommendations are offered to stimulate local and global discussion about keyword use for defining undergraduate assessment standards in art and design.

  2. Towards product design automation based on parameterized standard model with diversiform knowledge

    Science.gov (United States)

    Liu, Wei; Zhang, Xiaobing

    2017-04-01

    Product standardization based on CAD software is an effective way to improve design efficiency. In the past, research and development on standardization mainly focused on the level of component, and the standardization of the entire product as a whole is rarely taken into consideration. In this paper, the size and structure of 3D product models are both driven by the Excel datasheets, based on which a parameterized model library is therefore established. Diversiform knowledge including associated parameters and default properties are embedded into the templates in advance to simplify their reuse. Through the simple operation, we can obtain the correct product with the finished 3D models including single parts or complex assemblies. Two examples are illustrated later to invalid the idea, which will greatly improve the design efficiency.

  3. Standard concerning the design of nuclear power stations in earthquake-prone districts

    International Nuclear Information System (INIS)

    Kirillov, A.P.; Anbriashivili, Y.K.; Suvilova, A.V.

    1980-01-01

    The measures of security assurance against the effect of radioactive contamination has become more and more complex due to the construction of nuclear power stations of diverse types. The aseismatic measures for the nuclear power stations built in the districts where earthquakes of different intensity occur are important problems. All main machinery and equipments and emergency systems in power stations must be protected from earthquakes, and this makes the solution of problems difficult. At present in USSR, the provisional standard concerning the design of atomic energy facilities built in earthquake-prone districts is completed. The basic philosophy of the standard is to decide the general requirements as the conditions for the design of nuclear power stations built in earthquake-prone districts. The lowest earthquake activity in the construction districts is considered as magnitude 4, and in the districts where earthquake activity is magnitude 9 or more, the construction of nuclear power stations is prohibited. Two levels of earthquake action are specified for the design: design earthquake and the largest design earthquake. The construction sites of nuclear power stations must be 15 to 150 km distant from the potential sources of earthquakes. Nuclear power stations are regarded as the aseismatically guaranteed type when the safety of reactors is secured under the application of the standard. The buildings and installations are classified into three classes regarding the aseismatic properties. (Kako, I.)

  4. The Synthetic Biology Open Language (SBOL) provides a community standard for communicating designs in synthetic biology.

    Science.gov (United States)

    Galdzicki, Michal; Clancy, Kevin P; Oberortner, Ernst; Pocock, Matthew; Quinn, Jacqueline Y; Rodriguez, Cesar A; Roehner, Nicholas; Wilson, Mandy L; Adam, Laura; Anderson, J Christopher; Bartley, Bryan A; Beal, Jacob; Chandran, Deepak; Chen, Joanna; Densmore, Douglas; Endy, Drew; Grünberg, Raik; Hallinan, Jennifer; Hillson, Nathan J; Johnson, Jeffrey D; Kuchinsky, Allan; Lux, Matthew; Misirli, Goksel; Peccoud, Jean; Plahar, Hector A; Sirin, Evren; Stan, Guy-Bart; Villalobos, Alan; Wipat, Anil; Gennari, John H; Myers, Chris J; Sauro, Herbert M

    2014-06-01

    The re-use of previously validated designs is critical to the evolution of synthetic biology from a research discipline to an engineering practice. Here we describe the Synthetic Biology Open Language (SBOL), a proposed data standard for exchanging designs within the synthetic biology community. SBOL represents synthetic biology designs in a community-driven, formalized format for exchange between software tools, research groups and commercial service providers. The SBOL Developers Group has implemented SBOL as an XML/RDF serialization and provides software libraries and specification documentation to help developers implement SBOL in their own software. We describe early successes, including a demonstration of the utility of SBOL for information exchange between several different software tools and repositories from both academic and industrial partners. As a community-driven standard, SBOL will be updated as synthetic biology evolves to provide specific capabilities for different aspects of the synthetic biology workflow.

  5. Operating experience and systems analysis at Trillo NPP: A program intended for systematic review of plant safety systems to assess design basis requirements compliance

    International Nuclear Information System (INIS)

    Vega, R. de la

    1996-01-01

    The program was defined to apply to all plant safety systems and/or systems included in plant Technical Specifications. The goal of the program was to ensure, by systematic design, construction, and commissioning review, the adequacy of safety systems, structures and components to fulfill their safety functions. Also, as a result of the program, it was established that a complete, unambiguous, systematic, design basis definition shall take place. And finally, a complete documental review of the plant design shall result from the program execution

  6. Meeting Classroom Needs: Designing Space Physics Educational Outreach for Science Education Standards

    Science.gov (United States)

    Urquhart, M. L.; Hairston, M.

    2008-12-01

    As with all NASA missions, the Coupled Ion Neutral Dynamics Investigation (CINDI) is required to have an education and public outreach program (E/PO). Through our partnership between the University of Texas at Dallas William B. Hanson Center for Space Sciences and Department of Science/Mathematics Education, the decision was made early on to design our educational outreach around the needs of teachers. In the era of high-stakes testing and No Child Left Behind, materials that do not meet the content and process standards teachers must teach cannot be expected to be integrated into classroom instruction. Science standards, both state and National, were the fundamental drivers behind the designs of our curricular materials, professional development opportunities for teachers, our target grade levels, and even our popular informal educational resource, the "Cindi in Space" comic book. The National Science Education Standards include much more than content standards, and our E/PO program was designed with this knowledge in mind as well. In our presentation we will describe how we came to our approach for CINDI E/PO, and how we have been successful in our efforts to have CINDI materials and key concepts make the transition into middle school classrooms. We will also present on our newest materials and high school physics students and professional development for their teachers.

  7. Sandia National Laboratories Facilities Management and Operations Center Design Standards Manual

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, Timothy L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-09-01

    At Sandia National Laboratories in New Mexico (SNL/NM), the design, construction, operation, and maintenance of facilities is guided by industry standards, a graded approach, and the systematic analysis of life cycle benefits received for costs incurred. The design of the physical plant must ensure that the facilities are "fit for use," and provide conditions that effectively, efficiently, and safely support current and future mission needs. In addition, SNL/NM applies sustainable design principles, using an integrated whole-building design approach, from site planning to facility design, construction, and operation to ensure building resource efficiency and the health and productivity of occupants. The safety and health of the workforce and the public, any possible effects on the environment, and compliance with building codes take precedence over project issues, such as performance, cost, and schedule. These design standards generally apply to all disciplines on all SNL/NM projects. Architectural and engineering design must be both functional and cost-effective. Facility design must be tailored to fit its intended function, while emphasizing low-maintenance, energy-efficient, and energy-conscious design. Design facilities that can be maintained easily, with readily accessible equipment areas, low maintenance, and quality systems. To promote an orderly and efficient appearance, architectural features of new facilities must complement and enhance the existing architecture at the site. As an Architectural and Engineering (A/E) professional, you must advise the Project Manager when this approach is prohibitively expensive. You are encouraged to use professional judgment and ingenuity to produce a coordinated interdisciplinary design that is cost-effective, easily contractible or buildable, high-performing, aesthetically pleasing, and compliant with applicable building codes. Close coordination and development of civil, landscape, structural, architectural, fire

  8. Single-Case Experimental Designs: A Systematic Review of Published Research and Current Standards

    Science.gov (United States)

    Smith, Justin D.

    2013-01-01

    This article systematically reviews the research design and methodological characteristics of single-case experimental design (SCED) research published in peer-reviewed journals between 2000 and 2010. SCEDs provide researchers with a flexible and viable alternative to group designs with large sample sizes. However, methodological challenges have precluded widespread implementation and acceptance of the SCED as a viable complementary methodology to the predominant group design. This article includes a description of the research design, measurement, and analysis domains distinctive to the SCED; a discussion of the results within the framework of contemporary standards and guidelines in the field; and a presentation of updated benchmarks for key characteristics (e.g., baseline sampling, method of analysis), and overall, it provides researchers and reviewers with a resource for conducting and evaluating SCED research. The results of the systematic review of 409 studies suggest that recently published SCED research is largely in accordance with contemporary criteria for experimental quality. Analytic method emerged as an area of discord. Comparison of the findings of this review with historical estimates of the use of statistical analysis indicates an upward trend, but visual analysis remains the most common analytic method and also garners the most support amongst those entities providing SCED standards. Although consensus exists along key dimensions of single-case research design and researchers appear to be practicing within these parameters, there remains a need for further evaluation of assessment and sampling techniques and data analytic methods. PMID:22845874

  9. HCPB TBM thermo mechanical design: Assessment with respect codes and standards and DEMO relevancy

    International Nuclear Information System (INIS)

    Cismondi, F.; Kecskes, S.; Aiello, G.

    2011-01-01

    In the frame of the activities of the European TBM Consortium of Associates the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) is developed in Karlsruhe Institute of Technology (KIT). After performing detailed thermal and fluid dynamic analyses of the preliminary HCPB TBM design, the thermo mechanical behaviour of the TBM under typical ITER loads has to be assessed. A synthesis of the different design options proposed has been realized building two different assemblies of the HCPB-TBM: these two assemblies and the analyses performed on them are presented in this paper. Finite Element thermo-mechanical analyses of two detailed 1/4 scaled models of the HCPB-TBM assemblies proposed have been performed, with the aim of verifying the accordance of the mechanical behaviour with the criteria of the design codes and standards. The structural design limits specified in the codes and standard are discussed in relation with the EUROFER available data and possible damage modes. Solutions to improve the weak structural points of the present design are identified and the DEMO relevancy of the present thermal and structural design parameters is discussed.

  10. Innovating cystic fibrosis clinical trial designs in an era of successful standard of care therapies.

    Science.gov (United States)

    VanDevanter, Donald R; Mayer-Hamblett, Nicole

    2017-11-01

    Evolving cystic fibrosis 'standards of care' have influenced recent cystic fibrosis clinical trial designs for new therapies; care additions/improvements will require innovative trial designs to maximize feasibility and efficacy detection. Three cystic fibrosis therapeutic areas (pulmonary exacerbations, Pseudomonas aeruginosa airway infections, and reduced cystic fibrosis transmembrane conductance regulator [CFTR] protein function) differ with respect to the duration for which recognized 'standards of care' have been available. However, developers of new therapies in all the three areas are affected by similar challenges: standards of care have become so strongly entrenched that traditional placebo-controlled studies in cystic fibrosis populations likely to benefit from newer therapies have become less and less feasible. Today, patients/clinicians are more likely to entertain participation in active-comparator trial designs, that have substantial challenges of their own. Foremost among these are the selection of 'valid' active comparator(s), estimation of a comparator's current clinical efficacy (required for testing noninferiority hypotheses), and effective blinding of commercially available comparators. Recent and future cystic fibrosis clinical trial designs will have to creatively address this collateral result of successful past development of effective cystic fibrosis therapies: patients and clinicians are much less likely to accept simple, placebo-controlled studies to evaluate future therapies.

  11. A Robotics Systems Design Need: A Design Standard to Provide the Systems Focus that is Required for Longterm Exploration Efforts

    Science.gov (United States)

    Dischinger, H. Charles., Jr.; Mullins, Jeffrey B.

    2005-01-01

    The United States is entering a new period of human exploration of the inner Solar System, and robotic human helpers will be partners in that effort. In order to support integration of these new worker robots into existing and new human systems, a new design standard should be developed, to be called the Robot-Systems Integration Standard (RSIS). It will address the requirements for and constraints upon robotic collaborators with humans. These workers are subject to the same functional constraints as humans of work, reach, and visibility/situational awareness envelopes, and they will deal with the same maintenance and communication interfaces. Thus, the RSIS will be created by discipline experts with the same sort of perspective on these and other interface concerns as human engineers.

  12. Standards and the design of the Advanced Photon Source control system

    International Nuclear Information System (INIS)

    McDowell, W.P.; Knott, M.J.; Lenkszus, F.R.; Kraimer, M.R.; Daly, R.T.; Arnold, N.D.; Anderson, M.D.; Anderson, J.B.; Zieman, R.C.; Cha, Ben-Chin K.; Vong, F.C.; Nawrocki, G.J.; Gunderson, G.R.; Karonis, N.T.; Winans, J.R.

    1991-01-01

    The Advanced Photon Source (APS), now under construction at Argonne National Laboratory is a 7 GeV positron storage ring dedicated to research facilities using synchrotron radiation. This ring, along with its injection accelerators is to be controlled and monitored with a single, flexible, and expandable control system. In the conceptual stage the control system design group faced the challenges that face all control system designers: to force the machine designers to quantify and codify the system requirements, to protect the investment in hardware and software from rapid obsolescence, and to find methods of quickly incorporating new generations of equipment and replace of obsolete equipment without disrupting the exiting system. To solve these and related problems, the APS control system group made an early resolution to use standards in the design of the system. This paper will cover the present status of the APS control system as well as discuss the design decisions which led us to use industrial standards and collaborations with other laboratories whenever possible to develop a control system. It will explain the APS control system and illustrate how the use of standards has allowed APS to design a control system whose implementation addresses these issues. The system will use high performance graphic workstations using an X-Windows Graphical User Interface at the operator interface level. It connects to VME-based microprocessors at the field level using TCP/IP protocols over high performance networks. This strategy assures the flexibility and expansibility of the control system. A defined interface between the system components will allow the system to evolve with the direct addition of future, improved equipment and new capabilities

  13. Seismic response characteristics of base-isolated AP1000 nuclear shield building subjected to beyond-design basis earthquake shaking

    Directory of Open Access Journals (Sweden)

    Dayang Wang

    2018-02-01

    Full Text Available Because of the design and construction requirements, the nuclear structures need to maintain the structural integrity under both design state and extreme earthquake shaking. The base-isolation technology can significantly reduce the damages of structures under extreme earthquake events, and effectively protect the safeties of structures and internal equipment. This study proposes a base-isolation design for the AP1000 nuclear shield building on considering the performance requirements of the seismic isolation systems and devices of shield building. The seismic responses of isolated and nonisolated shield buildings subjected to design basis earthquake (DBE shaking and beyond-design basis earthquake (BDBE shaking are analyzed, and three different strategies for controlling the displacements subjected to BDBE shaking are performed. By comparing with nonisolated shield buildings, the floor acceleration spectra of isolated shield buildings, relative displacement, and base shear force are significantly reduced in high-frequency region. The results demonstrate that the base-isolation technology is an effective approach to maintain the structural integrity which subjected to both DBE and BDBE shaking. A displacement control design for isolation layers subjected to BDBE shaking, which adopts fluid dampers for controlling the horizontal displacement of isolation layer is developed. The effectiveness of this simple method is verified through numerical analysis.

  14. Impact of National Ambient Air Quality Standards Nonattainment Designations on Particulate Pollution and Health.

    Science.gov (United States)

    Zigler, Corwin M; Choirat, Christine; Dominici, Francesca

    2018-03-01

    Despite dramatic air quality improvement in the United States over the past decades, recent years have brought renewed scrutiny and uncertainty surrounding the effectiveness of specific regulatory programs for continuing to improve air quality and public health outcomes. We employ causal inference methods and a spatial hierarchical regression model to characterize the extent to which a designation of "nonattainment" with the 1997 National Ambient Air Quality Standard for ambient fine particulate matter (PM2.5) in 2005 causally affected ambient PM2.5 and health outcomes among over 10 million Medicare beneficiaries in the Eastern United States in 2009-2012. We found that, on average across all retained study locations, reductions in ambient PM2.5 and Medicare health outcomes could not be conclusively attributed to the nonattainment designations against the backdrop of other regional strategies that impacted the entire Eastern United States. A more targeted principal stratification analysis indicates substantial health impacts of the nonattainment designations among the subset of areas where the designations are estimated to have actually reduced ambient PM2.5 beyond levels achieved by regional measures, with noteworthy reductions in all-cause mortality, chronic obstructive pulmonary disorder, heart failure, ischemic heart disease, and respiratory tract infections. These findings provide targeted evidence of the effectiveness of local control measures after nonattainment designations for the 1997 PM2.5 air quality standard.

  15. Embedded FIR filter design for real-time refocusing using a standard plenoptic video camera

    Science.gov (United States)

    Hahne, Christopher; Aggoun, Amar

    2014-03-01

    A novel and low-cost embedded hardware architecture for real-time refocusing based on a standard plenoptic camera is presented in this study. The proposed layout design synthesizes refocusing slices directly from micro images by omitting the process for the commonly used sub-aperture extraction. Therefore, intellectual property cores, containing switch controlled Finite Impulse Response (FIR) filters, are developed and applied to the Field Programmable Gate Array (FPGA) XC6SLX45 from Xilinx. Enabling the hardware design to work economically, the FIR filters are composed of stored product as well as upsampling and interpolation techniques in order to achieve an ideal relation between image resolution, delay time, power consumption and the demand of logic gates. The video output is transmitted via High-Definition Multimedia Interface (HDMI) with a resolution of 720p at a frame rate of 60 fps conforming to the HD ready standard. Examples of the synthesized refocusing slices are presented.

  16. Development of reliability-based design and assessment standards for onshore gas transmission pipelines

    Energy Technology Data Exchange (ETDEWEB)

    Zhou, Joe; Rothwell, Brian [TransCanada PipeLines Ltd., Calgary, AB (Canada); Nessim, Maher; Zhou, Wenxing [C-FER Technologies, Edmonton, AB (Canada)

    2005-07-01

    Onshore pipelines have traditionally been designed with a deterministic stress based methodology. The changing operating environment has however imposed many challenges to the pipeline industry, including heightened public awareness of risk, more challenging natural hazards and increased economic competitiveness. To meet the societal expectation of pipeline safety and enhance the competitiveness of the pipeline industry, significant efforts have been spent for the development of reliability-based design and assessment (RBDA) methodology. This paper will briefly review the technology development in the RBDA area and the focus will be on the progresses in the past years in standard development within the American Society of Mechanical Engineers (ASME) and the Canadian Standard Association (CSA) organizations. (author)

  17. Regulatory requirements on accident management and emergency preparedness - concept of nuclear and radiation safety during beyond-design-basis accidents

    International Nuclear Information System (INIS)

    Yanke, R.

    2002-01-01

    Actual practice the and proposals for further activities in the field of Accident Management (AM) in the member countries of the Co-operation Forum of WWER regulators and in Western countries have been assessed. Further the results of the last working group on AM , the overview of interactions of severe accident research and the regulatory positions in various countries, IAEA reports, practice in Switzerland and Finland, were taken into consideration. From this information, the working group derived recommendations on Accident Management. The general proposals correspond to the present state of the art on AM. They do not describe the whole spectra of recommendations on AM for NPPs with WWER reactors. A basis for the implementation of an AM program is given, which could be extended in a follow-up working group. The developments and research concerning AM have to be continued. The positions of various countries with regard to the 'Interactions of severe accident research and the regulatory positions' are given. On the basis of the working group proposals, the WWER regulators could set regulatory requirements and support further developments of AM strategies, making use of the benefits of common features of NPPs with WWER reactors. Concerted actions in the field of AM between the WWER regulators would bundle the development of a unified concept of recommendations and speed up the implementation of AM measures in order to minimise the risks involved in nuclear power generation

  18. Assessment of value-impact associated with the elimination of postulated pipe ruptures from the design basis for nuclear power plants

    International Nuclear Information System (INIS)

    Holman, G.S.; Chou, C.K.

    1985-01-01

    The US Nuclear Regulatory Commission is proposing to amend the regulations that currently require that the design basis for nuclear power plants include the postulation of dynamic effects from loss of coolant accidents up to and including the double-ended rupture of the largest pipe in the reactor coolant system. Proposed modifications would allow analyses to serve as a sufficient basis for excluding dynamic effects, including but not necessarily limited to pipe whip and jet impingement, associated with specific pipe ruptures. Only dynamic effects would be impacted; current design requirements for containment sizing and discharge capacity of emergency core cooling systems would remain unchanged. This report presents a detailed analysis of value-impact associated with the proposed amendment for PWR reactor coolant loop piping and for BWR recirculation loop piping. The effect of extending application of the proposed rule change to other piping systems is also assessed in a less quantitative manner

  19. Critical parameters affecting the design of high frequency transmission lines in standard CMOS technology

    KAUST Repository

    Al Attar, Talal

    2017-05-13

    Different structures of transmission lines were designed and fabricated in standard CMOS technology to estimate some critical parameters including the RMS value of the surface roughness and the loss tangent. The input impedances for frequencies up to 50 GHz were modeled and compared with measurements. The results demonstrated a strong correlation between the used model with the proposed coefficients and the measured results, attesting the robustness of the model and the reliability of the incorporated coefficients values.

  20. Design of a large deformable obstacle for railway crash simulations according to the applicable standard

    Directory of Open Access Journals (Sweden)

    Špirk S.

    2012-06-01

    Full Text Available This article discusses the design of a deformable obstacle to be used in simulated rail and road vehicle collisions as prescribed by scenario 3 specified by standard ČSN EN 15227. To approve a vehicle in accordance with this standard, it is necessary to carry out numeric simulations of its collision with a large obstacle, following the standard’s specification. A simulated impact of a rigid ball into the obstacle is used to calibrate the obstacle’s properties, and the standard specifies limit deformation characteristics for that collision. The closer are the deformation characteristics observed in the test to the limit characteristics prescribed by the standard, the more favorable results can be expected when using the obstacle in actual numeric simulations of frontal impacts of rail vehicles. There are multiple ways to design a FEM model of the obstacle; this article discusses one of those. It shows that given a suitable definition of material properties, this particular approach yields quite favorable deformation characteristics.

  1. Regulatory standpoints on the design-basis capability of safety-related motor-operated valves(MOVs) and power-operated gate valves(POGVs)

    International Nuclear Information System (INIS)

    Kim, W. T.; Kum, O. H.

    1999-01-01

    The weakness in the design-basis capability of Motor-Operated Valves(MOVs) and the susceptibility to Pressure Locking and Thermal Binding phenomena of Power-Operated Gate Valves(POGVs) have been major concerns to be resolved in the nuclear society in and abroad since Three Mile Island accident occurred in the USA in 1979. Through detailed analysis of operating experience and regulatory activities, some MOVs and POGVs have been found to be unreliable in performing their safety functions when they are required to do so under certain conditions, especially under design-basis accident conditions. Further, it is well understood that these safety problems may not be identified by the typical valve in-service testing(IST). USNRC has published three Generic Letters, GL 89-10, GL 95-07, and GL 96-05, requiring nuclear plant licensees to take appropriate actions to resolve the problems mentioned above. Korean nuclear regulatory body has made public an administration measure called 'Regulatory recommendation to verify safety functions of the safety-related MOVs and POGVs' on June 13, 1997, and in this administration measure Korean utility is asked to submit written documents to show how it assure design-basis capability of these valves. The following are among the major concerns being considered from a regulation standpoint. Program scope and implementation priority, dynamic tests under differential pressure conditions, accuracy of diagnostic equipment, torque switch setting and torque bypass percentage, weak link analysis, motor actuator sizing, corrective actions taken to resolve pressure locking and thermal binding susceptibility, and a periodic verification program for the valves once design-basis capability has been verified

  2. Safety Standard for Oxygen and Oxygen Systems: Guidelines for Oxygen System Design, Materials Selection, Operations, Storage, and Transportation

    Science.gov (United States)

    1996-01-01

    NASA's standard for oxygen system design, materials selection, operation, and transportation is presented. Minimum guidelines applicable to NASA Headquarters and all NASA Field Installations are contained.

  3. An efficient auto TPT stitch guidance generation for optimized standard cell design

    Science.gov (United States)

    Samboju, Nagaraj C.; Choi, Soo-Han; Arikati, Srini; Cilingir, Erdem

    2015-03-01

    As the technology continues to shrink below 14nm, triple patterning lithography (TPT) is a worthwhile lithography methodology for printing dense layers such as Metal1. However, this increases the complexity of standard cell design, as it is very difficult to develop a TPT compliant layout without compromising on the area. Hence, this emphasizes the importance to have an accurate stitch generation methodology to meet the standard cell area requirement as defined by the technology shrink factor. In this paper, we present an efficient auto TPT stitch guidance generation technique for optimized standard cell design. The basic idea here is to first identify the conflicting polygons based on the Fix Guidance [1] solution developed by Synopsys. Fix Guidance is a reduced sub-graph containing minimum set of edges along with the connecting polygons; by eliminating these edges in a design 3-color conflicts can be resolved. Once the conflicting polygons are identified using this method, they are categorized into four types [2] - (Type 1 to 4). The categorization is based on number of interactions a polygon has with the coloring links and the triangle loops of fix guidance. For each type a certain criteria for keep-out region is defined, based on which the final stitch guidance locations are generated. This technique provides various possible stitch locations to the user and helps the user to select the best stitch location considering both design flexibility (max. pin access/small area) and process-preferences. Based on this technique, a standard cell library for place and route (P and R) can be developed with colorless data and a stitch marker defined by designer using our proposed method. After P and R, the full chip (block) would contain the colorless data and standard cell stitch markers only. These stitch markers are considered as "must be stitch" candidates. Hence during full chip decomposition it is not required to generate and select the stitch markers again for the

  4. Steric Hindrance as a Basis for Structure-Based Design of Selective Inhibitors of Protein-Tyrosine Phosphatases

    DEFF Research Database (Denmark)

    Iversen, L. F.; Andersen, H. S.; Møller, K. B.

    2001-01-01

    Utilizing structure-based design, we have previously demonstrated that it is possible to obtain selective inhibitors of protein-tyrosine phosphatase 1B (PTP1B). A basic nitrogen was introduced into a general PTP inhibitor to form a salt bridge to Asp48 in PTP1B and simultaneously cause repulsion...... residues in the same position in other PTPs cause steric hindrance and reduced substrate recognition capacity [Peters, G. H., et al. (2000) J. Biol. Chem. 275, 18201−18209]. The current study was undertaken to investigate the feasibility of structure-based design, utilizing these differences...... in accessibility to the active site among various PTPs. We show that a general, low-molecular weight PTP inhibitor can be developed into a highly selective inhibitor for PTP1B and TC-PTP by introducing a substituent, which is designed to address the region around residues 258 and 259. Detailed enzyme kinetic...

  5. Development of Pupils Picture Aesthetic Competences on the Basis of IT-didactic Designs of Digital Picture Production

    DEFF Research Database (Denmark)

    Rasmussen, Helle

    of subjects in school. The project is due to different facts: Digital pictures are increased factors in the development of culture, in socializing and in bildung. (Tholle 2007). Furthermore new genres and ways of using digital pictures and medias continuously develop. (Sørensen 2002). This ought...... competence - expected to develop and argue for a specific model for IT-didactic design of digital picture production, which makes the development of pupil’s picture aesthetic competences probable. References: (Only the most important references for the abstract) Buhl, Mie (2002): “Paradoxical Visual Arts...... Education” (English Title), The Danish University of Education Cobb, P. et al. (2003): “Design Experiments in Educational Research” in “Educational Researcher”, vol. 32, no. 1. Collins, Allan et. al. (2004): “Design Research: Theoretical and Metodological Issuses” in “Journal of the Learning Sciences”, Vol...

  6. Scientific basis and engineering design to accommodate disruption and halo current loads for the DIII-D tokamak

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, P.M.; Bozek, A.S.; Hollerbach, M.A.; Humphreys, D.A.; Luxon, J.L.; Reis, E.E.; Schaffer, M.J.

    1996-10-01

    Plasma disruptions and halo current events apply sudden impulsive forces to the interior structures and vacuum vessel walls of tokamaks. These forces arise when induced toroidal currents and attached poloidal halo currents in plasma facing components interact with the poloidal and toroidal magnetic fields respectively. Increasing understanding of plasma disruptions and halo current events has been developed from experiments on DIII-D and other machines. Although the understanding has improved, these events must be planned for in system design because there is no assurance that these events can be eliminated in the operation of tokamaks. Increased understanding has allowed an improved focus of engineering designs.

  7. Scientific basis and engineering design to accommodate disruption and halo current loads for the DIII-D tokamak

    International Nuclear Information System (INIS)

    Anderson, P.M.; Bozek, A.S.; Hollerbach, M.A.; Humphreys, D.A.; Luxon, J.L.; Reis, E.E.; Schaffer, M.J.

    1996-10-01

    Plasma disruptions and halo current events apply sudden impulsive forces to the interior structures and vacuum vessel walls of tokamaks. These forces arise when induced toroidal currents and attached poloidal halo currents in plasma facing components interact with the poloidal and toroidal magnetic fields respectively. Increasing understanding of plasma disruptions and halo current events has been developed from experiments on DIII-D and other machines. Although the understanding has improved, these events must be planned for in system design because there is no assurance that these events can be eliminated in the operation of tokamaks. Increased understanding has allowed an improved focus of engineering designs

  8. Materials, Designs and Standards Used in Ski-Boots for Alpine Skiing

    Directory of Open Access Journals (Sweden)

    Matteo Moncalero

    2013-10-01

    Full Text Available This review article reports the recent advances in the study, design and production of ski-boots for alpine skiing. An overview of the different designs and the materials used in ski-boot construction is provided giving particular emphasis to the effect of these parameters on the final performances and on the prevention of injuries. The use of specific materials for ski-boots dedicated to different disciplines (race skiing, mogul skiing, ski-mountaineering etc. has been correlated with the chemical and physical properties of the polymeric materials employed. A review of the scientific literature and the most interesting patents is also presented, correlating the results reported with the performances and industrial production of ski-boots. Suggestions for new studies and the use of advanced materials are also provided. A final section dedicated to the standards involved in ski-boot design completes this review article.

  9. Performance based building design to ensure building quality: from standardization to LEAN construction

    Directory of Open Access Journals (Sweden)

    Carlo Zanchetta

    2014-10-01

    Full Text Available The discipline of architectural design is influenced by the standardization activities concerning the construction and the development of tools for the coordination in the design process such as Building Information Modeling. The two disciplines contribute reciprocally to the achievement of the overall quality of the building process. To do so, it is strategic to develop researches on the following aspects: - definition of frameworks for the connection of the building system requirements to space and technology unit that defines it; - development of an inventory of interoperable and compliant technical solutions; - implementation of the discipline of model checking for project validation; and methodologies of comparison between intervention models; - implementation of collaborative environments for verification of compatibility between programs and regulations in order to identify the optimal design solution.

  10. Designing and Evaluating Tutoring Feedback Strategies for Digital Learning Environments on the Basis of the Interactive Tutoring Feedback Model

    Science.gov (United States)

    Narciss, Susanne

    2013-01-01

    This paper describes the interactive tutoring feedback model (ITF-model; Narciss, 2006; 2008), and how it can be applied to the design and evaluation of feedback strategies for digital learning environments. The ITF-model conceptualizes formative tutoring feedback as a multidimensional instructional activity that aims at contributing to the…

  11. The Cognitive and Behavioral Basis of an Instructional Design: Using CBT to Teach Technical Information and Learning Strategies.

    Science.gov (United States)

    Cook, E. K.; Kazlauskas, E. J.

    1993-01-01

    Describes a project that was developed to create production guidelines for instructional design of computer-based training (CBT) for industrial purposes. Topics addressed include Bloom's Taxonomy; Gagne's Events of Instruction; behavioral foundations; cognitive foundations; simulation as an example of cognitive instruction; learner control;…

  12. A Basis for the Design of a Curriculum Incorporating Music and Drama in Children's English Language Instruction

    Science.gov (United States)

    Rodríguez-Bonces, Monica

    2017-01-01

    This article presents the foundations to design a curriculum that integrates music and drama as strategies for the teaching of English as a foreign language. Besides promoting interdisciplinarity, this curriculum seeks to improve the language level of those children attending continuing educational programs at any higher education institution. The…

  13. Highly accurate CCSD(R12) and CCSD(F12) optical response properties using standard triple-ζ basis sets

    Science.gov (United States)

    Yang, Jun; Hättig, Christof

    2009-08-01

    Coupled-cluster response theory for frequency-dependent optical properties within the coupled-cluster singles-and-doubles model (CCSD) has been derived and implemented for ansatz 2 of the explicitly correlated CCSD(R12) and CCSD(F12) methods as part of the program package DALTON. The basis set convergence of static dipole moments, polarizabilities, and parallel averages of first and second hyperpolarizabilities has been investigated for Ne, BH, N2, CO, and BF. The frequency-dependent results are presented for the electronic second-harmonic generation of N2. With triple-ζ basis sets, the CCSD(F12) correlation contributions using ansatz 2 are close to the basis set limits for dipole moments and second hyperpolarizabilities; the CCSD(R12) results are better than the CCSD results obtained with at least quintuple-ζ basis sets for polarizabilities and first hyperpolarizabilities. The exponent of Slater-type correlation factor for CCSD(F12) ground state energy may not be optimal and has to be re-examined for response properties. We also suggest that the remaining one-electron basis set errors arising within the coupled-cluster singles should be reduced by allowing excitations into the auxiliary orbital space.

  14. A Framework for Improving Project Performance of Standard Design Models in Saudi Arabia

    Directory of Open Access Journals (Sweden)

    Shabbab Al-Otaib

    2013-07-01

    Full Text Available Improving project performance in the construction industry poses several challenges for stakeholders. Recently, there have been frequent calls for the importance of adopting standardisation in improving construction design as well as the process and a focus on learning mapping from other industries. The Saudi Ministry of Interior (SMoI has adopted a new Standard Design Model (SDM approach for the development of its construction programme to effectively manage its complex project portfolio and improve project performance. A review of existing literature indicates that despite the adoption of SDM repetitive projects, which enable learning from past mistakes and improving the performance of future projects, it has been realised that there is a lack of learning instruments to capture, store and disseminate Lessons Learnt (LL. This research proposes a framework for improving the project performance of SDMs in the Saudi construction industry. Eight case studies related to a typical standard design project were performed that included interviews with of 24 key stakeholders who are involved in the planning and implementation of SDM projects within the SMoI. The research identified 14 critical success factors CSFs have a direct impact on the SDM project performance. These are classified into three main CSF-related clusters: adaptability to the context; contract management; and construction management. A framework, which comprises the identified 14 CSFs, was developed, refined and validated through a workshop with 12 key stakeholders in the SMoI construction programme. Additionally, a framework implementation process map was developed. Web-based tools and KM were identified as core factors in the framework implementation strategy. Although many past CSF-related studies were conducted to develop a range of construction project performance improvement frameworks, the paper provides the first initiative to develop a framework to improve the performance of

  15. 41 CFR 102-76.25 - What standards must Federal agencies meet in providing architectural and interior design services?

    Science.gov (United States)

    2010-07-01

    ... Federal agencies meet in providing architectural and interior design services? 102-76.25 Section 102-76.25...) FEDERAL MANAGEMENT REGULATION REAL PROPERTY 76-DESIGN AND CONSTRUCTION Design and Construction § 102-76.25 What standards must Federal agencies meet in providing architectural and interior design services...

  16. Design and validation of a standards-based science teacher efficacy instrument

    Science.gov (United States)

    Kerr, Patricia Reda

    National standards for K--12 science education address all aspects of science education, with their main emphasis on curriculum---both science subject matter and the process involved in doing science. Standards for science teacher education programs have been developing along a parallel plane, as is self-efficacy research involving classroom teachers. Generally, studies about efficacy have been dichotomous---basing the theoretical underpinnings on the work of either Rotter's Locus of Control theory or on Bandura's explanations of efficacy beliefs and outcome expectancy. This study brings all three threads together---K--12 science standards, teacher education standards, and efficacy beliefs---in an instrument designed to measure science teacher efficacy with items based on identified critical attributes of standards-based science teaching and learning. Based on Bandura's explanation of efficacy being task-specific and having outcome expectancy, a developmental, systematic progression from standards-based strategies and activities to tasks to critical attributes was used to craft items for a standards-based science teacher efficacy instrument. Demographic questions related to school characteristics, teacher characteristics, preservice background, science teaching experience, and post-certification professional development were included in the instrument. The instrument was completed by 102 middle level science teachers, with complete data for 87 teachers. A principal components analysis of the science teachers' responses to the instrument resulted in two components: Standards-Based Science Teacher Efficacy: Beliefs About Teaching (BAT, reliability = .92) and Standards-Based Science Teacher Efficacy: Beliefs About Student Achievement (BASA, reliability = .82). Variables that were characteristic of professional development activities, science content preparation, and school environment were identified as members of the sets of variables predicting the BAT and BASA

  17. An adaptive software defined radio design based on a standard space telecommunication radio system API

    Science.gov (United States)

    Xiong, Wenhao; Tian, Xin; Chen, Genshe; Pham, Khanh; Blasch, Erik

    2017-05-01

    Software defined radio (SDR) has become a popular tool for the implementation and testing for communications performance. The advantage of the SDR approach includes: a re-configurable design, adaptive response to changing conditions, efficient development, and highly versatile implementation. In order to understand the benefits of SDR, the space telecommunication radio system (STRS) was proposed by NASA Glenn research center (GRC) along with the standard application program interface (API) structure. Each component of the system uses a well-defined API to communicate with other components. The benefit of standard API is to relax the platform limitation of each component for addition options. For example, the waveform generating process can support a field programmable gate array (FPGA), personal computer (PC), or an embedded system. As long as the API defines the requirements, the generated waveform selection will work with the complete system. In this paper, we demonstrate the design and development of adaptive SDR following the STRS and standard API protocol. We introduce step by step the SDR testbed system including the controlling graphic user interface (GUI), database, GNU radio hardware control, and universal software radio peripheral (USRP) tranceiving front end. In addition, a performance evaluation in shown on the effectiveness of the SDR approach for space telecommunication.

  18. Pine Flat Dam Fish and Wildlife Habitat Restoration, Fresno, California. Appendix C. Basis of Design and Cost Estimate Office Report

    Science.gov (United States)

    2001-12-01

    Analysis Program SAP2000 . B. Materials. - All materials are subject to the requirements of applicable American Society for Testing and Materials (ASTM...Computer Program. - SAP2000 - Integrated Finite Element Analysis and Design of Structures by CSI, Inc. ( Computers and Structures, Inc.) Berkeley, CA...locations. B. Loading Conditions. - Each rigid frame and structure was modeled as one structure in SAP2000 . At this time only the dead weight of the

  19. Design Basis of Core Components and their Realization in the frame of the EPR'sTM Core Component Development

    International Nuclear Information System (INIS)

    Schebitz, Florian; Mekmouche, Abdelhalim

    2008-01-01

    Rod Cluster Control Assemblies (RCCAs), Thimble Plug Assemblies (TPAs), Primary Neutron Sources (PNS) and Secondary Neutron Sources (SNS) are essential for the operation of a Nuclear Power Plant. Different functional requirements ask for different components and geometries. Therefore three different core components are used within the primary circuit: - The RCCA, which contains the absorber materials, is used to regulate and shut down the nuclear chain reaction. Under these demanding conditions different effects are determining the lifetime of the RCCA and in particular of the control rods. Several improvements like ion-nitriding of the cladding, lengthening of the bottom end plug, helium backfilling and reduction of the absorber diameter in the bottom part, which have already been introduced with the HARMONI TM RCCA, show a real improvement in terms of lifetime. - The TPAs are used at positions without RCCAs and neutron sources to limit the by-pass flow-rate in the fuel assembly guide tubes. The advanced TPA design results from a perfect combination of French and German design experience feedback. Benefits like homogenized hydraulic flow and improved manageability in terms of handling tools show the joined experience. - The neutron sources are used to enhance the flux level when the core is sub-critical so as to facilitate the core start-up control by the neutron flux detectors. Primary and secondary neutron sources are designed in a common way with reviewed and improved methodology. As there are different ways and conditions to operate core components, several designs are available. For the EPR TM , the best methods and products have been chosen. All chosen components contribute to an optimized and safe operation of the EPR TM . (authors)

  20. Designing and Evaluating Tutoring Feedback Strategies for digital learning environments on the basis of the Interactive Tutoring Feedback Model

    Directory of Open Access Journals (Sweden)

    Susanne Narciss

    2013-06-01

    Full Text Available This paper describes the interactive tutoring feedback model (ITF-model; Narciss, 2006; 2008, and how it can be applied to the design and evaluation of feedback strategies for digital learning environments. The ITF-model conceptualizes formative tutoring feedback as a multidimensional instructional activity that aims at contributing to the regulation of a learning process in order to help learners acquire or improve the competencies needed to master learning tasks. It integrates findings from systems theory with recommendations of prior research on interactive instruction and elaborated feedback, on task analyses, on error analyses, and on tutoring techniques. Based on this multi-dimensional view of formative tutoring feedback methodological implications for designing and investigating multiple effects of feedback under multiple individual and situational conditions are described. Furthermore, the paper outlines how the implications of the ITF-model have been applied in several studies to the design and evaluation of tutoring feedback strategies for digital learning environments (e.g., Narciss, 2004; Narciss & Huth, 2006; Narciss, Schnaubert, Andres, Eichelmann, Goguadze, & Sosnovsky, 2013.

  1. Research on a methodology for standardization of engineering data in nuclear power plant design

    International Nuclear Information System (INIS)

    Kang, K. D.; Moon, C. K.; Baik, J. H.

    1999-01-01

    The standardization of data and the integration of system are emerging as important issues since each company should handle various kinds of information which is originated from the distributed resources due to rapid development of information technology. Especially for the case of nuclear power plant, the integration of data is very essential since all the data generated during plant lifetime of 40 to 60 years should be maintained and various entities participated in the phase of design, construction and operation of the plant. It is desirable to adopt SGML as a standard in a long-term base for the standardization of NPP engineering data, however there are some difficulties to apply it in current stage. So it is a viable approach to utilize XML as an interim base. In the case of drawings, it is desirable to apply STEP in a long-term base and to apply CAD system in a near term, which can support IGES. Also IGES can be applied in order to store and exchange the drawings. Furthermore, it can be considered to use VRML as a standard for the three dimensional drawings due to the rapid expansion of internet in recent years

  2. GUIDELINES FOR THE DESIGN OF INSTRUMENTS OF COMPETENCE ASSESSMENT FROM MEASURABLE LEARNING STANDARDS

    Directory of Open Access Journals (Sweden)

    Ignacio Polo Martínez

    2015-06-01

    Full Text Available The evaluation is not enough to improve education necessary but. There are no magic to educational problems through assessment solutions. However, the evaluation, in partnership with the methodology, should be treated as determinants of the quality and improving education. Surely, many teachers agree that it is not easy to design assessment tools that are consistent with the teaching-learning competence and, in turn, with rigorous curriculum standards and assessment of the Autonomous Community. However, this difficulty should not be considered as an impossibility. Through this article aims to contribute to building an improvement plan associated with the design of the evaluation instruments from different areas or subjects. Such a design should be based on at least the following: I want to evaluate (referring to assessment criteria and standards of assessable learning included in the instrument and I will evaluate (referencing jurisdictional situations linked to next and known student context, HOW I WILL QUALIFY (preserving the right of students to an objective evaluation and what consequences they will have the results for the different agents that make up the educational community.

  3. SynBioHub: A Standards-Enabled Design Repository for Synthetic Biology.

    Science.gov (United States)

    McLaughlin, James Alastair; Myers, Chris J; Zundel, Zach; Mısırlı, Göksel; Zhang, Michael; Ofiteru, Irina Dana; Goñi-Moreno, Angel; Wipat, Anil

    2018-02-16

    The SynBioHub repository ( https://synbiohub.org ) is an open-source software project that facilitates the sharing of information about engineered biological systems. SynBioHub provides computational access for software and data integration, and a graphical user interface that enables users to search for and share designs in a Web browser. By connecting to relevant repositories (e.g., the iGEM repository, JBEI ICE, and other instances of SynBioHub), the software allows users to browse, upload, and download data in various standard formats, regardless of their location or representation. SynBioHub also provides a central reference point for other resources to link to, delivering design information in a standardized format using the Synthetic Biology Open Language (SBOL). The adoption and use of SynBioHub, a community-driven effort, has the potential to overcome the reproducibility challenge across laboratories by helping to address the current lack of information about published designs.

  4. SSTL I/O Standard Based Environment Friendly Energy Efficient ROM Design on FPGA

    DEFF Research Database (Denmark)

    Bansal, Neha; Bansal, Meenakshi; Saini, Rishita

    2014-01-01

    GHz frequency in place of 4GHz. There is no change in clock power and signal power but SSTL2_II_DCI having 80.24%, 83.38%, 62.92%, and 76.52% and 83.03% more I/O power consumption with respect to SSTL2_I, SST18_I, SSTL2_I_DCI, SSTL2_II, and SSTL15 respectively at 3.3GHz.......Stub Series Terminated Logic (SSTL) is an Input/output standard. It is used to match the impedance of line, port and device of our design under consideration. Therefore, selection of energy efficient SSTL I/O standard among available different class of SSTL logic family in FPGA, plays a vital role...... to achieve energy efficiency in design under test (DUT). Here, DUT is ROM. ROM is an integral part of processor. Therefore, energy efficient design of RAM is a building block of energy efficient processor. We are using Verilog hardware description language, Virtex-6 FPGA, and Xilinx ISE simulator. We...

  5. International Standardization in the Design of "Shore to Ship" - Power Supply Systems of Ships in Port

    Science.gov (United States)

    Tarnapowicz, Dariusz; German-Galkin, Sergiej

    2018-03-01

    The decisive source of air pollution emissions in ports is the berthed ships. This is primarily caused by the work of ship's autonomous generator sets. One way of reducing the air pollution emissions in ports is the supply of ships from electricity inland system. The main problem connected with the power connection of ships to the inland network is caused by different values of levels and frequencies of voltages in these networks (in various countries) in relation to different values of levels and frequencies of voltages present in the ship's network. It is also important that the source power can range from a few hundred kW up to several MW. In order to realize a universal „Shore to Ship" system that allows the connection of ships to the electricity inland network, the international standardization is necessary. This article presents the current recommendations, standards and regulations for the design of „Shore to Ship" systems.

  6. Systematic Approach to Design Tailor Made Fuel Blends That Meets ASTM Standards

    DEFF Research Database (Denmark)

    Intikhab, S.; Kalakul, Sawitree; H., Choudhury

    2015-01-01

    blends [1]. The main architecture in MINLP has four structures viz., (i) problem definition (ii) property model identification (iii) mixture blend design and (iv) model-based verification. These structures are further subdivided in to sub-problems and a decomposition based solution approach was adopted...... point, vapor pressure, and heat content were determined using analytical instruments according to their respective American Society for Testing and Materials (ASTM) standards. Most of the properties complied well with the industry standards. However, model gasoline had a comparatively low RVP....... On the other hand, model diesel had a significantly higher cloud point and pour point than what is recommended. This deviation will have an impact on the cold flow properties of the fuels. For both fuels, different additives along with their composition have also been determined using the same computational...

  7. Building a computer-aided design capability using a standard time share operating system

    Science.gov (United States)

    Sobieszczanski, J.

    1975-01-01

    The paper describes how an integrated system of engineering computer programs can be built using a standard commercially available operating system. The discussion opens with an outline of the auxiliary functions that an operating system can perform for a team of engineers involved in a large and complex task. An example of a specific integrated system is provided to explain how the standard operating system features can be used to organize the programs into a simple and inexpensive but effective system. Applications to an aircraft structural design study are discussed to illustrate the use of an integrated system as a flexible and efficient engineering tool. The discussion concludes with an engineer's assessment of an operating system's capabilities and desirable improvements.

  8. Design of Standards and Labeling programs in Chile: Techno-Economic Analysis for Refrigerators

    Energy Technology Data Exchange (ETDEWEB)

    Letschert, Virginie E. [Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States). Environmental Energy Technologies Division.; McNeil, Michael A. [Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States). Environmental Energy Technologies Division.; Pavon, Mariana [Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States). Environmental Energy Technologies Division.; Lutz, Wolfgang F. [Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States). Environmental Energy Technologies Division.

    2013-05-01

    Lawrence Berkeley National Laboratory is a global leader in the study of energy efficiency and its effective implementation through government policy. The Energy Analysis and Environmental Impacts Department of LBNL’s Environmental Energy Technologies Division provides technical assistance to help federal, stat e and local government agencies in the United States, and throughout the world, develop long-term strategies, policy, and programs to encourage energy efficiency in all sectors and industries. In the past, LBNL has assisted staff of various countries government agencies and their con tractors in providing methodologies to analyze cost-effectiveness of regulations and asses s overall national impacts of efficiency programs. The paper presents the work done in collaboration with the Ministry of Energy (MoE) in Chile and the Collaborative Labeling Appliance Standards Programs (CLASP) on designing a Minimum Energy Performance Standards (MEPS) and ext ending the current labeling program for refrigerators.

  9. Clinical Trial Design for HIV Prevention Research: Determining Standards of Prevention.

    Science.gov (United States)

    Dawson, Liza; Zwerski, Sheryl

    2015-06-01

    This article seeks to advance ethical dialogue on choosing standards of prevention in clinical trials testing improved biomedical prevention methods for HIV. The stakes in this area of research are high, given the continued high rates of infection in many countries and the budget limitations that have constrained efforts to expand treatment for all who are currently HIV-infected. New prevention methods are still needed; at the same time, some existing prevention and treatment interventions have been proven effective but are not yet widely available in the countries where they most urgently needed. The ethical tensions in this field of clinical research are well known and have been the subject of extensive debate. There is no single clinical trial design that can optimize all the ethically important goals and commitments involved in research. Several recent articles have described the current ethical difficulties in designing HIV prevention trials, especially in resource limited settings; however, there is no consensus on how to handle clinical trial design decisions, and existing international ethical guidelines offer conflicting advice. This article acknowledges these deep ethical dilemmas and moves beyond a simple descriptive approach to advance an organized method for considering what clinical trial designs will be ethically acceptable for HIV prevention trials, balancing the relevant criteria and providing justification for specific design decisions. Published 2014. This article is a U.S. Government work and is in the public domain in the USA.

  10. Earthquakes and aseismatic design standard for nuclear power stations in F.R. Germany

    International Nuclear Information System (INIS)

    Ide, Akira

    1976-01-01

    Brief history of the earthquakes in F.R. Germany for the period from 1000 to 1969 is reviewed, and comparison of the aseismatic design of nuclear power stations between F.R. Germany and Japan is made. Earthquakes of intensity 7 (maximum acceleration value of 70 to 220 gal) and 8 (that of 150 to 300 gal) could be expected to occur in F.R. Germany, according to European seismic committee. The definitions of safety earthquake (Sicherheitserdbeben) and design earthquake (Auslegungserdbeben) are compared with the Japanese terms, S-2 (maximum possible earthquake giving the strongest vibration to site base) and S-1 (maximum probable earthquake giving the strongest vibration to site base). The total area of F.R. Germany is classified into four zones according to dangerousness. Aseismatic design in F.R. Germany is classified into two classes, whereas that in Japan into three or four classes. In F.R. Germany, either dynamic analysis, simple analysis, or omission of analysis is employed. F.R. Germany employs the waves of E1-centro, Taft, etc. of USA as standard, referring to U.S.N.R.C. 1.60 and Housner's equation. The attenuation coefficient and the allowable stress are also compared. A power plant to be exported to Iran is designed at SE of 500 gal and AE of 250 gal, which are approximately equal to the maximum earthquake acceleration for design in Japan. (Iwakiri, K.)

  11. Analysis of the metallic containment integrity of Angra 2/3 reactor under the effects of the design basis accident

    International Nuclear Information System (INIS)

    Costa, J.R.

    1981-06-01

    The application of Condru 4 computer code, developed to determine the maximum values of pressure and temperature that occur inside the metallic containment building of PWR nuclear power plants, in case of a hypothetic accident - LOCA - considered as a Design Basic Accident - DBA. The hypothesis, input and results for the simulation of a loss of coolant in the hot leg of the Angra-2/3 reactors, considered as the most critical case for that Kind of project, are presented. The analysis was made with input provided by the manufacturer. (Author) [pt

  12. Design, experiments and simulation of voltage transformers on the basis of a differential input D-dot sensor.

    Science.gov (United States)

    Wang, Jingang; Gao, Can; Yang, Jie

    2014-07-17

    Currently available traditional electromagnetic voltage sensors fail to meet the measurement requirements of the smart grid, because of low accuracy in the static and dynamic ranges and the occurrence of ferromagnetic resonance attributed to overvoltage and output short circuit. This work develops a new non-contact high-bandwidth voltage measurement system for power equipment. This system aims at the miniaturization and non-contact measurement of the smart grid. After traditional D-dot voltage probe analysis, an improved method is proposed. For the sensor to work in a self-integrating pattern, the differential input pattern is adopted for circuit design, and grounding is removed. To prove the structure design, circuit component parameters, and insulation characteristics, Ansoft Maxwell software is used for the simulation. Moreover, the new probe was tested on a 10 kV high-voltage test platform for steady-state error and transient behavior. Experimental results ascertain that the root mean square values of measured voltage are precise and that the phase error is small. The D-dot voltage sensor not only meets the requirement of high accuracy but also exhibits satisfactory transient response. This sensor can meet the intelligence, miniaturization, and convenience requirements of the smart grid.

  13. Design, Experiments and Simulation of Voltage Transformers on the Basis of a Differential Input D-dot Sensor

    Directory of Open Access Journals (Sweden)

    Jingang Wang

    2014-07-01

    Full Text Available Currently available traditional electromagnetic voltage sensors fail to meet the measurement requirements of the smart grid, because of low accuracy in the static and dynamic ranges and the occurrence of ferromagnetic resonance attributed to overvoltage and output short circuit. This work develops a new non-contact high-bandwidth voltage measurement system for power equipment. This system aims at the miniaturization and non-contact measurement of the smart grid. After traditional D-dot voltage probe analysis, an improved method is proposed. For the sensor to work in a self-integrating pattern, the differential input pattern is adopted for circuit design, and grounding is removed. To prove the structure design, circuit component parameters, and insulation characteristics, Ansoft Maxwell software is used for the simulation. Moreover, the new probe was tested on a 10 kV high-voltage test platform for steady-state error and transient behavior. Experimental results ascertain that the root mean square values of measured voltage are precise and that the phase error is small. The D-dot voltage sensor not only meets the requirement of high accuracy but also exhibits satisfactory transient response. This sensor can meet the intelligence, miniaturization, and convenience requirements of the smart grid.

  14. Applying Human-performance Models to Designing and Evaluating Nuclear Power Plants: Review Guidance and Technical Basis

    International Nuclear Information System (INIS)

    O'Hara, J.M.

    2009-01-01

    Human performance models (HPMs) are simulations of human behavior with which we can predict human performance. Designers use them to support their human factors engineering (HFE) programs for a wide range of complex systems, including commercial nuclear power plants. Applicants to U.S. Nuclear Regulatory Commission (NRC) can use HPMs for design certifications, operating licenses, and license amendments. In the context of nuclear-plant safety, it is important to assure that HPMs are verified and validated, and their usage is consistent with their intended purpose. Using HPMs improperly may generate misleading or incorrect information, entailing safety concerns. The objective of this research was to develop guidance to support the NRC staff's reviews of an applicant's use of HPMs in an HFE program. The guidance is divided into three topical areas: (1) HPM Verification, (2) HPM Validation, and (3) User Interface Verification. Following this guidance will help ensure the benefits of HPMs are achieved in a technically sound, defensible manner. During the course of developing this guidance, I identified several issues that could not be addressed; they also are discussed.

  15. High-Affinity α-Conotoxin PnIA Analogs Designed on the Basis of the Protein Surface Topography Method

    Science.gov (United States)

    Kasheverov, Igor E.; Chugunov, Anton O.; Kudryavtsev, Denis S.; Ivanov, Igor A.; Zhmak, Maxim N.; Shelukhina, Irina V.; Spirova, Ekaterina N.; Tabakmakher, Valentin M.; Zelepuga, Elena A.; Efremov, Roman G.; Tsetlin, Victor I.

    2016-01-01

    Despite some success for small molecules, elucidating structure–function relationships for biologically active peptides — the ligands for various targets in the organism — remains a great challenge and calls for the development of novel approaches. Some of us recently proposed the Protein Surface Topography (PST) approach, which benefits from a simplified representation of biomolecules’ surface as projection maps, which enables the exposure of the structure–function dependencies. Here, we use PST to uncover the “activity pattern” in α-conotoxins — neuroactive peptides that effectively target nicotinic acetylcholine receptors (nAChRs). PST was applied in order to design several variants of the α-conotoxin PnIA, which were synthesized and thoroughly studied. Among the best was PnIA[R9, L10], which exhibits nanomolar affinity for the α7 nAChR, selectivity and a slow wash-out from this target. Importantly, these mutations could hardly be delineated by “standard” structure-based drug design. The proposed combination of PST with a set of experiments proved very efficient for the rational construction of new bioactive molecules. PMID:27841338

  16. Applying Human-performance Models to Designing and Evaluating Nuclear Power Plants: Review Guidance and Technical Basis

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, J.M.

    2009-11-30

    Human performance models (HPMs) are simulations of human behavior with which we can predict human performance. Designers use them to support their human factors engineering (HFE) programs for a wide range of complex systems, including commercial nuclear power plants. Applicants to U.S. Nuclear Regulatory Commission (NRC) can use HPMs for design certifications, operating licenses, and license amendments. In the context of nuclear-plant safety, it is important to assure that HPMs are verified and validated, and their usage is consistent with their intended purpose. Using HPMs improperly may generate misleading or incorrect information, entailing safety concerns. The objective of this research was to develop guidance to support the NRC staff's reviews of an applicant's use of HPMs in an HFE program. The guidance is divided into three topical areas: (1) HPM Verification, (2) HPM Validation, and (3) User Interface Verification. Following this guidance will help ensure the benefits of HPMs are achieved in a technically sound, defensible manner. During the course of developing this guidance, I identified several issues that could not be addressed; they also are discussed.

  17. Taking the stairs instead: The impact of workplace design standards on health promotion strategies

    Directory of Open Access Journals (Sweden)

    Marian Tye

    2013-01-01

    Full Text Available AbstractBackground Comprehensive health promotion in Western Australia has been conducted from the point of views of policy development, promotion, education and service delivery. Much of this recent work has been focused on supporting workplaces – but there has yet to be any real focus on the design of the actual physical workplace environment from a health promotion perspective. Aims This paper is aimed at highlighting the gap in health promotion knowledge by addressing how the disciplines of architecture and health promotion can work together to challenge the regulations that dictate design practice and ultimately bridge that gap for long-term change. The overarching aim is to undertake further evidenced-based research that will inform best practice in the planning and design of workplaces to reduce sedentary behaviour and increase opportunities for physical activity. Method Within this wide objective this paper focuses in particular on the idea of stairs-versus-lift movement strategies within office buildings. By examining building design guidelines from a health promotion perspective we expose a central dichotomy, where health promotion posters say “Take the stairs instead” whereas the language of building design suggests that the lift is best. Results From a design point of view, the National Codes of Construction (NCC, formally known as the Building Codes of Australia (BCA, the essential technical regulation for all building design and construction, primarily addresses the concepts of ‘egress’ and ‘travel distance’ for escape in the event of fire, and building access in terms of universal access. Additionally, The Property Council of Australia’s Guide to Office Building Quality prioritises lift performance criteria along with the quality and experience of lift use as a major grading factor. There is no provision in either set of standards for staircase quality and experience. Conclusion The stairs, despite being promoted

  18. Designing a water calorimeter as primary standard of gamma rays at IPEN/CNEN

    International Nuclear Information System (INIS)

    Cintra, Felipe B. de; Caldas, Linda V.E.

    2013-01-01

    This work aims to describe the present stage and the next steps of the development of a water calorimeter of the Calibration Laboratory of IPEN/CNEN. This calorimeter will be used as a primary standard of gamma ray sources at the laboratory. Between the design and the construction step it will be shown how this model was chosen and how it is modeled virtually with computer simulation. The two main codes used, MCNP and Fluent, to characterize the prototype before its construction are presented. (author)

  19. Basis and Statistical Design of the Passive HIV-1 Antibody Mediated Prevention (AMP) Test-of-Concept Efficacy Trials.

    Science.gov (United States)

    Gilbert, Peter B; Juraska, Michal; deCamp, Allan C; Karuna, Shelly; Edupuganti, Srilatha; Mgodi, Nyaradzo; Donnell, Deborah J; Bentley, Carter; Sista, Nirupama; Andrew, Philip; Isaacs, Abby; Huang, Yunda; Zhang, Lily; Capparelli, Edmund; Kochar, Nidhi; Wang, Jing; Eshleman, Susan H; Mayer, Kenneth H; Magaret, Craig A; Hural, John; Kublin, James G; Gray, Glenda; Montefiori, David C; Gomez, Margarita M; Burns, David N; McElrath, Julie; Ledgerwood, Julie; Graham, Barney S; Mascola, John R; Cohen, Myron; Corey, Lawrence

    2017-01-01

    Anti-HIV-1 broadly neutralizing antibodies (bnAbs) have been developed as potential agents for prevention of HIV-1 infection. The HIV Vaccine Trials Network and the HIV Prevention Trials Network are conducting the Antibody Mediated Prevention (AMP) trials to assess whether, and how, intravenous infusion of the anti-CD4 binding site bnAb, VRC01, prevents HIV-1 infection. These are the first test-of-concept studies to assess HIV-1 bnAb prevention efficacy in humans. The AMP trials are two parallel phase 2b HIV-1 prevention efficacy trials conducted in two cohorts: 2700 HIV-uninfected men and transgender persons who have sex with men in the United States, Peru, Brazil, and Switzerland; and 1500 HIV-uninfected sexually active women in seven countries in sub-Saharan Africa. Participants are randomized 1:1:1 to receive an intravenous infusion of 10 mg/kg VRC01, 30 mg/kg VRC01, or a control preparation every 8 weeks for a total of 10 infusions. Each trial is designed (1) to assess overall prevention efficacy (PE) pooled over the two VRC01 dose groups vs. control and (2) to assess VRC01 dose and laboratory markers as correlates of protection (CoPs) against overall and genotype- and phenotype-specific infection. Each AMP trial is designed to have 90% power to detect PE > 0% if PE is ≥ 60%. The AMP trials are also designed to identify VRC01 properties (i.e., concentration and effector functions) that correlate with protection and to provide insight into mechanistic CoPs. CoPs are assessed using data from breakthrough HIV-1 infections, including genetic sequences and sensitivities to VRC01-mediated neutralization and Fc effector functions. The AMP trials test whether VRC01 can prevent HIV-1 infection in two study populations. If affirmative, they will provide information for estimating the optimal dosage of VRC01 (or subsequent derivatives) and identify threshold levels of neutralization and Fc effector functions associated with high-level protection, setting a benchmark

  20. Providing the Basis for Innovative Improvements in Advanced LWR Reactor Passive Safety Systems Design: An Educational R and D Project

    International Nuclear Information System (INIS)

    Brian G. Williams; Jim C. P. Liou; Hiral Kadakia; Bill Phoenix; Richard R. Schultz

    2007-01-01

    This project characterizes typical two-phase stratified flow conditions in advanced water reactor horizontal pipe sections, following activation of passive cooling systems. It provides (1) a means to educate nuclear engineering students regarding the importance of two-phase stratified flow in passive cooling systems to the safety of advanced reactor systems and (2) describes the experimental apparatus and process to measure key parameters essential to consider when designing passive emergency core cooling flow paths that may encounter this flow regime. Based on data collected, the state of analysis capabilities can be determined regarding stratified flow in advanced reactor systems and the best paths forward can be identified to ensure that the nuclear industry can properly characterize two-phase stratified flow in passive emergency core cooling systems

  1. Produced Water Treatment Using the Switchable Polarity Solvent Forward Osmosis (SPS FO) Desalination Process: Preliminary Engineering Design Basis

    Energy Technology Data Exchange (ETDEWEB)

    Wendt, Daniel; Adhikari, Birendra; Orme, Christopher; Wilson, Aaron

    2016-05-01

    Switchable Polarity Solvent Forward Osmosis (SPS FO) is a semi-permeable membrane-based water treatment technology. INL is currently advancing SPS FO technology such that a prototype unit can be designed and demonstrated for the purification of produced water from oil and gas production operations. The SPS FO prototype unit will used the thermal energy in the produced water as a source of process heat, thereby reducing the external process energy demands. Treatment of the produced water stream will reduce the volume of saline wastewater requiring disposal via injection, an activity that is correlated with undesirable seismic events, as well as generate a purified product water stream with potential beneficial uses. This paper summarizes experimental data that has been collected in support of the SPS FO scale-up effort, and describes how this data will be used in the sizing of SPS FO process equipment. An estimate of produced water treatment costs using the SPS FO process is also provided.

  2. Rational designing of the internal water supply system in reconstructed residential buildings of mass standard series

    Directory of Open Access Journals (Sweden)

    Orlov Evgeny

    2018-01-01

    Full Text Available The issues of water supply system reconstruction in mass series buildings are reviewed with consideration of water- and resource saving. Principal points for location of plumbing cells in apartments, arrangement of water devices and wastewater receivers, selection of pipelines for reconstructed water line are described. Comparative analysis of design variants of inner water line before and following reconstruction are given. It was found that applying the developed system design approaches the head losses in the inner water supply line will be significantly decreased as well as the water mains length will be decreased with material and installation saving. Based on the data the conclusions on necessity to review standard arrangement solutions of water supply systems in the reconstructed buildings were made. Recommendations on water loss reduction in the system by installation of special water saving fittings on water devices and touchless faucets.

  3. The family of standard hydrogen monitoring system computer software design description: Revision 2

    International Nuclear Information System (INIS)

    Bender, R.M.

    1994-01-01

    In March 1990, 23 waste tanks at the Hanford Nuclear Reservation were identified as having the potential for the buildup of gas to a flammable or explosive level. As a result of the potential for hydrogen gas buildup, a project was initiated to design a standard hydrogen monitoring system (SHMS) for use at any waste tank to analyze gas samples for hydrogen content. Since it was originally deployed three years ago, two variations of the original system have been developed: the SHMS-B and SHMS-C. All three are currently in operation at the tank farms and will be discussed in this document. To avoid confusion in this document, when a feature is common to all three of the SHMS variants, it will be referred to as ''The family of SHMS.'' When it is specific to only one or two, they will be identified. The purpose of this computer software design document is to provide the following: the computer software requirements specification that documents the essential requirements of the computer software and its external interfaces; the computer software design description; the computer software user documentation for using and maintaining the computer software and any dedicated hardware; and the requirements for computer software design verification and validation

  4. Conceptual design of a municipal energy and environmental system as an efficient basis for advanced energy planning

    International Nuclear Information System (INIS)

    Kostevšek, Anja; Petek, Janez; Čuček, Lidija; Pivec, Aleksandra

    2013-01-01

    Effectively implementing various energy and environmental policies contributes to the acceleration of energy performance, a reduction in negative environmental impacts, and increased deployment of renewable resources. The MEEMS (municipal energy and environmental management system) performs the almost inconceivable role of accomplishing prerequisite targets at the national level and, consequently, the European and World levels also. Therefore, a proper infrastructure for MEEMS needs to be effectively applied in order to implement policy initiatives. A novel organisational framework of MEEMS is proposed and is constituted upon three pillars: integration of the municipal metabolism approach, the KBS (knowledge-based system), and the MTIS (municipal technology innovation system). By properly addressing the dynamics of the MEES (municipal energy and environmental system), and the new conceptual organisation of MEEMS, a need for the inclusion of innovative elements can be defined regarding support mechanisms. Integration of the end-user approach defines the fundamental orientation of modern MEEMS. This new concept paves a pathway towards an intelligent energy and environmental system. This paper describes an implementation of the new conceptual design of MEEMS within the urban municipality energy system of Ptuj, Slovenia. - Highlights: • Combination of energy and environmental management system (MEEMS) within municipalities is proposed. • Novel MEEMS structure to accomplish more effective functioning of the system. • Accelerated energy policy implementation process is enabled with proposed MEEMS. • Key ingredients to transform present energy systems to more innovative ones are discussed

  5. Design basis knowledge management for the newcomer countries. Relying on the owner/operator as a knowledgeable customer

    International Nuclear Information System (INIS)

    Lepouze, Benoît

    2013-01-01

    Becoming a knowledgeable customer is the first step to manage knowledge: • Vendors, consulting firms, TSOs can assist the future operator but it will remain the sole owner of the decisions; • Future owner operator has to become a knowledgeable customer: • Know what to ask for, • Know how to ask for it, • Know how to check if it got what it asked. • Where should knowledge management belong (management?, HRD?, procurement?) and is it important? What it means for DBKM ? (example): • The owner/operator (the licensee) is responsible in front of the safety agency: it should answer its questions at every stage of the program; • It will often turn back to its vendor/suppliers especially for detailed design questions; • But that means it has to know what to ask for and to check the result before talking to the regulator; • That also means it has to make sure knowledge is managed throughout the life of the program

  6. Theoretical basis, principles of design, and experimental study of the prototype of perfect AFCS transmitting signals without coding

    Science.gov (United States)

    Platonov, A.; Zaitsev, Ie.; Opalski, L. J.

    2017-08-01

    The paper presents an overview of design methodology and results of experiments with a Prototype of highly efficient optimal adaptive feedback communication systems (AFCS), transmitting low frequency analog signals without coding. The paper emphasizes the role of the forward transmitter saturation as the factor that blocked implementation of theoretical results of pioneer (1960-1970s) and later research on FCS. Deepened analysis of the role of statistical fitting condition in adequate formulation and solution of AFCS optimization task is given. Solution of the task - optimal transmission/reception algorithms is presented in the form useful for elaboration of the hardware/software Prototype. A notable particularity of the Prototype is absence of the encoding/decoding units, whose functions are realized by the adaptive pulse amplitude modulator (PAM) of the forward transmitter (FT) and estimating/controlling algorithm in the receiver of base station (BS). Experiments confirm that the Prototype transmits signals from FT to BS "perfectly": with the bit rate equal to the capacity of the system, and with limit energy [J/bit] and spectral [bps/Hz] efficiency. Another, not less important and confirmed experimentally, particularity of AFCS is its capability to adjust parameters of FT and BS to the characteristics of scenario of application and maintain the ideal regime of transmission including spectralenergy efficiency. AFCS adjustment can be made using BS estimates of mean square error (MSE). The concluding part of the paper contains discussion of the presented results, stressing capability of AFCS to solve problems appearing in development of dense wireless networks.

  7. Blinded sample size re-estimation in three-arm trials with 'gold standard' design.

    Science.gov (United States)

    Mütze, Tobias; Friede, Tim

    2017-10-15

    In this article, we study blinded sample size re-estimation in the 'gold standard' design with internal pilot study for normally distributed outcomes. The 'gold standard' design is a three-arm clinical trial design that includes an active and a placebo control in addition to an experimental treatment. We focus on the absolute margin approach to hypothesis testing in three-arm trials at which the non-inferiority of the experimental treatment and the assay sensitivity are assessed by pairwise comparisons. We compare several blinded sample size re-estimation procedures in a simulation study assessing operating characteristics including power and type I error. We find that sample size re-estimation based on the popular one-sample variance estimator results in overpowered trials. Moreover, sample size re-estimation based on unbiased variance estimators such as the Xing-Ganju variance estimator results in underpowered trials, as it is expected because an overestimation of the variance and thus the sample size is in general required for the re-estimation procedure to eventually meet the target power. To overcome this problem, we propose an inflation factor for the sample size re-estimation with the Xing-Ganju variance estimator and show that this approach results in adequately powered trials. Because of favorable features of the Xing-Ganju variance estimator such as unbiasedness and a distribution independent of the group means, the inflation factor does not depend on the nuisance parameter and, therefore, can be calculated prior to a trial. Moreover, we prove that the sample size re-estimation based on the Xing-Ganju variance estimator does not bias the effect estimate. Copyright © 2017 John Wiley & Sons, Ltd. Copyright © 2017 John Wiley & Sons, Ltd.

  8. Designing an artificial neural network using radial basis function to model exergetic efficiency of nanofluids in mini double pipe heat exchanger

    Science.gov (United States)

    Ghasemi, Nahid; Aghayari, Reza; Maddah, Heydar

    2017-12-01

    The present study aims at predicting and optimizing exergetic efficiency of TiO2-Al2O3/water nanofluid at different Reynolds numbers, volume fractions and twisted ratios using Artificial Neural Networks (ANN) and experimental data. Central Composite Design (CCD) and cascade Radial Basis Function (RBF) were used to display the significant levels of the analyzed factors on the exergetic efficiency. The size of TiO2-Al2O3/water nanocomposite was 20-70 nm. The parameters of ANN model were adapted by a training algorithm of radial basis function (RBF) with a wide range of experimental data set. Total mean square error and correlation coefficient were used to evaluate the results which the best result was obtained from double layer perceptron neural network with 30 neurons in which total Mean Square Error(MSE) and correlation coefficient (R2) were equal to 0.002 and 0.999, respectively. This indicated successful prediction of the network. Moreover, the proposed equation for predicting exergetic efficiency was extremely successful. According to the optimal curves, the optimum designing parameters of double pipe heat exchanger with inner twisted tape and nanofluid under the constrains of exergetic efficiency 0.937 are found to be Reynolds number 2500, twisted ratio 2.5 and volume fraction(v/v%) 0.05.

  9. ACSYNT - A standards-based system for parametric, computer aided conceptual design of aircraft

    Science.gov (United States)

    Jayaram, S.; Myklebust, A.; Gelhausen, P.

    1992-01-01

    A group of eight US aerospace companies together with several NASA and NAVY centers, led by NASA Ames Systems Analysis Branch, and Virginia Tech's CAD Laboratory agreed, through the assistance of Americal Technology Initiative, in 1990 to form the ACSYNT (Aircraft Synthesis) Institute. The Institute is supported by a Joint Sponsored Research Agreement to continue the research and development in computer aided conceptual design of aircraft initiated by NASA Ames Research Center and Virginia Tech's CAD Laboratory. The result of this collaboration, a feature-based, parametric computer aided aircraft conceptual design code called ACSYNT, is described. The code is based on analysis routines begun at NASA Ames in the early 1970's. ACSYNT's CAD system is based entirely on the ISO standard Programmer's Hierarchical Interactive Graphics System and is graphics-device independent. The code includes a highly interactive graphical user interface, automatically generated Hermite and B-Spline surface models, and shaded image displays. Numerous features to enhance aircraft conceptual design are described.

  10. Developing a Korean standard brain atlas on the basis of statistical and probabilistic approach and visualization tool for functional image analysis

    International Nuclear Information System (INIS)

    Koo, B. B.; Lee, J. M.; Kim, J. S.; Kim, I. Y.; Kim, S. I.; Lee, J. S.; Lee, D. S.; Kwon, J. S.; Kim, J. J.

    2003-01-01

    The probabilistic anatomical maps are used to localize the functional neuro-images and morphological variability. The quantitative indicator is very important to inquire the anatomical position of an activated region because functional image data has the low-resolution nature and no inherent anatomical information. Although previously developed MNI probabilistic anatomical map was enough to localize the data, it was not suitable for the Korean brains because of the morphological difference between Occidental and Oriental. In this study, we develop a probabilistic anatomical map for Korean normal brain. Normal 75 brains of T1-weighted spoiled gradient echo magnetic resonance images were acquired on a 1.5-T GESIGNA scanner. Then, a standard brain is selected in the group through a clinician searches a brain of the average property in the Talairach coordinate system. With the standard brain, an anatomist delineates 89 regions of interest (ROI) parcellating cortical and subcortical areas. The parcellated ROIs of the standard are warped and overlapped into each brain by maximizing intensity similarity. And every brain is automatically labeled with the registered ROIs. Each of the same-labeled region is linearly normalize to the standard brain, and the occurrence of each region is counted. Finally, 89 probabilistic ROI volumes are generated. This paper presents a probabilistic anatomical map for localizing the functional and structural analysis of Korean normal brain. In the future, we'll develop the group specific probabilistic anatomical maps of OCD and schizophrenia disease

  11. SMI Compatible Simulation Scheduler Design for Reuse of Model Complying with SMP Standard

    Directory of Open Access Journals (Sweden)

    Cheol-Hea Koo

    2010-12-01

    Full Text Available Software reusability is one of key factors which impacts cost and schedule on a software development project. It is very crucial also in satellite simulator development since there are many commercial simulator models related to satellite and dynamics. If these models can be used in another simulator platform, great deal of confidence and cost/schedule reduction would be achieved. Simulation model portability (SMP is maintained by European Space Agency and many models compatible with SMP/simulation model interface (SMI are available. Korea Aerospace Research Institute (KARI is developing hardware abstraction layer (HAL supported satellite simulator to verify on-board software of satellite. From above reasons, KARI wants to port these SMI compatible models to the HAL supported satellite simulator. To port these SMI compatible models to the HAL supported satellite simulator, simulation scheduler is preliminary designed according to the SMI standard.

  12. SSTL I/O Standard Based Green Communication Using Fibonacci Generator Design on Ultra Scale FPGA

    DEFF Research Database (Denmark)

    Nagah, Sumi; Kaur, Ravinder; Pandey, Bishwajeet

    2015-01-01

    In this paper six different available classes of Stub-Series Terminated Logic (SSTL) Input/output standard is used for the design of Green Fibonacci generator on 40nm FGPA. That green Fibonacci Generator is used to generate key for Wi-Fi Protected Access in order to make energy efficient...... comparison it is observed that, SSTL15 is the most energy efficient and S18IIDis the worst energy efficient. Then on comparison of SSTL15 with SSTL18_II_DCI (S18IID), it is found that, when Fibonacci generator is operated at different frequencies like 1GHz, 10GHz, 100GHz and 1THz, the reduction in I/O power...

  13. Environmental Monitoring, Water Quality - MO 2009 Water Quality Standards - Table G Lake Classifications and Use Designations (SHP)

    Data.gov (United States)

    NSGIC State | GIS Inventory — This data set contains Missouri Water Quality Standards (WQS) lake classifications and use designations described in the Missouri Code of State Regulations (CSR), 10...

  14. A standard reference for chamber testing of material VOC emissions: Design principle and performance

    Science.gov (United States)

    Wei, Wenjuan; Zhang, Yinping; Xiong, Jianyin; Li, Mu

    2012-02-01

    Environmental chambers are widely used to test formaldehyde and other volatile organic compound (VOC) emissions from indoor materials and furniture. However, there is a lack of a proven method to assess the precision of the test results of the chamber system. In this paper, we describe a new standard reference, LIFE (liquid-inner tube diffusion-film-emission), to address this problem. This reference has the following salient features: (1) Constant emission rate, with less than 3.0% change with an ambient airflow speed (>0.014 m/s) at furniture emission range (0.1-1.0 mg/m 3 in a 30 m 3 chamber with air change rate of 1/h) under standard chamber test conditions as specified by ISO 16000-9 (23 °C, 50% RH); (2) Long duration of emissions, on the order of 1000 h; (3) Easy to store, apply and maintain. The design principle and criteria of the LIFE reference are presented. An analytical model and dimensionless analysis were applied to optimize the factors influencing the emission rate, and experiments were conducted to validate the analytical results. In addition, the equivalent emission parameters of the reference, i.e., the initial emittable concentration, the diffusion coefficient and the partition coefficient, were determined through a three-parameter optimizing regression. This can then be used to check the reliability of a chamber method for testing these three parameters. The developed standard reference should prove useful for calibrating chamber systems for indoor material/furniture VOC emissions tests.

  15. Standardization of Experimental Design for Crop Cultivation in Life Support Systems for Space Exploration

    Science.gov (United States)

    Wolff, Silje Aase; Coelho, Liz Helena; Karoliussen, Irene; Kittang Jost, Ann-Iren

    Due to logistical challenges, long-term human space exploration missions require a life support system capable of regenerating all the essentials for survival. Higher plants can be utilized to provide a continuous supply of fresh food, fresh air, and clean water for humans. The extensive work performed have shown that higher plants are able to adapt to space conditions in low Earth orbit, at least from one generation from seed to seed. Since the hardware has turned out to be of great importance for the results in microgravity research, full environmental monitoring and control must be the standard for future experiments. Selecting a few model plants, including crop plants for life support, would further increase the comparability between studies. The European Space Agency (ESA) has developed the Micro-Ecological Life Support System Alternative (MELiSSA) program to develop a closed regenerative life support system, based on micro-organisms and higher plants, with continuous recycling of resources. In the present study, recommended standardization of the experimental design for future scientific work assessing the effects of graded gravity on plant metabolism will be presented. This includes the environmental conditions required for cultivation of the selected MEliSSA species (wheat, bread wheat, soybean and potato), as well as guidelines for sowing, plant handling and analysis. Keywords: microgravity; magnetic field; radiation; MELiSSA; Moon; Mars.

  16. Los Alamos National Laboratory new generation standard nuclear material storage container - the SAVY4000 design

    International Nuclear Information System (INIS)

    Stone, Timothy Amos

    2010-01-01

    Incidents involving release of nuclear materials stored in containers of convenience such as food pack cans, slip lid taped cans, paint cans, etc. has resulted in defense board concerns over the lack of prescriptive performance requirements for interim storage of nuclear materials. Los Alamos National Laboratory (LANL) has shared in these incidents and in response proactively moved into developing a performance based standard involving storage of nuclear material (RD003). This RD003 requirements document has sense been updated to reflect requirements as identified with recently issued DOE M 441.1-1 'Nuclear Material Packaging Manual'. The new packaging manual was issued at the encouragement of the Defense Nuclear Facilities Safety Board with a clear directive for protecting the worker from exposure due to loss of containment of stored materials. The Manual specifies a detailed and all inclusive approach to achieve a high level of protection; from package design and performance requirements, design life determinations of limited life components, authorized contents evaluations, and surveillance/maintenance to ensure in use package integrity over time. Materials in scope involve those stored outside an approved engineered-contamination barrier that would result in a worker exposure of in excess of 5 rem Committed Effective Does Equivalent (CEDE). Key aspects of meeting the challenge as developed around the SAVY-3000 vented storage container design will be discussed. Design performance and acceptance criteria against the manual, bounding conditions as established that the user must ensure are met to authorize contents in the package (based upon the activity of heat-source plutonium (90% Pu-238) oxide, which bounds the requirements for weapons-grade plutonium oxide), interface as a safety class system within the facility under the LANL plutonium facility DSA, design life determinations for limited life components, and a sense of design specific surveillance program

  17. 41 CFR 102-76.30 - What seismic safety standards must Federal agencies follow in the design and construction of...

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false What seismic safety... § 102-76.30 What seismic safety standards must Federal agencies follow in the design and construction of Federal facilities? Federal agencies must follow the seismic safety standards identified in § 102-80.45 of...

  18. Learning-Goals-Driven Design Model: Developing Curriculum Materials that Align with National Standards and Incorporate Project-Based Pedagogy

    Science.gov (United States)

    Krajcik, Joseph; McNeill, Katherine L.; Reiser, Brian J.

    2008-01-01

    Reform efforts in science education emphasize the importance of rigorous treatment of science standards and use of innovative pedagogical approaches to make science more meaningful and successful. In this paper, we present a learning-goals-driven design model for developing curriculum materials, which combines national standards and a…

  19. Design and test of the microwave cavity in an optically-pumped Rubidium beam frequency standard

    Science.gov (United States)

    Liu, Chang; Wang, Yan-Hui

    2015-01-01

    We are developing a compact rubidium atomic beam frequency standard with optical pumping and detection. The cavity for microwave interrogation is an important part of the clock. The cavity in our design is a Ramsey-type, E-bend one, which is the same as the conventional method in most cesium beam clocks. Requirements for the design are proposed based on the frequency shift associated with the cavity. The basic structure of the cavity is given by theoretical analysis and detailed dimensions are determined by means of electromagnetic field simulation with the help of commercial software. The cavity is manufactured and fabricated successfully. The preliminary test result of the cavity is given, which is in good agreement with the simulation. The resonant frequency is 6.835 GHz, equal to the clock transition frequency of 87Rb, and the loaded quality factor is 500. These values are adjustable with posts outside the cavity. Estimations on the Ramsey line width and several frequency shifts are made. Project supported by the National Natural Science Foundation of China (Grant No. 11174015).

  20. Analysis and design of 40 m high steel chimney according to Eurocode and SRPS standards

    Directory of Open Access Journals (Sweden)

    Bešević Miroslav T.

    2015-01-01

    Full Text Available This paper presents structural analysis according to Eurocode and SRPS standards. Analysed construction is 40 m high steel chimney, made of 33 m long upper circular cross-section segment of constant diameter D=1834 mm and bottom variable circular cross-section segment of D=2234 mm on the foundation level. Wind loads are dominant loads for this kind of structures. In analyzing workload basic wind speed is thoroughly treated according to SRPS U.C7.110, and respectively wind speed is treated according to Eurocode 1 for the location of Prahovo. Design of model for the effects of its own weight, a constant load and wind load was conducted according to the second order theory for pre-formed load combinations. The load combinations do not contain partial load safety factors. Design of chimney shaft segments are carried out for different ticknes by height of the pillar, for bearing capacity of cross-section, buckling due normal stress, buckling due tangential stress and buckling control is carried out due shear stress.

  1. STRATEGY FOR IMPROVEMENT OF SAFETY AND EFFICIENCY OF COMPUTER-AIDED DESIGN ANALYSIS OF CIVIL ENGINEERING STRUCTURES ON THE BASIS OF THE SYSTEM APPROACH

    Directory of Open Access Journals (Sweden)

    Zaikin Vladimir Genrikhovich

    2012-12-01

    Full Text Available The authors highlight three problems of the age of information technologies and proposes the strategy for their resolution in relation to the computer-aided design of civil engineering structures. The authors express their concerns in respect of globalization of software programmes designated for the analysis of civil engineering structures and employed outside of Russia. The problem of the poor quality of the input data has reached Russia. Lately, the rate of accidents of buildings and structures has been growing not only in Russia. Control over efficiency of design projects is hardly performed. This attitude should be changed. Development and introduction of CAD along with the application the efficient methods of projection of behaviour of building structures are in demand. Computer-aided calculations have the function of a logical nucleus, and they need proper control. The system approach to computer-aided calculations and technologies designated for the projection of accidents is formulated by the authors. Two tasks of the system approach and fundamentals of the strategy for its implementation are formulated. The study of cases of negative results of computer-aided design of engineering structures was performed and multi-component design patterns were developed. Conclusions concerning the results of researches aimed at regular and wide-scale implementation of the strategy fundamentals are formulated. Organizational and innovative actions concerning the projected behaviour of civil engineering structures proposed in the strategy are to facilitate: safety and reliability improvement of buildings and structures; saving of building materials and resources; improvement of labour efficiency of designers; modernization and improvement of accuracy of projected behaviour of buildings and building standards; closer ties between civil and building engineering researchers and construction companies; development of competitive environment to boost

  2. Information and communication technologies for operating of smart distribution grids based on the German standardization roadmap; Informations- und Kommunikationstechnologien zur Betriebsfuehrung smarter Verteilungsnetze auf Basis der Deutschen Normungsroadmap

    Energy Technology Data Exchange (ETDEWEB)

    Brunner, Christoph [IT4Power, Zug (Switzerland); Buchholz, Bernd Michael [NTB Technoservice, Pyrbaum (Germany); Hampel, Herman [iAD GmbH, Grosshabersdorf (Germany); Naumann, A. [Magdeburg Univ. (Germany)

    2012-07-01

    The current challenges of the distribution networks are caused by a growing volume of distributed energy in-feed and new types of load. They require the introduction of information and communication technologies (ICT) down to the low voltage level. Innovative monitoring and control tasks are developed in the framework of the European lighthouse project ''Web2Energy'' (W2E) and performed in the practice of the 20/0.4 kV network of the HSE AG in Darmstadt. The overview of the realized functions is given and the related information exchange between the control centre and the distributed plants is considered. The project applies the standards IEC 61850 for data communication and IEC 61968/70 for the data management (CIM - Common Information Model) in the control center (CC). The client - server architecture of the developed communication system is considered in detail. The project related W2E CC serves the aspects of smart distribution also in the context with market activities. Data acquisition and control of the 20/0.4 kV terminals and the various power plants are executed by a mini remote terminal unit. The W2E RTU offers a 100 MBd Ethernet interface providing the IEC 61850 protocol for the access to the communication system. The required application specific extensions of the standards are discussed and the first experiences for application in the practice are demonstrated. (orig.)

  3. From the Analysis of Work-Processes to Designing Competence-Based Occupational Standards and Vocational Curricula

    Science.gov (United States)

    Tutlys, Vidmantas; Spöttl, Georg

    2017-01-01

    Purpose: This paper aims to explore methodological and institutional challenges on application of the work-process analysis approach in the design and development of competence-based occupational standards for Lithuania. Design/methodology/approach: The theoretical analysis is based on the review of scientific literature and the analysis of…

  4. 10 CFR Appendix N to Part 50 - Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate...

    Science.gov (United States)

    2010-01-01

    ... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FACILITIES Pt. 50, App.N Appendix N to Part 50—Standardization of Nuclear Power Plant Designs: Permits To..., apply to construction permits and operating licenses subject to this appendix N. 2. Applications for...

  5. Revision of standard molar enthalpies of formation of glycine and L-alanine in the gaseous phase on the basis of theoretical calculations

    International Nuclear Information System (INIS)

    Dorofeeva, Olga V.; Ryzhova, Oxana N.

    2009-01-01

    The standard molar enthalpies of formation of urea, glycine, and L-alanine in the gaseous phase at 298.15 K were calculated by the high-level Gaussian-3X method. The agreement with the available experimental data is very good for urea and glycine and, thus, supports the high accuracy of calculated values. A significant discrepancy between theoretical and experimental enthalpy of formation values for L-alanine provides a reason to reconsider the experimental data previously used to derive the standard molar enthalpy of formation of L-alanine in the gaseous phase at 298.15 K. To obtain a more reliable value of enthalpy of sublimation at 298.15 K, the heat capacity values of gaseous L-alanine were calculated by standard statistical thermodynamics formulae using molecular parameters determined from B3LYP/cc-pVTZ calculations. With the obtained value of C p,m 0 (L-alanine, g, 298.15 K) = 112.6 ± 4.0 J . K -1 . mol -1 the original published experimental values of enthalpy of sublimation of L-alanine were readjusted to the reference temperature: Δ cr g H m (L-alanine, 298.15 K) = 135.2 ± 2.0 kJ . mol -1 . This value, together with the experimental enthalpy of formation of solid L-alanine, Δ f H m 0 (L-alanine, cr, 298.15 K) = -560.0 ± 1.0 kJ . mol -1 [S.N. Ngauv, R. Sabbah, M. Laffitte, Thermochim. Acta 20 (1977) 371-380; I. Contineanu, D.I. Marchidan, Rev. Roum. Chim. 29 (1984) 43-48], gives a new value for the enthalpy of formation of L-alanine in the gaseous phase, Δ f H m 0 (L-alanine, g, 298.15 K) = -424.8 ± 2.0 kJ . mol -1 , which is in good agreement with our theoretical G3X result, -427.6 ± 4.0 kJ . mol -1 . The same procedure for glycine allowed us to improve the literature value of the enthalpy of formation for this compound, Δ f H m 0 (glycine, g, 298.15 K) = -393.7 ± 1.5 kJ . mol -1 . As a result a set of self-consistent thermochemical data for glycine and L-alanine is proposed

  6. Comparison of the General Electric BWR/6 standard plant design to the IAEA NUSS codes and guides

    International Nuclear Information System (INIS)

    D'Ardenne, W.H.; Sherwood, G.G.

    1985-01-01

    The General Electric BWR/6 Mark III standard plant design meets or exceeds current requirements of published International Atomic Energy Agency (IAEA) Nuclear Safety Standards (NUSS) codes and guides. This conclusion is based on a review of the NUSS codes and guides by General Electric and by the co-ordinated US review of the NUSS codes and guides during their development. General Electric compared the published IAEA NUSS codes and guides with the General Electric design. The applicability of each code and guide to the BWR/6 Mark III standard plant design was determined. Each code or guide was reviewed by a General Electric engineer knowledgeable about the structures, systems and components addressed and the technical area covered by that code or guide. The results of this review show that the BWR/6 Mark III standard plant design meets or exceeds the applicable requirements of the published IAEA NUSS codes and guides. The co-ordinated US review of the IAEA NUSS codes and guides corroborates the General Electric review. In the co-ordinated US review, the USNRC and US industry organizations (including General Electric) review the NUSS codes and guides during their development. This review ensures that the NUSS codes and guides are consistent with the current US government regulations, guidance and regulatory practices, US voluntary industry codes and standards, and accepted US industry design, construction and operational practices. If any inconsistencies are identified, comments are submitted to the IAEA by the USNRC. All US concerns submitted to the IAEA have been resolved. General Electric design reviews and the Final Design Approval (FDA) issued by the USNRC have verified that the General Electric BWR/6 Mark III standard plant design meets or exceeds the current US requirements, guidance and practices. Since these requirements, guidance and practices meet or exceed those of the NUSS codes and guides, so does the General Electric design. (author)

  7. Development of standard methods for activity measurement of natural radionuclides in waterworks as basis for dose and risk assessment—First results of an Austrian study

    International Nuclear Information System (INIS)

    Stietka, M.; Baumgartner, A.; Seidel, C.; Maringer, F.J.

    2013-01-01

    A comprehensive study with the aim to evaluate the risks due to radiation exposure for workers in water supply is conducted in 21 Austrian waterworks. The development of standard methods for the assessment of occupational exposure of water work staff is a part of this study. Preliminary results of this study show a wide range of Rn-222 activity concentration in waterworks with values from (28±10) Bq/m 3 to (38,000±4000) Bq/m 3 . Also seasonal variations of the Rn-222 activity concentration could be observed. - Highlights: • In this study operational exposure of water work staff was evaluated. • The Rn-222 concentration in indoor air in waterworks was measured for 1 year. • Results show a wide range of Rn-222 activity concentration in waterworks. • Seasonal variations of the Rn-222 activity concentration could be observed

  8. Design and verification of the shielding around the new Neutron Standards Laboratory (LPN) at CIEMAT.

    Science.gov (United States)

    Méndez-Villafañe, R; Guerrero, J E; Embid, M; Fernández, R; Grandio, R; Pérez-Cejuela, P; Márquez, J L; Alvarez, F; Ortego, P

    2014-10-01

    The construction of the new Neutron Standards Laboratory at CIEMAT (Laboratorio de Patrones Neutrónicos) has been finalised and is ready to provide service. The facility is an ∼8 m×8 m×8 m irradiation vault, following the International Organization for Standardization 8529 recommendations. It relies on several neutron sources: a 5-GBq (5.8× 10(8) s(-1)) (252)Cf source and two (241)Am-Be neutron sources (185 and 11.1 GBq). The irradiation point is located 4 m over the ground level and in the geometrical centre of the room. Each neutron source can be moved remotely from its storage position inside a water pool to the irradiation point. Prior to this, an important task to design the neutron shielding and to choose the most appropriate materials has been developed by the Radiological Security Unit and the Ionizing Radiations Metrology Laboratory. MCNPX was chosen to simulate the irradiation facility. With this information the walls were built with a thickness of 125 cm. Special attention was put on the weak points (main door, air conditioning system, etc.) so that the ambient dose outside the facility was below the regulatory limits. Finally, the Radiation Protection Unit carried out a set of measurements in specific points around the installation with an LB6411 neutron monitor and a Reuter-Stokes high-pressure ion chamber to verify experimentally the results of the simulation. © The Author 2014. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  9. Design standards for experimental and field studies to evaluate diagnostic accuracy of tests for infectious diseases in aquatic animals.

    Science.gov (United States)

    Laurin, E; Thakur, K K; Gardner, I A; Hick, P; Moody, N J G; Crane, M S J; Ernst, I

    2018-03-15

    Design and reporting quality of diagnostic accuracy studies (DAS) are important metrics for assessing utility of tests used in animal and human health. Following standards for designing DAS will assist in appropriate test selection for specific testing purposes and minimize the risk of reporting biased sensitivity and specificity estimates. To examine the benefits of recommending standards, design information from published DAS literature was assessed for 10 finfish, seven mollusc, nine crustacean and two amphibian diseases listed in the 2017 OIE Manual of Diagnostic Tests for Aquatic Animals. Of the 56 DAS identified, 41 were based on field testing, eight on experimental challenge studies and seven on both. Also, we adapted human and terrestrial-animal standards and guidelines for DAS structure for use in aquatic animal diagnostic research. Through this process, we identified and addressed important metrics for consideration at the design phase: study purpose, targeted disease state, selection of appropriate samples and specimens, laboratory analytical methods, statistical methods and data interpretation. These recommended design standards for DAS are presented as a checklist including risk-of-failure points and actions to mitigate bias at each critical step. Adherence to standards when designing DAS will also facilitate future systematic review and meta-analyses of DAS research literature. © 2018 John Wiley & Sons Ltd.

  10. Comparison between technical requirements in different standards on synthesis of design ground motion history for nuclear power plants

    International Nuclear Information System (INIS)

    Li Zhongcheng; Tianjin Univ., Tianjin; Zhao Fengxin

    2006-01-01

    The main technical requirements in several domestic and American Standards, Codes and Guides involved in the seismic analysis and design activities of nuclear power plants (NPPs) in China are construed in detail . Based on better understanding of the technical backgrounds and resultant requirements on the synthesis of design ground motion history for NPPs, some discussions and viewpoints in application are conducted together with the engineering in practice. Some conclusions can be provided for reference to conduct the seismic safety evaluation, seismic analysis and design of NPPs. And the suggestions in this paper can be employed in the revision and refinement of the relevant Standards, Codes and Guides in China. (authors)

  11. Designing Innovative Lessons Plans to Support the Next Generation Science Standards (NGSS)

    Science.gov (United States)

    Passow, M. J.

    2013-12-01

    The Next Generation Science Standards (NGSS) issued earlier in 2013 provide the opportunity to enhance pre-college curricula through a new focus on the ';Big Ideas' in Science, more attention to reading and writing skills needed for college and career readiness, and incorporation of engineering and technology. We introduce a set of lesson plans about scientific ocean drilling which can serve as a exemplars for developing curricula to meet NGSS approaches. Designed for middle and high school students, these can also be utilized in undergraduate courses. Development of these lessons was supported through a grant from the Deep Earth Academy of the Consortium for Ocean Leadership. They will be disseminated through websites of the Deep Earth Academy (http://www.oceanleadership.org/education/deep-earth-academy/) and Earth2Class Workshops for Teachers (http://www.earth2class.org), as well as through workshops at science education conferences sponsored by the National Earth Science Teachers Association (www.nestanet.org) and other organizations. Topics include 'Downhole Logging,' 'Age of the Ocean Floors,' 'Tales of the Resolution,' and 'Continental Shelf Sediments and Climate Change Patterns.' 'Downhole Logging' focuses on the engineering and technology utilized to obtain more information about sediments and rocks cored by the JOIDES Resolution scientific drilling vessel. 'Age of the Ocean Floor' incorporates the GeoMap App visualization tools (http://www.geomapapp.org/) to compare sea bottom materials in various parts of the world. 'Tales of the Resolution' is a series of ';graphic novels' created to describe the scientific discoveries, refitting of the JOIDES Resolution, and variety of careers available in the marine sciences (http://www.ldeo.columbia.edu/BRG/outreach/media/tales/). The fourth lesson focuses on discoveries made during Integrated Ocean Drilling Program Expedition 313, which investigated patterns in the sediments beneath the continental shelf off New

  12. [An investigation of the application of hygienic standards for the design of industrial enterprises (GBZ 1-2010)].

    Science.gov (United States)

    Lu, Y; Zhang, M

    2016-08-20

    Objective: To study the applicability, the high frequency used content, the feasibility, and issues needed to be solved of the standard of GBZ 1-2010, aiming to provide technical evidence for the revision of GBZ1. Methods: In the study, the data were collected by referring to the literature database and the questionnaire from June 2013 to June 2015. There were 2 surveys carried out in the study, with methods including questionnaire survey and specific interview. The investigation methods include the paper version of the questionnaire by mail, the electronic version of the questionnaire by e-mail, and the online survey. And 111 questionnaires were collected. Results: In total, the applicability survey (the first survey) received 156 suggestions covering 76 items from 23 facilities, and 13 key technical issues were summarized to be solved as priorities. In the application survey (the second survey) , the leading three jobs using GBZ 1-2010 were the occupational hazards evaluation for constructive project (82.0%) , lecturing/training (65.8%) , occupational hazards monitoring (64.9%) , respectively. The high frequency used contents of GBZ 1-2010 were the sixth part "the basic hygienic requirements for workplace" (90.1%) , the fifth part "site selection, overall layout and workshop design" (87.4%) , the seventh part "the basic hygienic requirements for welfare room" (85.6%) , respectively. In the results of feasibility, scores of the fourth part "the general rules" , the fifth part "site selection, overall layout and workshop design" , the sixth part "the basic hygienic requirements for workplace" , the seventh part "the basic hygienic requirements for welfare room" , the eighth "emergency rescue" , annex A "the correct use instructions" , annex B "buffer zone standards for industrial enterprises" were 2.6, 3.1, 3.5, 3.8, 3.2, 3.3, 2.6, respectively. Among 111 questionnaires, the parts needed to be modified as priories were the fifth part "site selection, overall layout

  13. Antarctica's Princess Elisabeth research station setting new standards in renewable energy design

    International Nuclear Information System (INIS)

    Anon.

    2009-01-01

    The first zero emission research platform that was recently inaugurated in Antarctica. The Princess Elisabeth research station, which is operated by the International Polar Foundation (IPF), is the only polar base to operate entirely on renewable energy. It was commissioned by the Belgian government to better understand the mechanism of climate change. The research station sets new standards in advanced design methodology. It demonstrates that the techniques and technology being used in extreme conditions could be a model for both commercial and domestic applications in more temperate areas around the world. Renewable energy sources are used along with passive housing techniques, optimization of energy consumption and best waste management practices. Solar energy provides about 30 per cent of the station's electricity supply through PV solar panels. Solar energy also provides hot water through solar thermal panels. Newly developed vacuum tube thermal panels reduce conducted heat loss and convert 70 per cent of the solar energy into useable thermal energy. The station's water treatment unit will recycle 100 per cent of its water and reuse 75 per cent of it using technology developed for future spaceships. After purification and neutralization, the recycled water is allocated to a second use for showers, toilets and washing machines. The research station uses passive building techniques. Its insulation, shape, orientation and window disposition allow comfortable ambient temperature to be maintained inside the building with little energy input. Wind power is responsible for about 70 per cent of the station's total electricity requirement. This is provided by 9 wind turbines that are designed to withstand the harsh conditions in Antarctica. This article also described the advanced power management system at the station, with particular reference to its SCADA human interface, the three-phase AC, the battery grid, evacuation of surplus energy and wiring system. 4 figs

  14. Designing a Distributed Space Systems Simulation in Accordance with the Simulation Interoperability Standards Organization (SISO)

    Science.gov (United States)

    Cowen, Benjamin

    2011-01-01

    Simulations are essential for engineering design. These virtual realities provide characteristic data to scientists and engineers in order to understand the details and complications of the desired mission. A standard development simulation package known as Trick is used in developing a source code to model a component (federate in HLA terms). The runtime executive is integrated into an HLA based distributed simulation. TrickHLA is used to extend a Trick simulation for a federation execution, develop a source code for communication between federates, as well as foster data input and output. The project incorporates international cooperation along with team collaboration. Interactions among federates occur throughout the simulation, thereby relying on simulation interoperability. Communication through the semester went on between participants to figure out how to create this data exchange. The NASA intern team is designing a Lunar Rover federate and a Lunar Shuttle federate. The Lunar Rover federate supports transportation across the lunar surface and is essential for fostering interactions with other federates on the lunar surface (Lunar Shuttle, Lunar Base Supply Depot and Mobile ISRU Plant) as well as transporting materials to the desired locations. The Lunar Shuttle federate transports materials to and from lunar orbit. Materials that it takes to the supply depot include fuel and cargo necessary to continue moon-base operations. This project analyzes modeling and simulation technologies as well as simulation interoperability. Each team from participating universities will work on and engineer their own federate(s) to participate in the SISO Spring 2011 Workshop SIW Smackdown in Boston, Massachusetts. This paper will focus on the Lunar Rover federate.

  15. Reaping the benefits of evolutionary critical technology development - system 80+trademark standardized plant design

    International Nuclear Information System (INIS)

    Matzie, R.A.; Davis, G.A.; Bagnal, C.W. Jr.; Turk, R.S.

    1993-01-01

    Light water reactors have proved themselves to be a critical part of the electrical power generation infrastructure in the United States as well as in the world. As society moves to improve the safety and economical viability of our critical technologies, we must decide the most beneficial means of making those improvements. In some cases, the critical technologies are propelled in a single leap; in others, it is the result of a continuous and deliberate series of carefully chosen steps. ABB Nuclear Systems was faced with making such a choice in the development of nuclear power plant technology. We elected to focus our development and commercialization efforts on the evolutionary System 80+ Advanced Standardized plant design. Obviously, this was because we have a strong indication that this would be the most beneficial way to meet customers' needs and reap the largest possible benefit from the development of these critical technologies. The evolutionary approach to critical technology development requires a reliance on making incremental improvements over time to the technology. This has the benefit of providing the following: 1. predictable performance based on experience, 2. enhanced safety, performance, economics 3. incremental changes in technology, 4. availability of proven equipment and systems, and 5. assured acceptance and licensability

  16. Experimental design and reporting standards for metabolomics studies of mammalian cell lines.

    Science.gov (United States)

    Hayton, Sarah; Maker, Garth L; Mullaney, Ian; Trengove, Robert D

    2017-12-01

    Metabolomics is an analytical technique that investigates the small biochemical molecules present within a biological sample isolated from a plant, animal, or cultured cells. It can be an extremely powerful tool in elucidating the specific metabolic changes within a biological system in response to an environmental challenge such as disease, infection, drugs, or toxins. A historically difficult step in the metabolomics pipeline is in data interpretation to a meaningful biological context, for such high-variability biological samples and in untargeted metabolomics studies that are hypothesis-generating by design. One way to achieve stronger biological context of metabolomic data is via the use of cultured cell models, particularly for mammalian biological systems. The benefits of in vitro metabolomics include a much greater control of external variables and no ethical concerns. The current concerns are with inconsistencies in experimental procedures and level of reporting standards between different studies. This review discusses some of these discrepancies between recent studies, such as metabolite extraction and data normalisation. The aim of this review is to highlight the importance of a standardised experimental approach to any cultured cell metabolomics study and suggests an example procedure fully inclusive of information that should be disclosed in regard to the cell type/s used and their culture conditions. Metabolomics of cultured cells has the potential to uncover previously unknown information about cell biology, functions and response mechanisms, and so the accurate biological interpretation of the data produced and its ability to be compared to other studies should be considered vitally important.

  17. SRAC: JAERI thermal reactor standard code system for reactor design and analysis

    International Nuclear Information System (INIS)

    Tsuchihashi, Keichiro; Takano, Hideki; Horikami, Kunihiko; Ishiguro, Yukio; Kaneko, Kunio; Hara, Toshiharu.

    1983-01-01

    The SRAC (Standard Reactor Analysis Code) is a code system for nuclear reactor analysis and design. It is composed of neutron cross section libraries and auxiliary processing codes, neutron spectrum routines, a variety of transport, 1-, 2- and 3-D diffusion routines, dynamic parameters and cell burn-up routines. By making the best use of the individual code function in the SRAC system, the user can select either the exact method for an accurate estimate of reactor characteristics or the economical method aiming at a shorter computer time, depending on the purpose of study. The user can select cell or core calculation; fixed source or eigenvalue problem; transport (collision probability or Sn) theory or diffusion theory. Moreover, smearing and collapsing of macroscopic cross sections are separately done by the user's selection. And a special attention is paid for double heterogeneity. Various techniques are employed to access the data storage and to optimize the internal data transfer. Benchmark calculations using the SRAC system have been made extensively for the Keff values of various types of critical assemblies (light water, heavy water and graphite moderated systems, and fast reactor systems). The calculated results show good prediction for the experimental Keff values. (author)

  18. TWRS hydrogen mitigation portable standard hydrogen monitoring system platform design and fabrication engineering task plan

    International Nuclear Information System (INIS)

    Philipp, B.L.

    1997-01-01

    The primary function of portable gas monitoring is to quickly determine tank vapor space gas composition and gas release rate, and to detect gas release events. Characterization of the gas composition is needed for safety analysis. The lower flammability limit, as well as the peak burn temperature and pressure, are dependent upon the gas composition. If there is little or no knowledge about the gas composition, safety analysis utilize compositions that yield the worst case in a deflagration or detonation. This conservative approach to unknowns necessitates a significant increase in administrative and engineering costs. Knowledge of the true composition could lead to reductions in the assumptions and therefore contribute to a reduction in controls and work restrictions. Also, knowledge of the actual composition will be required information for the analysis that is needed to remove tanks from the Watch List. Similarly, the rate of generation and release of gases is required information for performing safety analysis, developing controls, designing equipment, and closing safety issues. To determine release rate, both the gas concentrations and the dome space ventilation rates (exhauster flow rate or passive dome/atmosphere exchange rate) are needed. Therefore, to quickly verify waste tank categorization or to provide additional characterization for tanks with installed gas monitoring, a temporary, portable standard hydrogen monitoring system is needed that can be used to measure gas compositions at both high and low sensitivities

  19. From BASIS to MIRACLES

    DEFF Research Database (Denmark)

    Tsapatsaris, Nikolaos; Willendrup, Peter Kjær; E. Lechner, Ruep

    2015-01-01

    Results based on virtual instrument models for the first high-flux, high-resolution, spallation based, backscattering spectrometer, BASIS are presented in this paper. These were verified using the Monte Carlo instrument simulation packages McStas and VITESS. Excellent agreement of the neutron count...... are pivotal to the conceptual design of the next generation backscattering spectrometer, MIRACLES at the European Spallation Source....

  20. 76 FR 23690 - Version One Regional Reliability Standards for Facilities Design, Connections, and Maintenance...

    Science.gov (United States)

    2011-04-28

    ... Reliability Standards (NERC Glossary), unless a specific deviation has been justified; and, (2) documents that... Standards, the Commission proposed to direct NERC to remove this regional definition from the NERC Glossary... revised regional Reliability Standard also removes the definition of Business Day. Since these terms are...