test design criteria: Topics by WorldWideScience.org

Sample records for test design criteria

Design criteria and fabrication in-pile test section of HANARO fuel test loop

Energy Technology Data Exchange (ETDEWEB)

Kim, J. Y.

1997-10-01

Safety state fuel test loop will be equipped in HANARO to obtain the development and betterments of advanced fuel and materials through the irradiation tests. The objective of this study is to determine the design criteria and technical specification of in-pile test section and to specify the manufacturing requirements of in-pile test section. HANARO fuel test loop was designed to meet the CANDU and PWR fuel testing and in-pile section will be manufactured and installed in HANARO. The design criteria and technical specification of in-pile test section could be used the fuel and materials design with for irradiation testing IPS of HANARO fuel test loop. This results will become guidances for the planning and programming of irradiation testing. (author). 12 refs., tabs., figs.
Radiological design criteria for fusion power test facilities

International Nuclear Information System (INIS)

Singh, M.S.; Campbell, G.W.

1982-01-01

The quest for fusion power and understanding of plasma physics has resulted in planning, design, and construction of several major fusion power test facilities, based largely on magnetic and inertial confinement concepts. We have considered radiological design aspects of the Joint European Torus (JET), Livermore Mirror and Inertial Fusion projects, and Princeton Tokamak. Our analyses on radiological design criteria cover acceptable exposure levels at the site boundary, man-rem doses for plant personnel and population at large, based upon experience gained for the fission reactors, and on considerations of cost-benefit analyses
Design criteria of out-pile system of HANARO fuel test loop

Energy Technology Data Exchange (ETDEWEB)

Kim, J. Y.

1997-07-01

The objective of HANARO aims at the development and localization of nuclear technologies through the engineering tests. Thus it is very important the design and installation of the irradiation test facilities to be installed at the irradiation hole for verification test of the fuel performance are in connection with maximization of the utilization of HANARO. The principle subjects of this study are to presend and informed the detail design criteria and technical specification of out-pile system of HANARO fuel test loop for the developing of the fuel and reactor material. This results will become guidance for the planning of the irradiation testing using the HANARO fuel test loop. (author). 16 refs., 31 tabs., 9 figs.
CisLunar Habitat Internal Architecture Design Criteria

Science.gov (United States)

Jones, R.; Kennedy, K.; Howard, R.; Whitmore, M.; Martin, C.; Garate, J.

2017-01-01

BACKGROUND: In preparation for human exploration to Mars, there is a need to define the development and test program that will validate deep space operations and systems. In that context, a Proving Grounds CisLunar habitat spacecraft is being defined as the next step towards this goal. This spacecraft will operate differently from the ISS or other spacecraft in human history. The performance envelope of this spacecraft (mass, volume, power, specifications, etc.) is being defined by the Future Capabilities Study Team. This team has recognized the need for a human-centered approach for the internal architecture of this spacecraft and has commissioned a CisLunar Phase-1 Habitat Internal Architecture Study Team to develop a NASA reference configuration, providing the Agency with a "smart buyer" approach for future acquisition. THE CISLUNAR HABITAT INTERNAL ARCHITECTURE STUDY: Overall, the CisLunar Habitat Internal Architecture study will address the most significant questions and risks in the current CisLunar architecture, habitation, and operations concept development. This effort is achieved through definition of design criteria, evaluation criteria and process, design of the CisLunar Habitat Phase-1 internal architecture, and the development and fabrication of internal architecture concepts combined with rigorous and methodical Human-in-the-Loop (HITL) evaluations and testing of the conceptual innovations in a controlled test environment. The vision of the CisLunar Habitat Internal Architecture Study is to design, build, and test a CisLunar Phase-1 Habitat Internal Architecture that will be used for habitation (e.g. habitability and human factors) evaluations. The evaluations will mature CisLunar habitat evaluation tools, guidelines, and standards, and will interface with other projects such as the Advanced Exploration Systems (AES) Program integrated Power, Avionics, Software (iPAS), and Logistics for integrated human-in-the-loop testing. The mission of the Cis
77 FR 38857 - Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal...

Science.gov (United States)

2012-06-29

... Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water- Cooled Nuclear Power... Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled... draft regulatory guide (DG), DG-1280, ``Design, Inspection, and Testing Criteria for Air Filtration and...
Containment design, performance criteria and research needs for advanced reactor designs

International Nuclear Information System (INIS)

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

2004-01-01

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

International Nuclear Information System (INIS)

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

1975-06-01

In order to evaluate the ability of critical facilities at the Nevada Test Site to withstand the possible damaging effects of extreme winds and tornadoes, parameters for the effects of tornadoes and extreme winds and structural design criteria for the design and evaluation of structures were developed. The meteorological investigations conducted are summarized, and techniques used for developing the combined tornado and extreme wind risk model are discussed. The guidelines for structural design include methods for calculating pressure distributions on walls and roofs of structures and methods for accommodating impact loads from wind-driven missiles. Calculations for determining the design loads for an example structure are included
An Investigation Into Design Criteria for Affordable Housing Supply

Directory of Open Access Journals (Sweden)

Olanrewaju Abdul Lateef

2017-01-01

Full Text Available Affordable housing provision constitutes a very large scheme in any countries due to income distribution and national development. The supply of housing depends on many activities and processes. The purpose of the houses is to meet the requirement of the householders therefore design criteria must address the users’ requirements. The establishment of the design criteria constitutes an important activity at the initial phase of the housing development. The design criteria are prepared by the design team in collaboration with many stakeholders especially the householders. Housinsg design criteria are the requirements that must be considered prior to construction of the housing. Lack of adequate information on the design criteria would lead to poor householders’ satisfactions, increase in maintenance cost, abandonments and completed but not occupy housing. In Malaysia, many of these consequences are prevalent. However, while information on the house owners’ requirements is inconclusive, this current research set out to investigate the design criteria of affordable housing. The increase in the affordable housing gap in Malaysia can be reduced if the designers have a comprehensive understanding of users’ requirements and the design criteria. Through a cross sectional survey questionnaire, comprising 25 criteria, 7 criteria were found to be extremely critical. The Kaiser-Meyer-Olkin measure of sampling adequacy indicated that the strength of the relationships among variables was strong (KMO =0.716. Bartlett’s test of sphericity, which tests the overall significance of all the correlations within the correlation matrix, was significant χ2 (325 = 1825.075, p<0.001, indicating the data were drawn from the same population and that the criteria were related.Sustainability considerations are now being considered by the providers of affordable housing. Deductively, the results lead to the conclusion that a major factor responsible for the poor
Review of design criteria and safety analysis of safety class electric building for fuel test loop

Energy Technology Data Exchange (ETDEWEB)

Kim, J. Y.

1998-02-01

Steady state fuel test loop will be equipped in HANARO to obtain the development and betterment of advanced fuel and materials through the irradiation tests. HANARO fuel test loop was designed for CANDU and PWR fuel testing. Safety related system of Fuel Test Loop such as emergency cooling water system, component cooling water system, safety ventilation system, high energy line break mitigation system and remote control room was required 1E class electric supply to meet the safety operation in accordance with related code. Therefore, FTL electric building was designed to construction and install the related equipment based on seismic category I. The objective of this study is to review the design criteria and analysis the safety function of safety class electric building for fuel test loop, and this results will become guidance for the irradiation testing in future. (author). 10 refs., 6 tabs., 30 figs.
Design Criteria Based on Aesthetic Considerations

DEFF Research Database (Denmark)

Thomsen, Bente Dahl

2009-01-01

Aesthetic criteria for designs are often debated in a very subjective manner which makes it difficult to reach consensus. In order to have a more rational and transparent process, in particular in industrial design, we propose a procedure based on Baumgarten's aesthetic considerations and Thommesen......'s dividing of a form into form elements. The procedure has been tested in student projects....
Radiological design criteria

International Nuclear Information System (INIS)

Selby, J.M.; Andersen, B.V.; Carter, L.A.; Waite, D.A.

1977-01-01

Many new nuclear facilities are unsatisfactory from a radiation protection point of view, particularly when striving to maintain occupational exposure as low as practicable 'ALAP'. Radiation protection is achieved through physical protective features supplemented by administrative controls. Adequate physical protective feature should be achieved during construction so that supplemental administrative controls may be kept simple and workable. Many nuclear facilities fall short of adequate physical protective features, thus, remedial and sometimes awkward administrative procedures are required to safely conduct work. In reviewing the various handbooks, reports and regulations which deal with radiation protection, it may be noted that there is minimal radiological design guidance for application to nuclear facilities. A set of criteria or codes covering functional areas rather than specific nuclear facility types is badly needed. The following are suggested as functional areas to be considered: characterization of the Facility; siting and access; design exposure limits; layout (people and materials flow); ventilation and effluent control; radiation protection facilities and systems. The application of such radiological design criteria early in the design process would provide some assurance that nuclear facilities will be safe, flexible, and efficient with a minimum of costly retrofitting or administrative restrictions. Criteria which we have found helpful in these functional areas is discussed together with justification for adoption of such criteria and identification of problems which still require solution
Termination Criteria for Computerized Classification Testing

Directory of Open Access Journals (Sweden)

Nathan A. Thompson

2011-02-01

Full Text Available Computerized classification testing (CCT is an approach to designing tests with intelligent algorithms, similar to adaptive testing, but specifically designed for the purpose of classifying examinees into categories such as - pass- and - fail.- Like adaptive testing for point estimation of ability, the key component is the termination criterion, namely the algorithm that decides whether to classify the examinee and end the test or to continue and administer another item. This paper applies a newly suggested termination criterion, the generalized likelihood ratio (GLR, to CCT. It also explores the role of the indifference region in the specification of likelihood-ratio based termination criteria, comparing the GLR to the sequential probability ratio test. Results from simulation studies suggest that the GLR is always at least as efficient as existing methods.
Seismic design and evaluation criteria based on target performance goals

International Nuclear Information System (INIS)

Murray, R.C.; Nelson, T.A.; Kennedy, R.P.; Short, S.A.

1994-04-01

The Department of Energy utilizes deterministic seismic design/evaluation criteria developed to achieve probabilistic performance goals. These seismic design and evaluation criteria are intended to apply equally to the design of new facilities and to the evaluation of existing facilities. In addition, the criteria are intended to cover design and evaluation of buildings, equipment, piping, and other structures. Four separate sets of seismic design/evaluation criteria have been presented each with a different performance goal. In all these criteria, earthquake loading is selected from seismic hazard curves on a probabilistic basis but seismic response evaluation methods and acceptable behavior limits are deterministic approaches with which design engineers are familiar. For analytical evaluations, conservatism has been introduced through the use of conservative inelastic demand-capacity ratios combined with ductile detailing requirements, through the use of minimum specified material strengths and conservative code capacity equations, and through the use of a seismic scale factor. For evaluation by testing or by experience data, conservatism has been introduced through the use of an increase scale factor which is applied to the prescribed design/evaluation input motion
Reliability-based econometrics of aerospace structural systems: Design criteria and test options. Ph.D. Thesis - Georgia Inst. of Tech.

Science.gov (United States)

Thomas, J. M.; Hanagud, S.

1974-01-01

The design criteria and test options for aerospace structural reliability were investigated. A decision methodology was developed for selecting a combination of structural tests and structural design factors. The decision method involves the use of Bayesian statistics and statistical decision theory. Procedures are discussed for obtaining and updating data-based probabilistic strength distributions for aerospace structures when test information is available and for obtaining subjective distributions when data are not available. The techniques used in developing the distributions are explained.
Proposed design criteria for containments in Germany

International Nuclear Information System (INIS)

Schnellenbach, G.

1976-01-01

Till now all containments of German nuclear power plants have been fabricated in steel. However the nuclear power plants Gundremmingen II (KRB II) and Schmehausen II (HTR) will have prestressed concrete containments. The construction of these plants will probably start in 1975. Containments have to fulfill special tasks differing from those of pressure vessels. Because of this, design criteria for pressure vessels are not applicable to containments. On the other hand normal regulations for prestressed concrete structures are insufficient for containments. The containments KRB II and HTR are buildings of different types. KRB II is located in the interior of the reactor building of the SW-72-type. It is surrounded by a thick-walled concrete structure. HTR has the classical shape for concrete containments - vertical cylinder with spherical cap. It surrounds the reactor-building. The containment has to withstand aircraft impact forces. This influences its liner too. Design criteria have been developed for both containments, taking into consideration the special properties of these buildings. Design criteria are discussed for service-load conditions, test conditions, various forms of accident and for the ultimate load conditions. The influence of extreme external loads on the design is described. (author)
Tank SY-101 void fraction instrument functional design criteria

International Nuclear Information System (INIS)

McWethy, L.M.

1994-01-01

This document presents the functional design criteria for design, analysis, fabrication, testing, and installation of a void fraction instrument for Tank SY-101. This instrument will measure the void fraction in the waste in Tank SY-101 at various elevations
Principles and Criteria for Design

DEFF Research Database (Denmark)

Beghin, D.; Cervetto, D.; Hansen, Peter Friis

1997-01-01

The mandate of ISSC Committee IV.1 on principles and Criteria for Design is to report on the following:The ongoing concern for quantification of general economic and safety criteria for marine structures and for the development of appropriate principles for rational life cycle design using...
Maintainability design criteria for packaging of spacecraft replaceable electronic equipment.

Science.gov (United States)

Kappler, J. R.; Folsom, A. B.

1972-01-01

Maintainability must be designed into long-duration spacecraft and equipment to provide the required high probability of mission success with the least cost and weight. The ability to perform repairs quickly and easily in a space environment can be achieved by imposing specific maintainability design criteria on spacecraft equipment design and installation. A study was funded to investigate and define design criteria for electronic equipment that would permit rapid removal and replacement in a space environment. The results of the study are discussed together with subsequent simulated zero-g demonstration tests of a mockup with new concepts for packaging.
Human Systems Design Criteria

DEFF Research Database (Denmark)

Rasmussen, Jens

1982-01-01

This paper deals with the problem of designing more humanised computer systems. This problem can be formally described as the need for defining human design criteria, which — if used in the design process - will secure that the systems designed get the relevant qualities. That is not only...... the necessary functional qualities but also the needed human qualities. The author's main argument is, that the design process should be a dialectical synthesis of the two points of view: Man as a System Component, and System as Man's Environment. Based on a man's presentation of the state of the art a set...... of design criteria is suggested and their relevance discussed. The point is to focus on the operator rather than on the computer. The crucial question is not to program the computer to work on its own conditions, but to “program” the operator to function on human conditions....
Basic design criteria for an impact test frame for safety glazing; Criterios basicos de diseno de banco de ensayos para impactos de vidrios de seguridad

Energy Technology Data Exchange (ETDEWEB)

Postigo, S.; Pacios, A.; Huerta, C.

2011-07-01

The Spanish Building Code establishes the essential requirements of safety and habitability that buildings must satisfy. The Basic Document of Safety in Use and Accessibility identifies some critical areas where falling through brittle elements may cause a risk to the user. The document also establishes the minimum performance of glasses located in such areas, according to the impact procedure described in UNE-EN 12600:2003. However, this standard does not provide detailed information about the characteristics of the test equipment, but indicates a final calibration as validation test. The general criteria and conditions of this calibration are also incorporated in the UNE-EN 12600. To better achieve a successful manufacture of a pendulum complying with calibration limits, a proposal of the basic design criteria of a test frame for impacts of safety glazing is presented in this paper. Prototypes and results have been evaluated using dynamic design criteria of the impact phenomenon. Three criteria proposed and applied in the design and manufacture of a real test frame have helped to achieve the calibration required by the UNE-EN 12600:2003. The repeatability and reproducibility of the tests presented in this paper also guaranty the robustness of the set-up. (Author)

Redefining design criteria for Pu-238 gloveboxes

International Nuclear Information System (INIS)

Acosta, S.V.

1998-01-01

Enclosures for confinement of special nuclear materials (SNM) have evolved into the design of gloveboxes. During the early stages of glovebox technology, established practices and process operation requirements defined design criteria. Proven boxes that performed and met or exceeded process requirements in one group or area, often could not be duplicated in other areas or processes, and till achieve the same success. Changes in materials, fabrication and installation methods often only met immediate design criteria. Standardization of design criteria took a big step during creation of ''Special-Nuclear Materials R and D Laboratory Project, Glovebox standards''. The standards defined design criteria for every type of process equipment in its most general form. Los Alamos National Laboratory (LANL) then and now has had great success with Pu-238 processing. However with ever changing Environment Safety and Health (ES and H) requirements and Ta-55 Facility Configuration Management, current design criteria are forced to explore alternative methods of glovebox design fabrication and installation. Pu-238 fuel processing operations in the Power Source Technologies Group have pushed the limitations of current design criteria. More than half of Pu-238 gloveboxes are being retrofitted or replaced to perform the specific fuel process operations. Pu-238 glovebox design criteria are headed toward process designed single use glovebox and supporting line gloveboxes. Gloveboxes that will house equipment and processes will support TA-55 Pu-238 fuel processing needs into the next century and extend glovebox expected design life
Guidelines and criteria for nuclear piping and support evaluation and design

International Nuclear Information System (INIS)

Rehn, D.L.; Stout, D.H. Jr.; Minichiello, J.C.

1993-05-01

The EPRI Research Project 2967-2 has set its fundamental goal to be the development of realistic guidelines and criteria for piping and pipe support design and evaluation. The focus is on items that are most critical to utilities and consists of a variety of tasks relating to piping and pipe support design. One objective of this report is to summarize the recommendations from the seven task reports of the first phase of the project and to provide examples of how to use those recommendations. Criteria and methods for evaluating both short and long term system operation are addressed. Benefits gained from applying the recommendations to actual systems are discussed. The report also reviews other work currently being done within the nuclear industry and assesses the impact of that work on the recommended criteria/methods of this project. The second objective of the report is to discuss possible changes needed in the governing codes or licensing commitments in order to implement the recommendations. Finally, the report describes further research which can be done to advance the criteria presented and answer questions concerning applicability of the proposed criteria to designs not tested/investigated. The basic conclusion reached in the project is that many of the criteria/methods used today in piping analysis/design are overly conservative. The report's conclusion is supported by extensive literature searches, tests, and analyses. The report presents a robust source of reference to utilities which wish to implement changes in criteria and methods. Most of the criteria and methodologies described in the seven task reports and summarized in the following sections will require some effort in licensing or Code changes
Containment penetration design criteria and implementation

International Nuclear Information System (INIS)

Perry, R.F.; Rigamonti, G.; Dainora, J.

1975-01-01

A rational design criteria is presented which serves as a basis for the design and analysis of containment piping penetrations. The criteria includes the effect of temperature as well as mechanical loads for the full range of plant conditions. With this criteria various penetration flued head designs have been compared and optimization achieved. Sleeve wall dimensions and containment loads have been determined without reference to piping configuration. An interaction theory which allows the implementation of the criteria for the determination of design loads and minimum sleeve wall thickness. The interaction theory developed applies to elastic-perfectly plastic cylinders (pipes and sleeves) and accounts for the simultaneous load resultants of transverse shear force, bending moment, torsional moment, and axial force in addition to internal pipe pressure. Application of the theory developed to the determination of sleeve thickness and containment design loads is presented in detail. (Auth.)
FHR Generic Design Criteria

Energy Technology Data Exchange (ETDEWEB)

Flanagan, George F [ORNL; Holcomb, David Eugene [ORNL; Cetiner, Sacit M [ORNL

2012-06-01

The purpose of this document is to provide an initial, focused reference to the safety characteristics of and a licensing approach for Fluoride-Salt-Cooled High-Temperature Reactors (FHRs). The document does not contain details of particular reactor designs nor does it attempt to identify or classify either design basis or beyond design basis accidents. Further, this document is an initial attempt by a small set of subject matter experts to document the safety and licensing characteristics of FHRs for a larger audience. The document is intended to help in setting the safety and licensing research, development, and demonstration path forward. Input from a wider audience, further technical developments, and additional study will be required to develop a consensus position on the safety and licensing characteristics of FHRs. This document begins with a brief overview of the attributes of FHRs and then a general description of their anticipated safety performance. Following this, an overview of the US nuclear power plant approval process is provided that includes both test and power reactors, as well as the role of safety standards in the approval process. The document next describes a General Design Criteria (GDC) - based approach to licensing an FHR and provides an initial draft set of FHR GDCs. The document concludes with a description of a path forward toward developing an FHR safety standard that can support both a test and power reactor licensing process.
Translating DWPF design criteria into an engineered facility design

International Nuclear Information System (INIS)

Kemp, J.B.

1986-01-01

The Defense Waste Processing Facility (DWPF) takes radioactive defense waste sludge and the radioactive nuclides, cesium and strontium, from the salt solution, and incorporates them in borosilicate glass in stainless steel canisters, for subsequent disposal in a deep geologic repository. The facility was designed by Bechtel National, Inc. under a subcontract from E.I. DuPont de Nemurs and Co., the prime contractor for the Department of Energy, for the design, construction and commissioning of the plant. The design criteria were specified by the DuPont Company, based upon their extensive experience as designer, and operator since the early 1950's, of the existing Savannah River Plant facilities. Some of the design criteria imposed unusual or new requirements on the detailed design of the facilities. This paper describes some of these criteria, encompassing several engineering disciplines, and discusses the solutions and designs which were developed for the DWPF
Risk based seismic design criteria

International Nuclear Information System (INIS)

Kennedy, R.P.

1999-01-01

In order to develop a risk based seismic design criteria the following four issues must be addressed: (1) What target annual probability of seismic induced unacceptable performance is acceptable? (2) What minimum seismic margin is acceptable? (3) Given the decisions made under Issues 1 and 2, at what annual frequency of exceedance should the safe-shutdown-earthquake (SSE) ground motion be defined? (4) What seismic design criteria should be established to reasonably achieve the seismic margin defined under Issue 2? The first issue is purely a policy decision and is not addressed in this paper. Each of the other three issues are addressed. Issues 2 and 3 are integrally tied together so that a very large number of possible combinations of responses to these two issues can be used to achieve the target goal defined under Issue 1. Section 2 lays out a combined approach to these two issues and presents three potentially attractive combined resolutions of these two issues which reasonably achieves the target goal. The remainder of the paper discusses an approach which can be used to develop seismic design criteria aimed at achieving the desired seismic margin defined in resolution of Issue 2. Suggestions for revising existing seismic design criteria to more consistently achieve the desired seismic margin are presented. (orig.)
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
Design criteria for piping and nozzles program

International Nuclear Information System (INIS)

Moore, S.E.; Bryson, J.W.

1977-01-01

This report reviews the activities and accomplishments of the Design Criteria for Piping and Nozzles program being conducted by the Oak Ridge National Laboratory for the period July 1, 1975, to September 30, 1976. The objectives of the program are to conduct integrated experimental and analytical stress analysis studies of piping system components and isolated and closely-spaced pressure vessel nozzles in order to confirm and/or improve the adequacy of structural design criteria and analytical methods used to assure the safe design of nuclear power plants. Activities this year included the development of a finite-element program for analyzing two closely spaced nozzles in a cylindrical pressure vessel; a limited-parameter study of vessels with isolated nozzles, finite-element studies of piping elbows, a fatigue test of an out-of-round elbow, summary and evaluation of experimental studies on the elastic-response and fatigue failure of tees, parameter studies on the behavior of flanged joints, publication of fifteen topical reports and papers on various experimental and analytical studies; and the development and acceptance of a number of design rules changes to the ASME Code. 2 figures, 2 tables
Design Criteria for Achieving Acceptable Indoor Radon Concentration

DEFF Research Database (Denmark)

Rasmussen, Torben Valdbjørn

2016-01-01

Design criteria for achieving an acceptable indoor radon concentration are presented in this paper. The paper suggests three design criteria. These criteria have to be considered at the early stage of the building design phase to meet the latest recommendations from the World Health Organization...... in most countries. The three design criteria are; first, establishing a radon barrier facing the ground; second, lowering the air pressure in the lower zone of the slab on ground facing downwards; third, diluting the indoor air with outdoor air. The first two criteria can prevent radon from infiltrating...... from the ground, and the third criteria can dilute the indoor air. By combining these three criteria, the indoor radon concentration can be lowered achieving an acceptable level. In addition, a cheap and reliable method for measuring the radon concentration in the indoor air is described. The provision...
CO2 Employment as Refrigerant Fluid with a Low Environmental Impact. Experimental Tests on Arugula and Design Criteria for a Test Bench

Directory of Open Access Journals (Sweden)

Biagio Bianchi

2015-03-01

Full Text Available In order to define design criteria for CO2 refrigeration systems to be used for agricultural products and foodstuff storage, a variable geometrical system was realized, with the goal of meeting a wide range of environmental and process conditions, such as producing low environmental impact and maintaining the highest Coefficient of Performance (COP, at the same time. This test-bench, at semi-industrial scale, was designed as a result of experimental tests carried out on Arugula. The storage tests showed that all samples stored in cold rooms with R.H. control showed a slight increase of weight but also small rot zones in all the boxes due to an excessive accumulation of water condensation; thus, the system may not have achieved conditions that RH requires in a given range, without reaching saturation condition. At the same time, the use of CO2 must be adequately tested along its thermodynamic cycle, during steady state and/or transient conditions, imposing variable working conditions that can simulate plant starting phase or some striking conservation process, like those that characterize sausages. The designed plant will allow studying these specific performances and evaluate COP variation, according to environmental and plant operating conditions.
Design criteria for advanced reactors

International Nuclear Information System (INIS)

Dennielou, Y.

1991-01-01

Design criteria for advanced reactors are discussed, including safety aspects, site selection, problems related to maintenance and possibility of repairing or replacing structures or components of a nuclear power plant, the human factor considerations. Bearing in mind that some of these criteria are the subject of consensus at international level, the author suggests to establish a table of different operator requirements, to prepare a dossier on the comparison of input data for probabilistic risk analysis, to take into consideration the means to control a severe accident from the very start of the design
NASA balloon design and flight - Philosophy and criteria

Science.gov (United States)

Smith, I. S., Jr.

1993-01-01

The NASA philosophy and criteria for the design and flight of scientific balloons are set forth and discussed. The thickness of balloon films is standardized at 20.3 microns to isolate potential film problems, and design equations are given for specific balloon parameters. Expressions are given for: flight-stress index, total required thickness, cap length, load-tape rating, and venting-duct area. The balloon design criteria were used in the design of scientific balloons under NASA auspices since 1986, and the resulting designs are shown to be 95 percent effective. These results represent a significant increase in the effectiveness of the balloons and therefore indicate that the design criteria are valuable. The criteria are applicable to four balloon volume classes in combination with seven payload ranges.
Seismic design criteria for the Clinch River Breeder Reactor Plant

International Nuclear Information System (INIS)

Morrone, A.; Bitner, J.L.; Sigal, G.B.

1975-01-01

The general criteria for seismic resistant design for structures, systems and components of the Clinch River Breeder Reactor Plant (CRBRP) are presented and discussed. Site dependency of the maximum ground accelerations for the Operating Basis Earthquake and the Safe Shutdown Earthquake is described from the viewpoint of historical records and geological and seismological studies for the CRBRP site. The respective ground response spectra are derived by normalization of the latest AEC Regulatory standard shapes to these maximum ground accelerations. Modeling and analytical techniques and requirements are given. In addition, loading conditions and categories, loading combinations, earthquake direction effects and allowable damping values are defined. A discussion of the testing criteria which considers both single and multiple frequency test motions, and basic test procedures for single frequency sine beat testing is presented. (U.S.)
Design Criteria for Achieving Low Radon Concentration Indoors

DEFF Research Database (Denmark)

Rasmussen, Torben Valdbjørn

2016-01-01

Design criteria for achieving low radon concentration indoors are presented in this paper. The paper suggests three design criteria. These criteria have to be considered at the early stage of the building design phase to meet the latest recommendations from the World Health Organization in most...... countries. The three design criteria are; first, establishing a radon barrier facing the ground; second, lowering the air pressure in the lower zone of the slab on ground facing downwards; third, diluting the indoor air with outdoor air. Three criteria when used can prevent radon infiltration and lower...... the radon concentration in the indoor air. In addition, a cheap and reliable method for measuring the radon concentration in the air indoors is described. The provision on radon in the Danish Building Regulations complies with the latest recommendations from the World Health Organization. Radon can cause...
Licensing experiences, risk assessment, demonstration test on nuclear fuel packages and design criteria for sea going vessel carrying spent fuel in Japan

International Nuclear Information System (INIS)

Aoki, S.; Ikeda, K.

1978-01-01

In Japan spent fuels from nuclear power plants shall be shipped to reprocessing plants by sea-going vessels. Atomic Energy Committee has initiated a board of experts to implement the assessment of environmental safety for sea transport. As a part of the assessment a study has been conducted by Central Research Institute of Electric Power Industry under sponsorship of Nuclear Safety Bureau, which is intended to guarantee the safety of sea transport. Nuclear Safety Bureau also has a program to carry out a long term demonstration test on spent fuel package using full scale package models. The test consists of drop, heat transfer, fire, collapse under high external pressure, immersion, shielding and subcritical test. The purpose of this test is to obtain the public acceptance and also to verify the adequacy of the safety analysis for nuclear fuel packages. In order to secure the safety of sea transport, the Ministry of Transportation has provided for the design criteria for sea-going vessel in the case of full load shipping, which aims to make minimum the probability of sinking at collision, grounding and other unforeseen accidents on the sea and also to retain the radiation exposure to crews as low as possible. The design criteria consists of the following items: (1) structural strength of vessel, (2) collision protective structure, (3) arrangement of holds, (4) stability after damage, (5) grounding protective structure, (6) cooling system, (7) tie-down equipment, (8) radiation inspection apparatus, (9) decontamination facilities, (10) emergency water flooding equipment for ship fire, (11) emergency electric sources, etc. Based on the design criteria a sea-going vessel names HINOURA-MARU has been reconstructed to transport spent fuel packages from nuclear power stations to the reprocessing plant
Intelligent intefrace design criteria

International Nuclear Information System (INIS)

Sicard, Y.; Siebert, S.; Thebault, M.H.

1990-01-01

Optimum adequation between control means and the capacities of the teams of operators is sought for to achieve computerization of control and monitoring interfaces. Observation of the diagnosis activity of populations of operators in incident situations on a simulator enables design criteria well-suited to the characteristics of the detection, interpretation of symptoms and incident location tasks to be defined. A software tool based on a qualitative approach enables the design process to be systematized
Ammunition Peculiar Equipment (APE) 1995, NIR Propellant Analyzer, to MIL-STD-398, Military Standard Shields, Operational for Ammunition Operations, Criteria for Design of and Tests for Acceptance

National Research Council Canada - National Science Library

2003-01-01

... (SJMAC-DEM) to test the Ammunition Peculiar Equipment (APE) 1995 NIR Propellant Analyzer, to MIL-STD-398, "Military Standard Shields, Operational for Ammunition Operations, Criteria for Design of and Tests for Acceptance...
Position paper: Seismic design criteria

International Nuclear Information System (INIS)

Farnworth, S.K.

1995-01-01

The purpose of this paper is to document the seismic design criteria to be used on the Title 11 design of the underground double-shell waste storage tanks and appurtenant facilities of the Multi-Function Waste Tank Facility (MWTF) project, and to provide the history and methodologies for determining the recommended Design Basis Earthquake (DBE) Peak Ground Acceleration (PGA) anchors for site-specific seismic response spectra curves. Response spectra curves for use in design are provided in Appendix A
DOE natural phenomenal hazards design and evaluation criteria

International Nuclear Information System (INIS)

Murray, R.C.; Nelson, T.A.; Short, S.A.; Kennedy, R.P.; Chander, H.; Hill, J.R.; Kimball, J.K.

1994-10-01

It is the policy of the Department of Energy (DOE) to design, construct, and operate DOE facilities so that workers, the general public, and the environment are protected from the impacts of natural phenomena hazards (NPH). Furthermore, DOE has established explicit goals of acceptable risk for NPH performance. As a result, natural phenomena hazard (earthquake, extreme wind, and flood) design and evaluation criteria for DOE facilities have been developed based on target probabilistic performance goals. These criteria include selection of design/evaluation NPH input from probabilistic hazard curves combined with commonly practiced deterministic response evaluation methods and acceptance criteria with controlled levels of conservatism. For earthquake considerations, conservatism is intentionally introduced in specification of material strengths and capacities, in the allowance of limited inelastic behavior, and by a seismic scale factor. Criteria have been developed following a graded approach for several performance goals ranging from that appropriate for normal-use facilities to that appropriate for facilities involving hazardous or critical operations. Performance goals are comprised of qualitative expressions of acceptable behavior and of target quantitative probabilities that acceptable limits of behavior are maintained. The criteria are simple procedures but have a rigorous basis. This paper addresses DOE seismic design and evaluation criteria
Independent review of Oak Ridge HCTW test program and development of seismic evaluation criteria

International Nuclear Information System (INIS)

1995-05-01

Many of the existing buildings at the Oak Ridge Y-12 Plant are steel frame construction with unreinforced hollow clay tile infill walls (HCTW). The HCTW infill provides some lateral seismic resistance to the design/evaluation basis earthquake; however acceptance criteria for this construction must be developed. The basis for the development of seismic criteria is the Oak Ridge HCTW testing and analysis program and the target performance goals of DOE 5480.28 and DOE-STD-1020-94. This report documents and independent review of the testing and analysis program and development of recommended acceptance criteria for Oak Ridge HCTW construction. The HCTW test program included ''macro'' wall in-plane and out-of-plane tests, full-scale wall in-plane and out-of-plane tests, in-situ out-of-plane test, shake table tests, and masonry component tests

46 CFR 154.466 - Design criteria.

Science.gov (United States)

2010-10-01

... GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) CERTAIN BULK DANGEROUS CARGOES SAFETY STANDARDS FOR... § 154.466 Design criteria. (a) The insulation for a cargo tank without a secondary barrier must be... cargo tank with a secondary barrier must be designed for the secondary barrier at the design temperature...
A study on design and testing of software module of safety software

International Nuclear Information System (INIS)

Sohn, Se Do; Seong, Poong Hyun

2000-01-01

The design criteria of the software module were based on complexity of the module and the cohesion of the module. The easiness of detection of a fault in the software module can be an additional candidate for the module design criteria. The module test coverage criteria and test case generation is reviewed from the aspects of module testability, easiness of the fault detection. One of the methods is making the numerical results as output in addition to the logical outputs. With modules designed with high testability, the test case generation and test coverage can be made more effective
New facility shield design criteria

International Nuclear Information System (INIS)

Howell, W.P.

1981-07-01

The purpose of the criteria presented here is to provide standard guidance for the design of nuclear radiation shields thoughout new facilities. These criteria are required to assure a consistent and integrated design that can be operated safely and economically within the DOE standards. The scope of this report is confined to the consideration of radiation shielding for contained sources. The whole body dose limit established by the DOE applies to all doses which are generally distributed throughout the trunk of the body. Therefore, where the whole body is the critical organ for an internally deposited radionuclide, the whole body dose limit applies to the sum of doses received must assure control of the concentration of radionuclides in the building atmosphere and thereby limit the dose from internal sources
Functional design criteria for an exploratory shaft facility in salt: Technical report

International Nuclear Information System (INIS)

1986-11-01

The purpose of the Functional Criteria for Design is to provide technical direction for the development of detailed design criteria for the exploratory shaft facility. This will assure that the exploratory shaft facility will be designed in accordance with the current Mission Plan as well as the Nuclear Waste Policy Act and 10 CFR Part 60, which will facilitate the licensing process. The functional criteria for design are not intended to limit or constrain the designer's flexibility. The following philosophies will be incorporated in the designs: (1) The exploratory shaft will be designed to fulfill its intended purpose which is to characterize the salt site by subsurface testing; (2) the design will minimize any adverse impact which the facility may cause to the environment and any damage to the site if it should be found suitable for a repository; (3) the health and safety of the public and of the workers will be an essential factor in the design; (4) sound engineering principles and practices will be consistently employed in the design process; (5) the exploratory shaft and related surface and subsurface facilities will be designed to be economical and reliable in construction, operation, and maintenance; and (6) the exploratory shaft facility will be designed in accordance with applicable federal, state, and local regulations, as well as all applicable national consensus codes and standards
Thermal-hydraulic criteria for the APT tungsten neutron source design

International Nuclear Information System (INIS)

Pasamehmetoglu, K.

1998-03-01

This report presents the thermal-hydraulic design criteria (THDC) developed for the tungsten neutron source (TNS). The THDC are developed for the normal operations, operational transients, and design-basis accidents. The requirements of the safety analyses are incorporated into the design criteria, consistent with the integrated safety management and the safety-by-design philosophy implemented throughout the APT design process. The phenomenology limiting the thermal-hydraulic design and the confidence level requirements for each limit are discussed. The overall philosophy of the uncertainty analyses and the confidence level requirements also are presented. Different sets of criteria are developed for normal operations, operational transients, anticipated accidents, unlikely accidents, extremely unlikely accidents, and accidents during TNS replacement. In general, the philosophy is to use the strictest criteria for the high-frequency events. The criteria is relaxed as the event frequencies become smaller. The THDC must be considered as a guide for the design philosophy and not as a hard limit. When achievable, design margins greater than those required by the THDC must be used. However, if a specific event sequence cannot meet the THDC, expensive design changes are not necessary if the single event sequence results in sufficient margin to safety criteria and does not challenge the plant availability or investment protection considerations
Some considerations for establishing seismic design criteria for nuclear plant piping

International Nuclear Information System (INIS)

Chen, W.P.; Chokshi, N.C.

1997-01-01

The Energy Technology Engineering Center (ETEC) is providing assistance to the U.S. NRC in developing regulatory positions on the seismic analysis of piping. As part of this effort, ETEC previously performed reviews of the ASME Code, Section III piping seismic design criteria as revised by the 1994 Addenda. These revised criteria were based on evaluations by the ASME Special Task Group on Integrated Piping Criteria (STGIPC) and the Technical Core Group (TCG) of the Advanced Reactor Corporation (ARC) of the earlier joint Electric Power Research Institute (EPRI)/NRC Piping ampersand Fitting Dynamic Reliability (PFDR) program. Previous ETEC evaluations reported at the 23rd WRSM of seismic margins associated with the revised criteria are reviewed. These evaluations had concluded, in part, that although margins for the timed PFDR tests appeared acceptable (>2), margins in detuned tests could be unacceptable (<1). This conclusion was based primarily on margin reduction factors (MRFs) developed by the ASME STGIPC and ARC/TCG from realistic analyses of PFDR test 36. This paper reports more recent results including: (1) an approach developed for establishing appropriate seismic margins based on PRA considerations, (2) independent assessments of frequency effects on margins, (3) the development of margins based on failure mode considerations, and (4) the implications of Code Section III rules for Section XI
Seismic design criteria used for electrical raceway systems in commercial nuclear power plants

International Nuclear Information System (INIS)

Summers, P.B.; Manrique, M.A.; Nelson, T.A.

1991-01-01

This paper summarizes some of the seismic design approaches, relevant technical issues and criteria used over the years for design of electrical raceway systems at commercial nuclear power plant facilities. The approaches used for design and endorsed by the NRC can be seen to be quite varied. In recent years, considerably more rigor has been required for raceway design, as well as for the level of design basis documentation produced. However, there has also been a willingness by the NRC to accept rational approaches based on testing, analytical results or experience data, provided proper justification is given. Such rational approaches can simplify the significant task of analysis, design and construction of miles of raceways and thousands of raceway supports. Summarizing past practice and identifying relevant technical issues are an important first step in formalizing up-to-date criteria for new raceway designs
Packaging design criteria for the Hanford Ecorok Packaging

International Nuclear Information System (INIS)

Mercado, M.S.

1996-01-01

The Hanford Ecorok Packaging (HEP) will be used to ship contaminated water purification filters from K Basins to the Central Waste Complex. This packaging design criteria documents the design of the HEP, its intended use, and the transportation safety criteria it is required to meet. This information will serve as a basis for the safety analysis report for packaging
Packaging design criteria for the MCO cask

International Nuclear Information System (INIS)

Clements, M.D.

1996-01-01

Approximately 2,100 metric tons of unprocessed, irradiated nuclear fuel elements are presently stored in the K Basins. To permit cleanup of the K Basins and fuel conditioning, the fuel will be transported from the K Basins to a Canister Storage Building in the 200 East Area. The purpose of this packaging design criteria is to provide criteria for the design, fabrication, and use of a packaging system to transport the large quantities of irradiated nuclear fuel elements positioned within Multiple Canister Overpacks
Multi-Criteria Approach in Multifunctional Building Design Process

Science.gov (United States)

Gerigk, Mateusz

2017-10-01

The paper presents new approach in multifunctional building design process. Publication defines problems related to the design of complex multifunctional buildings. Currently, contemporary urban areas are characterized by very intensive use of space. Today, buildings are being built bigger and contain more diverse functions to meet the needs of a large number of users in one capacity. The trends show the need for recognition of design objects in an organized structure, which must meet current design criteria. The design process in terms of the complex system is a theoretical model, which is the basis for optimization solutions for the entire life cycle of the building. From the concept phase through exploitation phase to disposal phase multipurpose spaces should guarantee aesthetics, functionality, system efficiency, system safety and environmental protection in the best possible way. The result of the analysis of the design process is presented as a theoretical model of the multifunctional structure. Recognition of multi-criteria model in the form of Cartesian product allows to create a holistic representation of the designed building in the form of a graph model. The proposed network is the theoretical base that can be used in the design process of complex engineering systems. The systematic multi-criteria approach makes possible to maintain control over the entire design process and to provide the best possible performance. With respect to current design requirements, there are no established design rules for multifunctional buildings in relation to their operating phase. Enrichment of the basic criteria with functional flexibility criterion makes it possible to extend the exploitation phase which brings advantages on many levels.
Design criteria for prestressed concrete pressure vessels

International Nuclear Information System (INIS)

Schimmelpfennig, K.

1989-01-01

The work concerned with the PCRVs has been focussed on topics which are not sufficiently covered by the usual codes with respect to the special structure of PCRVs and the special demands on it, and different investigations yielding a basis for such specific design criteria have been carried out. Only a couple of subjects being in the fore under the aspect of defining quality enlarging design criteria for PCRVs are outlined. The materials for the concrete to be used for the PCRVs are carefully selected. (DG)
Working Towards Unified Safety Design Criteria for Modular High Temperature Gas-cooled Reactor Designs

International Nuclear Information System (INIS)

Reitsma, Frederik; Silady, Fred; Kunitomi, Kazuhiko

2014-01-01

The Nuclear Power Development Section of the IAEA recently received approval for a Coordinated Research Project (CRP) to investigate and make proposals on modular High Temperature Gas-cooled Reactor (HTGR) Safety design criteria. It is expected that these criteria would consider past experience and existing safety standards in the light of modular HTGR material and design characteristics to propose safety design criteria. It will consider the deterministic and risk-informed safety design standards that apply to the wide spectrum of Off- normal events under development worldwide for existing and planned HTGRs. The CRP would also take into account lessons from the Fukushima Daiichi accident, clarifying the safety approach and safety evaluation criteria for design and beyond design basis events, including those events that can affect multiple reactor modules and/or are dependent on the application proximate to the plant site. (e. g., industrial process steam/heat). The logical flow of criteria is from the fundamental inherent safety characteristics of modular HTGRs and associated expected performance characteristics, to the safety functions required to ensure those characteristics during the wide spectrum of Off-normal events, and finally to specific criteria related to those functions. This is detailed in the paper with specific examples included of how it may be applied. The results of the CRP will be made available to the member states and HTGR community. (author)
Evaluation of seismic criteria used in design of INEL facilities

International Nuclear Information System (INIS)

Young, G.A.

1977-01-01

This report provides the results of an independent evaluation of seismic studies that were made to establish the seismic acceleration levels and the response spectra used in the design of vital facilities at Idaho National Engineering Laboratory. A comparison of the procedures used to define the seismic acceleration values and response spectra at INEL with the requirements of the Nuclear Regulatory Commission showed that additional geologic studies would probably be required in order to fulfill NRC regulations. Recommendations are made on justifiable changes in the acceleration values and response spectra used at INEL. The geologic, geophysical, and seismological studies needed to provide a better understanding of the tectonic processes in the Snake River plains and the surrounding region are identified. Both potential and historical acceleration values are evaluated on a probability basis to permit a risk assessment approach to the design of new facilities and facility modifications. Studies conducted to develop seismic criteria for the design of the Loss of Fluid Test reactor and the New Waste Calcining Facility were selected as typical examples of criteria development previously used in the design of INEL facilities
Hydraulic Design Criteria for Spacer Grids of Nuclear Fuel Element

International Nuclear Information System (INIS)

Juanico, Luis; Brasnarof, Daniel

2000-01-01

In this paper a hydraulic model for calculating the pressure drop on the CARA spacer grids is extended.This model is validated and feedback from experimental hydraulic test performed in a low pressure loop.The importance of the spacer grid geometric parameter (that is, its thickness and length, the number and kind of their fix spacer), developing hydraulic design criteria for spacer grid on fuel element
NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

International Nuclear Information System (INIS)

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

2005-01-01

This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal
Development of a chromatographic method with multi-criteria decision making design for simultaneous determination of nifedipine and atenolol in content uniformity testing.

Science.gov (United States)

Ahmed, Sameh; Alqurshi, Abdulmalik; Mohamed, Abdel-Maaboud Ismail

2018-07-01

A new robust and reliable high-performance liquid chromatography (HPLC) method with multi-criteria decision making (MCDM) approach was developed to allow simultaneous quantification of atenolol (ATN) and nifedipine (NFD) in content uniformity testing. Felodipine (FLD) was used as an internal standard (I.S.) in this study. A novel marriage between a new interactive response optimizer and a HPLC method was suggested for multiple response optimizations of target responses. An interactive response optimizer was used as a decision and prediction tool for the optimal settings of target responses, according to specified criteria, based on Derringer's desirability. Four independent variables were considered in this study: Acetonitrile%, buffer pH and concentration along with column temperature. Eight responses were optimized: retention times of ATN, NFD, and FLD, resolutions between ATN/NFD and NFD/FLD, and plate numbers for ATN, NFD, and FLD. Multiple regression analysis was applied in order to scan the influences of the most significant variables for the regression models. The experimental design was set to give minimum retention times, maximum resolution and plate numbers. The interactive response optimizer allowed prediction of optimum conditions according to these criteria with a good composite desirability value of 0.98156. The developed method was validated according to the International Conference on Harmonization (ICH) guidelines with the aid of the experimental design. The developed MCDM-HPLC method showed superior robustness and resolution in short analysis time allowing successful simultaneous content uniformity testing of ATN and NFD in marketed capsules. The current work presents an interactive response optimizer as an efficient platform to optimize, predict responses, and validate HPLC methodology with tolerable design space for assay in quality control laboratories. Copyright © 2018 Elsevier B.V. All rights reserved.
Seismic design criteria for special isotope separation plant structures

International Nuclear Information System (INIS)

Wrona, M.W.; Wuthrich, S.J.; Rose, D.L.; Starkey, J.

1989-01-01

This paper describes the seismic criteria for the design of the Special Isotope Separation (SIS) production plant. These criteria are derived from the applicable Department of Energy (DOE) orders, references and proposed standards. The SIS processing plant consistent of Load Center Building (LCB), Dye Pump Building (DPB), Laser Support Building (LSB) and Plutonium Processing Building (PPB). The facility-use category for each of the SIS building structures is identified and the applicable seismic design criteria and parameters are selected
Nevada Test Site Waste Acceptance Criteria, December 2000

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-12-01

This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal.
Nevada Test Site Waste Acceptance Criteria, December 2000

International Nuclear Information System (INIS)

2000-01-01

This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal
Design criteria and principles for criticality detection and alarm systems

International Nuclear Information System (INIS)

Delafield, H.J.; Clifton, J.J.

1984-10-01

The report gives design principles and criteria for criticality detection and alarm systems based on earlier work and revised in the light of more recent experience. In particular, account is taken of the developments which have taken place in the field of radiation detection and in the understanding of the different types of criticality excursion. General guidance is given on the principles to apply in deciding upon the need for a criticality system. The characteristics of a criticality incident are described in terms of the minimum incident of concern, and the radiation field. Criteria for the threshold of detection of a criticality incident are then derived and the methods of detection considered. The selection and siting of criticality detectors is discussed, and design principles are given for alarm systems. Finally, testing and post-alarm procedures are outlined, followed by a summary of the principal recommendations. The supporting Appendices include a discussion of reliability and a summary of radiation detector characteristics. (author)

Crew Transportation Technical Standards and Design Evaluation Criteria

Science.gov (United States)

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

2015-01-01

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

Energy Technology Data Exchange (ETDEWEB)

Yun, C H [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Yu, T S [Daewoo Engineering Company, Sungnam (Korea, Republic of); Ko, H M [Seoul National Univ., Seoul (Korea, Republic of)

1990-11-15

The objective of the present project is to develop design criteria for the structural stability of rock cavity for the underground repository are defined, according to which detailed descriptions for design methodologies, design stages and stability analysis of the cavity are made. The proposed criteria can be used as a guide for the preparation of design codes which are to be established as the site condition and technical emplacement procedure are fixed. The present report first reviews basic safety requirements and criteria of the underground disposal of nuclear wastes for the establishment of design concepts and stability analysis of the rock cavity. Important factors for the design are also described by considering characteristics of the wastes and underground facilities. The present project has investigated technical aspects on the design of underground structures based on the currently established underground construction technologies, and presented a proposal for design criteria for the structural stability of the nuclear waste repository. The proposed criteria consist of general provisions, geological exploration, rock classification, design process and methods, supporting system, analyses and instrumentation.
Radiological criteria for underground nuclear tests

International Nuclear Information System (INIS)

Malik, J.S.; Brownlee, R.R.; Costa, C.F.; Mueller, H.F.; Newman, R.W.

1981-04-01

The radiological criteria for the conduct of nuclear tests have undergone many revisions with the current criteria being 0.17 rad for uncontrolled populations and 0.5 rad for controllable populations. Their effect upon operations at the Nevada Test Site and the current off-site protective plans are reviewed for areas surrounding the Site. The few accidental releases that have occurred are used to establish estimates of probability of release and of hazard to the population. These are then put into context by comparing statistical data on other accidents and cataclysms. The guidelines established by DOE Manual Chapter MC-0524 have never been exceeded during the entire underground nuclear test program. The probability of real hazard to off-site populations appears to be sufficiently low as not to cause undue concern to the citizenry
Radiological criteria for underground nuclear tests

Energy Technology Data Exchange (ETDEWEB)

Malik, J.S.; Brownlee, R.R.; Costa, C.F.; Mueller, H.F.; Newman, R.W.

1981-04-01

The radiological criteria for the conduct of nuclear tests have undergone many revisions with the current criteria being 0.17 rad for uncontrolled populations and 0.5 rad for controllable populations. Their effect upon operations at the Nevada Test Site and the current off-site protective plans are reviewed for areas surrounding the Site. The few accidental releases that have occurred are used to establish estimates of probability of release and of hazard to the population. These are then put into context by comparing statistical data on other accidents and cataclysms. The guidelines established by DOE Manual Chapter MC-0524 have never been exceeded during the entire underground nuclear test program. The probability of real hazard to off-site populations appears to be sufficiently low as not to cause undue concern to the citizenry.
Design criteria monograph for pressurized metal cases

Science.gov (United States)

1972-01-01

Organiation and presentation of data pertaining to design of solid propellant rocket engine cases are discussed. Design criteria are presented in form of monograph based on accumulated experience and knowledge. Improvements in reliability, cost effectiveness, and engine efficiency are stressed.
Criteria procedure development for tender in construction design

Directory of Open Access Journals (Sweden)

Malykha Galina Gennad’evna

Full Text Available This article deals with the problem of criteria optimization in order to objectively evaluate the experience of an applicant (a project organization and the quality of a design product (project documentation. The methodology to be developed is based on introduction of new evaluation criteria (sub-criteria that in conjunction with the applicable criteria specified by the Law on the Contract System will allow developing the optimal procedure to evaluate competitive bids of the participants in tenders and determining the most appropriate candidate, with whom the contract will be further concluded. The article analyzes the existing criteria and their interaction with each other and describes the specifics of tenders for design in the form of open competition. The list decreases to three criteria, such as "contract price", "quality, functional and environmental characteristics of a procurement facility", "qualification of procurement participants, including availability of financial resources, equipment and other material resources necessary for the execution of the contract material resources, the presence of goodwill, professionals and other employees of a certain experience level". However, in order to upgrade the quality of assurance procedures for the design works to be performed, it was decided to apply new evaluation criteria (sub-criteria components, such as "availability of positive findings of the state out-of-departmental examination that are similar to the subject of competition, on a participant in placement of order", "availability of the certificate on approval of architectural and urban planning decisions that are similar to the subject of competition, on a participant in placement of order", "availability of the permit for the commissioning of facilities that are similar to the subject of competition, on a participant in placement of order", "availability of the contract for designer's supervision with a participant in placement of
Human factors engineering design review acceptance criteria for the safety parameter display

International Nuclear Information System (INIS)

McGevna, V.; Peterson, L.R.

1981-01-01

This report contains human factors engineering design review acceptance criteria developed by the Human Factors Engineering Branch (HFEB) of the Nuclear Regulatory Commission (NRC) to use in evaluating designs of the Safety Parameter Display System (SPDS). These criteria were developed in response to the functional design criteria for the SPDS defined in NUREG-0696, Functional Criteria for Emergency Response Facilities. The purpose of this report is to identify design review acceptance criteria for the SPDS installed in the control room of a nuclear power plant. Use of computer driven cathode ray tube (CRT) displays is anticipated. General acceptance criteria for displays of plant safety status information by the SPDS are developed. In addition, specific SPDS review criteria corresponding to the SPDS functional criteria specified in NUREG-0696 are established
Research on high level radioactive waste repository seismic design criteria

International Nuclear Information System (INIS)

Jing Xu

2012-01-01

Review seismic hazard analysis principle and method in site suitable assessment process of Yucca Mountain Project, and seismic design criteria and seismic design basis in primary design process. Demonstrated spatial character of seismic hazard by calculated regional seismic hazard map. Contrasted different level seismic design basis to show their differences and relation. Discussed seismic design criteria for preclosure phrase of high level waste repository and preference goal under beyond design basis ground motion. (author)
Seismic design criteria for the system 80+ advanced light water reactor

International Nuclear Information System (INIS)

Manrique, M.A.; Dermitzakis, S.N.; Gerdes, L.D.; Kennedy, R.P.; Idriss, I.M.; Cassidy, J.R.

1991-01-01

This paper presents the development of seismic design criteria in support of design certification by the Nuclear Regulatory Commission (NRC) of the ABB-Combustion Engineering's System 80+ Standard Design. The design certification effort is sponsored by the US Department of Energy (DOE). The development of the design criteria included: (a) development of the seismic control motion, (b) development of generic soil profiles for anticipated sites, (c) generation of in-structure response spectra and design loads for structures and equipment through soil-structure interaction (SSI) analyses, and (d) acceptance criteria for future construction sites
Recommendations for Glass Durability Test Criteria

International Nuclear Information System (INIS)

Strachan, D.M.

1999-01-01

The objective of this short report is to define a set of activities that should lead to a specification for a test that can be used as one of the acceptance criteria and as an indicator of acceptable long-term behavior in contact with water. Since the glass composition is not yet defined and is likely to change as the composition of the waste changes, a strategy for developing criteria for what is acceptable involves a series of tests and modeling activities. The results of these activities lead to a criterion for an acceptable product and the data that are needed to reliably determine the behavior of the glass in the storage environment
Considerations for developing seismic design criteria for nuclear waste storage repositories

International Nuclear Information System (INIS)

Owen, G.N.; Yanev, P.I.; Scholl, R.E.

1980-04-01

The function of seismic design criteria is to reduce the potential for hazards that may arise during various stages of the repository life. During the operational phase, the major concern is with the possible effects of earthquakes on surface facilities, underground facilities, and equipment. During the decommissioned phase, the major concern is with the potential effects of earthquakes on the geologic formation, which may result in a reduction in isolation capacity. Existing standards and guides or criteria used for the static and seismic design of licensed nuclear facilities were reviewed and evaluated for their applicability to repository design. This report is directed mainly toward the development of seismic design criteria for the underground structures of repositories. An initial step in the development of seismic design criteria for the underground structures of repositories is the development of performance criteria, or minimum standards of acceptable behavior. A number of possible damage modes are identified for the operating phase of the repository; however, no damage modes are foreseen that would perturb the long-term function of the repository, except for the possibility of increased permeability within the rock mass. Subsequent steps in formulating acceptable seismic design criteria for the underground structures involve the quantification of the design process. The report discusses the necessity of specifying the form of ground motion that would be needed for seismic analysis and the procedures that may be used for making ground motion predictions. Further discussions outline what is needed for analysis, including rock properties, failure criteria, modeling techniques, seismic hardening criteria for the host rock mass, and probabilistic considerations
Optimal testlet pool assembly for multistage testing designs

NARCIS (Netherlands)

Ariel, A.; Veldkamp, Bernard P.; Breithaupt, Krista

2006-01-01

Computerized multistage testing (MST) designs require sets of test questions (testlets) to be assembled to meet strict, often competing criteria. Rules that govern testlet assembly may dictate the number of questions on a particular subject or may describe desirable statistical properties for the
Design criteria for the light duty utility arm system end effectors

International Nuclear Information System (INIS)

Pardini, A.F.; Kiebel, G.R.

1995-12-01

The purpose of this document is to provide criteria for the design of end effectors that will be used as part of the Light Duty Utility Arm (LDUA) System. Actual component design, fabrication, testing, and inspection will be performed by various DOE laboratories, industry, and academia. This document augments WHC-SD-TD-FRD-003, 'Functions and Requirements for the Light Duty Utility Arm Integrated System' (F). All requirements dictated in the F shall also be applicable in this document. Whenever conflicts arise between this document and the F, this document shall take precedence
Safety principles and design criteria for nuclear power stations

International Nuclear Information System (INIS)

Gazit, M.

1982-01-01

The criteria and safety principles for the design of nuclear power stations are presented from the viewpoint of a nuclear engineer. The design, construction and operation of nuclear power stations should be carried out according to these criteria and safety principles to ensure, to a reasonable degree, that the likelihood of release of radioactivity as a result of component failure or human error should be minimized. (author)
Criteria design of the CAREM 25 reactor's core: neutronic aspects

International Nuclear Information System (INIS)

Lecot, C.A.

1990-01-01

The criteria that guided the design, from the neutronic point of view, of the CAREM reactor's core were presented. The minimum set of objectives and general criteria which permitted the design of the particular systems constituting the CAREM 25 reactor's core is detailed and stated. (Author) [es
Development of design Criteria for ITER In-vessel Components

International Nuclear Information System (INIS)

Sannazzaro, G.; Barabash, V.; Kang, S.C.; Fernandez, E.; Kalinin, G.; Obushev, A.; Martínez, V.J.; Vázquez, I.; Fernández, F.; Guirao, J.

2013-01-01

Absrtract: The components located inside the ITER vacuum chamber (in-vessel components – IC), due to their specific nature and the environments they are exposed to (neutron radiation, high heat fluxes, electromagnetic forces, etc.), have specific design criteria which are, in this paper, referred as Structural Design Criteria for In-vessel Components (SDC-IC). The development of these criteria started in the very early phase of the ITER design and followed closely the criteria of the RCC-MR code. Specific rules to include the effect of neutron irradiation were implemented. In 2008 the need of an update of the SDC-IC was identified to add missing specifications, to implement improvements, to modernise rules including recent evolutions in international codes and regulations (i.e. PED). Collaboration was set up between ITER Organization (IO), European (EUDA) and Russian Federation (RFDA) Domestic Agencies to generate a new version of SDC-IC. A Peer Review Group (PRG) composed by members of the ITER Organization and all ITER Domestic Agencies and code experts was set-up to review the proposed modifications, to provide comments, contributions and recommendations
Biomonitoring test procedures and biological criteria

Energy Technology Data Exchange (ETDEWEB)

Kszos, L.A. [Oak Ridge National Lab., TN (United States); Lipschultz, M.J. [City of Las Vegas, NV (United States); Foster, W.E. [Saint Mary`s Coll., Winona, MN (United States)

1997-10-01

The Water Environment Federation recently issued a special publication, Biomonitoring in the Water Environment. In this paper, the authors highlight the contents of the chapter 3, Biomonitoring Test Procedures, identify current trends in test procedures and introduce the concept of biological criteria (biocriteria). The book chapter (and this paper) focuses on freshwater and marine chronic and acute toxicity tests used in the National Pollutant Discharge Elimination System (NPDES) permits program to identify effluents and receiving waters containing toxic materials in acutely or chronically toxic concentrations. The two major categories of toxicity tests include acute tests and chronic tests. The USEPA chronic tests required in NPDEs permits have been shortened to 7 days by focusing on the most sensitive life-cycle stages; these tests are often referred to as short-term chronic tests. The type of test(s) required depend on NPDES permit requirements, objectives of the test, available resources, requirements of the test organisms, and effluent characteristics such as variability in flow or toxicity. The permit writer will determine the requirements for toxicity test(s) by considering such factors as dilution, effluent variability, and exposure variability. Whether the required test is acute or chronic, the objective of the test is to estimate the safe or no effect concentration which is defined as the concentration which will permit normal propagation of fish and other aquatic life in the receiving waters. In this paper, the authors review the types of toxicity tests, the commonly used test organisms, and the uses of toxicity test data. In addition, they briefly describe research on new methods and the use of biological criteria.
Safety objectives and design criteria for the NHR-200

International Nuclear Information System (INIS)

Xue Dazhi; Zheng Wenxiang

1997-01-01

The construction of a nuclear district heating reactor (NHR) demonstration plant with a thermal power of 200 MW has been decided for the northeast of China. To facilitate the design and licensability a set of design criteria were developed for the NHR, based on existing general criteria for NPP but amended with regard to the unique features of NHR-200. Some key points are discussed in this paper. (author). 7 refs
Safety objectives and design criteria for the NHR-200

Energy Technology Data Exchange (ETDEWEB)

Dazhi, Xue; Wenxiang, Zheng [Institute of Nuclear Energy and Technology, Tsingua Univ., Beijing (China)

1997-09-01

The construction of a nuclear district heating reactor (NHR) demonstration plant with a thermal power of 200 MW has been decided for the northeast of China. To facilitate the design and licensability a set of design criteria were developed for the NHR, based on existing general criteria for NPP but amended with regard to the unique features of NHR-200. Some key points are discussed in this paper. (author). 7 refs.
Common Risk Criteria Standards for National Test Ranges

Science.gov (United States)

2016-08-01

supplemental) document to RCC Document 321. a. Modified aircraft vulnerability criteria for business class jets. b. Modified the aircraft vulnerability... successful , the logical relationships among criteria used at the test ranges and across different hazards are often difficult to comprehend. The...provides a common set of range safety policies, risk criteria, and guidelines for managing risk to people and assets during manned and unmanned

Evaluation criteria for spectral design of camouflage

Science.gov (United States)

Škerlind, Christina; Fagerström, Jan; Hallberg, Tomas; Kariis, Hans

2015-10-01

In development of visual (VIS) and infrared (IR) camouflage for signature management, the aim is the design of surface properties of an object to spectrally match or adapt to a background and thereby minimizing the contrast perceived by a threatening sensor. The so called 'ladder model" relates the requirements for task measure of effectiveness with surface structure properties through the steps signature effectiveness and object signature. It is intended to link materials properties via platform signature to military utility and vice versa. Spectral design of a surface intends to give it a desired wavelength dependent optical response to fit a specific application of interest. Six evaluation criteria were stated, with the aim to aid the process to put requirement on camouflage and for evaluation. The six criteria correspond to properties such as reflectance, gloss, emissivity, and degree of polarization as well as dynamic properties, and broadband or multispectral properties. These criteria have previously been exemplified on different kinds of materials and investigated separately. Anderson and Åkerlind further point out that the six criteria rarely were considered or described all together in one and same publication previously. The specific level of requirement of the different properties must be specified individually for each specific situation and environment to minimize the contrast between target and a background. The criteria or properties are not totally independent of one another. How they are correlated is part of the theme of this paper. However, prioritization has been made due to the limit of space. Therefore all of the interconnections between the six criteria will not be considered in the work of this report. The ladder step previous to digging into the different material composition possibilities and choice of suitable materials and structures (not covered here), includes the object signature and decision of what the spectral response should be
Nevada Test Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2005-01-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal
Failsafe design criteria for computer based reactor protection systems

International Nuclear Information System (INIS)

Keats, A.B.

1980-01-01

The design criteria proposed are an extrapolation of the failsafe mode of operation used in the UK in hardwired reactor protection systems. This is achieved by making the operational condition of the reactor dependent upon an energetic state of the protection system components. An important objective of the proposed design criteria is to eliminate, or at least to minimize, the need for a failure-mode-and-effect-analysis (FMEA) of the computer software. This demands some well defined but simple constraints upon the way in which data are stored in the computers, but the objective is achieved almost entirely by hardware properties of the system. The first of these is the systematic use of hardwired test inputs which cause transient excursions into the tripped state in a uniquely ordered but easily recognizable sequence. The second is the use of hardwired pattern recognition logic which generates a dynamic healthy stimulus for the shutdown actuators only in response to the unique sequence formed by the hardwired input signal pattern. It therefore detects abnormal states of any of the system inputs, software errors, wiring errors and hardware failures. This hardwired logic is conceptually simple, failsafe, and is amenable to simple FMEA. (U.K.)
NASA reliability preferred practices for design and test

Science.gov (United States)

1991-01-01

Given here is a manual that was produced to communicate within the aerospace community design practices that have contributed to NASA mission success. The information represents the best technical advice that NASA has to offer on reliability design and test practices. Topics covered include reliability practices, including design criteria, test procedures, and analytical techniques that have been applied to previous space flight programs; and reliability guidelines, including techniques currently applied to space flight projects, where sufficient information exists to certify that the technique will contribute to mission success.
Proposed waste form performance criteria and testing methods for low-level mixed waste

International Nuclear Information System (INIS)

Franz, E.M.; Fuhrmann, M.; Bowerman, B.

1995-01-01

Proposed waste form performance criteria and testing methods were developed as guidance in judging the suitability of solidified waste as a physico-chemical barrier to releases of radionuclides and RCRA regulated hazardous components. The criteria follow from the assumption that release of contaminants by leaching is the single most important property for judging the effectiveness of a waste form. A two-tier regimen is proposed. The first tier consists of a leach test designed to determine the net, forward leach rate of the solidified waste and a leach test required by the Environmental Protection Agency (EPA). The second tier of tests is to determine if a set of stresses (i.e., radiation, freeze-thaw, wet-dry cycling) on the waste form adversely impacts its ability to retain contaminants and remain physically intact. In the absence of site-specific performance assessments (PA), two generic modeling exercises are described which were used to calculate proposed acceptable leachates
46 CFR 154.460 - Design criteria.

Science.gov (United States)

2010-10-01

... GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) CERTAIN BULK DANGEROUS CARGOES SAFETY STANDARDS FOR... Barrier § 154.460 Design criteria. At static angles of heel up through 30°, a secondary barrier must (a) If a complete secondary barrier is required in § 154.459, hold all of the liquid cargo in the cargo...
SEISMIC DESIGN CRITERIA FOR NUCLEAR POWER REACTORS

Energy Technology Data Exchange (ETDEWEB)

Williamson, R. A.

1963-10-15

The nature of nuclear power reactors demands an exceptionally high degree of seismic integrity. Considerations involved in defining earthquake resistance requirements are discussed. Examples of seismic design criteria and applications of the spectrum technique are described. (auth)
VDTT removal system functional design criteria

International Nuclear Information System (INIS)

Legare, D.E.

1996-01-01

Two Velocity Density Temperature Trees (H-2-815016) are to be removed from risers 14A and 1B of tank 241-SY-101. This document provides functional design criteria for the removal system. The removal system consists of a Liquid Removal Tool, Flexible Receiver (H-2-79216), Burial Container, Transport Trailers, and associated equipment
Design criteria and pressure vessel codes - an American view

International Nuclear Information System (INIS)

Tuppeny, W.H.

1975-01-01

To the pressure vessel designer, codes and criteria represent the common ground where the stress analyst and the metallurgist must interact and evolve rules and procedures which will ensure safety and open-ended responsiveness to technological, economic, and environmental change. The paper briefly discusses the evolution and rationale behind the current ASME code sections -emphasizing those portions applicable to designs operating in the creep range. The author then proposes a plan of action so that the analysts and materials people can make optimum use of time and resources, and evolve data and design criteria which will be responsive to changing technology and the economic and safety requirements of the future. (author)
Multi-material topology design of laminates with strength criteria

DEFF Research Database (Denmark)

Lund, Erik

2012-01-01

The objective of this paper is to present a novel approach for multi-material topology optimization of laminated composite structures where strength constraints are taken into account together with other global structural performance measures. The topology design problem considered contains very...... many design variables, and when strength criteria are included in the problem, a very large number of criteria functions must be considered in the optimization problem to be solved. Thus, block aggregation methods are introduced, such that global strength measures are obtained. These formulations...... are illustrated for multi-material laminated design problems where the maximum failure index is minimized while compliance and mass constraints are taken into account....
Test-based approach to cable tray support system analysis and design: Behavior and test methods

Energy Technology Data Exchange (ETDEWEB)

Reigles, Damon G., E-mail: dreigles@engnovex.com [engNoveX, Inc., 19C Trolley Square, Wilmington, DE 19806 (United States); Brachmann, Ingo; Johnson, William H. [Bechtel Nuclear, Security & Environmental, 12011 Sunset Hills Rd, Suite 110, Reston, VA 20190 (United States); Gürbüz, Orhan [Tobolski Watkins Engineering, Inc., 4125 Sorrento Valley Blvd, Suite B, San Diego, CA 92121 (United States)

2016-06-15

Highlights: • Describes dynamic response behavior of unistrut type cable tray supports. • Summarizes observations from past full-scale shake table test programs. • Outlines testing methodologies necessary to identify key system parameters. - Abstract: Nuclear power plant safety-related cable tray support systems subjected to seismic loadings were originally understood and designed to behave as linear elastic systems. This behavioral paradigm persisted until the early 1980s when, due to evolution of regulatory criteria, some as-installed systems needed to be qualified to higher seismic motions than originally designed for. This requirement prompted a more in-depth consideration of the true seismic response behavior of support systems. Several utilities initiated extensive test programs, which demonstrated that trapeze strut-type cable tray support systems exhibited inelastic and nonlinear response behaviors with plastic hinging at the connections together with high damping due to bouncing of cables in the trays. These observations were used to demonstrate and justify the seismic adequacy of the aforementioned as-installed systems. However, no formalized design methodology or criteria were ever established to facilitate use of these test data for future evaluations. This paper assimilates and reviews the various test data and conclusions for the purpose of developing a design methodology for the seismic qualification of safety-related cable tray support systems.
Packaging design criteria for the MCO cask

International Nuclear Information System (INIS)

Edwards, W.S.

1996-01-01

Approximately 2,100 metric tons of unprocessed, irradiated nuclear fuel elements are presently stored in the K Basins (including possibly 700 additional elements from PUREX, N Reactor, and 327 Laboratory). The basin water, particularly in the K East Basin, contains significant quantities of dissolved nuclear isotopes and radioactive fuel corrosion particles. To permit cleanup of the K Basins and fuel conditioning, the fuel will be transported from the 100 K Area to a Canister Storage Building (CSB) in the 200 East area. In order to initiate K Basin cleanup on schedule, the two-year fuel-shipping campaign must begin by December 1997. The purpose of this packaging design criteria is to provide criteria for the design, fabrication, and use of a packaging system to transport the large quantities of irradiated nuclear fuel elements positioned within Multiple Canister Overpacks
Packaging Design Criteria for the MCO Cask

International Nuclear Information System (INIS)

FLANAGAN, B.D.

2000-01-01

Approximately 2,100 metric tons of unprocessed, irradiated, nuclear fuel elements are presently stored in the K Basins (including approximately 700 additional elements from the Plutonium-Uranium Extraction Plant, N Reactor, and 327 Laboratory). To permit cleanup of the K Basins and fuel conditioning, the fuel will be transported from the 100 K Area to a Canister Storage Building (CSB) in the 200 East Area. The purpose of this packaging design criteria is to provide criteria for the design, fabrication, and use of a packaging system to transport the large quantities of irradiated nuclear fuel elements positioned within Multi-canister Overpacks. Concurrent with the K Basin cleanup, 72 Shippingport Pressurized Water Reactor Core 2 fuel assemblies will be transported from T Plant to the CSB to provide space at T Plant for K Basin sludge canisters
Optimal design criteria - prediction vs. parameter estimation

Science.gov (United States)

Waldl, Helmut

2014-05-01

G-optimality is a popular design criterion for optimal prediction, it tries to minimize the kriging variance over the whole design region. A G-optimal design minimizes the maximum variance of all predicted values. If we use kriging methods for prediction it is self-evident to use the kriging variance as a measure of uncertainty for the estimates. Though the computation of the kriging variance and even more the computation of the empirical kriging variance is computationally very costly and finding the maximum kriging variance in high-dimensional regions can be time demanding such that we cannot really find the G-optimal design with nowadays available computer equipment in practice. We cannot always avoid this problem by using space-filling designs because small designs that minimize the empirical kriging variance are often non-space-filling. D-optimality is the design criterion related to parameter estimation. A D-optimal design maximizes the determinant of the information matrix of the estimates. D-optimality in terms of trend parameter estimation and D-optimality in terms of covariance parameter estimation yield basically different designs. The Pareto frontier of these two competing determinant criteria corresponds with designs that perform well under both criteria. Under certain conditions searching the G-optimal design on the above Pareto frontier yields almost as good results as searching the G-optimal design in the whole design region. In doing so the maximum of the empirical kriging variance has to be computed only a few times though. The method is demonstrated by means of a computer simulation experiment based on data provided by the Belgian institute Management Unit of the North Sea Mathematical Models (MUMM) that describe the evolution of inorganic and organic carbon and nutrients, phytoplankton, bacteria and zooplankton in the Southern Bight of the North Sea.
Natural phenomena hazards design and evaluation criteria for Department of Energy Facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-01-01

The Department of Energy (DOE) has issued an Order 420.1 which establishes policy for its facilities in the event of natural phenomena hazards (NPH) along with associated NPH mitigation requirements. This DOE Standard gives design and evaluation criteria for NPH effects as guidance for implementing the NPH mitigation requirements of DOE Order 420.1 and the associated implementation Guides. These are intended to be consistent design and evaluation criteria for protection against natural phenomena hazards at DOE sites throughout the United States. The goal of these criteria is to assure that DOE facilities can withstand the effects of natural phenomena such as earthquakes, extreme winds, tornadoes, and flooding. These criteria apply to the design of new facilities and the evaluation of existing facilities. They may also be used for modification and upgrading of existing facilities as appropriate. The design and evaluation criteria presented herein control the level of conservatism introduced in the design/evaluation process such that earthquake, wind, and flood hazards are treated on a consistent basis. These criteria also employ a graded approach to ensure that the level of conservatism and rigor in design/evaluation is appropriate for facility characteristics such as importance, hazards to people on and off site, and threat to the environment. For each natural phenomena hazard covered, these criteria consist of the following: Performance Categories and target performance goals as specified in the DOE Order 420.1 NPH Implementation Guide, and DOE-STD-1 021; specified probability levels from which natural phenomena hazard loading on structures, equipment, and systems is developed; and design and evaluation procedures to evaluate response to NPH loads and criteria to assess whether or not computed response is permissible.
Development and implementation of the TPX structural and cryogenic design criteria

International Nuclear Information System (INIS)

Zatz, I.; Heitzenroeder, P.; Schultz, J.H.

1993-01-01

The Tokamak Physics Experiment (TPX) is a superconducting tokamak utilizing both Nb 3 Sn and NbTi superconducting magnets and will feature a low-activation titanium alloy vacuum vessel and carbon-carbon composite divertors. Due to the unique nature of the component designs, materials, and environment, the TPX project felt it necessary to develop a design criteria (code) which will specifically address the structural and cryogenic design aspects of such a device. The developed code is intended to serve all components of the device; namely, the TF and PF magnets, vacuum vessel, first wall and divertor, cryostat, diagnostics, heating devices, shielding, and all associated structural elements. The structural portion is based largely on that developed for the Burning Plasma Experiment (BPX), which was modeled after the CIT Vacuum Vessel Structural Design Criteria and ASME Boiler and Pressure Vessel (B ampersand PV) Code. The cryogenic criteria is largely modeled after that proposed in the ITER CDA. This paper summarizes the TPX Criteria document
Nevada Test Site Waste Acceptance Criteria (NTSWAC)

Energy Technology Data Exchange (ETDEWEB)

NNSA/NSO Waste Management Project

2008-06-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.
Nevada Test Site Waste Acceptance Criteria (NTSWAC)

International Nuclear Information System (INIS)

NNSA/NSO Waste Management Project

2008-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal
Mechanical modelling of SiC/SiC composites and design criteria

International Nuclear Information System (INIS)

Bernachy, F.; Gélébart, L.; Crépin, J.; Bornert, M.

2013-01-01

Outcomes and perspectives: • Definition of damage criteria, easy to measure and reproducible: → Useful for design purposes. • Results about the biaxial mechanical behavior of the tubes: → Construction and identification of a damage model. • Measurement of elastic properties in good agreement with multiscale simulations: → Non-linear behavior has still to be adressed using a multiscale approach. Possible strategies: - Building of a 3D homogeneous damage model of the tow; - Simulation of the initiation and propagation of cracks through the composite. • More experimental results coming to address several issues: → Non proportional tests (complex loading paths): - Investigation of crack opening/closure mechanism. → Tension-internal pressure tests: - Mechanical properties along the orthoradial direction; → Tests on other microstructures (braiding and winding angles); → Bending tests: - Test of the mechanical model and close to industrial issues
36 CFR 212.55 - Criteria for designation of roads, trails, and areas.

Science.gov (United States)

2010-07-01

... roads, trails, and areas. 212.55 Section 212.55 Parks, Forests, and Public Property FOREST SERVICE, DEPARTMENT OF AGRICULTURE TRAVEL MANAGEMENT Designation of Roads, Trails, and Areas for Motor Vehicle Use § 212.55 Criteria for designation of roads, trails, and areas. (a) General criteria for designation of...

Seismic design and evaluation criteria for DOE facilities (DOE-STD-1020-XX)

International Nuclear Information System (INIS)

Short, S.A.; Kennedy, R.P.; Murray, R.C.

1993-01-01

Seismic design and evaluation criteria for DOE facilities are provided in DOE-STD-1020-XX. The criteria include selection of design/evaluation seismic input from probabilistic seismic hazard curves combined with commonly practiced deterministic response evaluation methods and acceptance criteria with controlled levels of conservatism. Conservatism is intentionally introduced in specification of material strengths and capacities, in the allowance of limited inelastic behavior and by a seismic load factor. These criteria are based on the performance or risk goals specified in DOE 5480.28. Criteria have been developed following a graded approach for several performance goals ranging from that appropriate for normal-use facilities to that appropriate for facilities involving hazardous or critical operations. Performance goals are comprised of desired behavior and of the probability of not achieving that behavior. Following the seismic design/evaluation criteria of DOE-STD-1020-XX is sufficient to demonstrate that the probabilistic performance or risk goals are achieved. The criteria are simple procedures but with a sound, rigorous basis for the achievement of goals
Establishing seismic design criteria to achieve an acceptable seismic margin

International Nuclear Information System (INIS)

Kennedy, R.P.

1997-01-01

In order to develop a risk based seismic design criteria the following four issues must be addressed: (1) What target annual probability of seismic induced unacceptable performance is acceptable? (2). What minimum seismic margin is acceptable? (3) Given the decisions made under Issues 1 and 2, at what annual frequency of exceedance should the Safe Shutdown Earthquake ground motion be defined? (4) What seismic design criteria should be established to reasonably achieve the seismic margin defined under Issue 2? The first issue is purely a policy decision and is not addressed in this paper. Each of the other three issues are addressed. Issues 2 and 3 are integrally tied together so that a very large number of possible combinations of responses to these two issues can be used to achieve the target goal defined under Issue 1. Section 2 lays out a combined approach to these two issues and presents three potentially attractive combined resolutions of these two issues which reasonably achieves the target goal. The remainder of the paper discusses an approach which can be used to develop seismic design criteria aimed at achieving the desired seismic margin defined in resolution of Issue 2. Suggestions for revising existing seismic design criteria to more consistently achieve the desired seismic margin are presented
Durability-Based Design Criteria for a Chopped-Glass-Fiber Automotive Structural Composite; TOPICAL

International Nuclear Information System (INIS)

Battiste, R.L.; Corum, J.M.; Ren, W.; Ruggles, M.B.

1999-01-01

This report provides recommended durability-based design criteria for a chopped-glass-fiber reinforced polymeric composite for automotive structural applications. The criteria closely follow the framework of an earlier criteria document for a continuous-strand-mat (CSM) glass-fiber reference composite. Together these design criteria demonstrate a framework that can be adapted for future random-glass-fiber composites for automotive structural applications
Two non-tracking solar collectors: Design criteria and performance analysis

International Nuclear Information System (INIS)

Ratismith, Wattana; Inthongkhum, Anusorn; Briggs, John

2014-01-01

Highlights: • A collector module designed to capture solar radiation efficiently is proposed. • Two different compound parabolic trough designs are examined and tested. • A novel design with a flat base trough and vertical absorber operates efficiently in direct and diffuse sunlight. - Abstract: We propose fixed (non-tracking) configurations of solar light collector modules which are designed to operate efficiently throughout the day, i.e. for varying incident angles of direct sunlight, and in conditions of diffuse solar irradiation. We present two trough designs of compound parabolic collector (CPC) type. One, a more conventional double-parabolic trough, has the absorber plate perpendicular to the vertical axis of the trough cross-section. The other, of a new flat-base shape, has the absorber plate parallel. The collectors have two novel features appropriate to non-tracking. The first is a smoothing of the power output over the day by the simple expedient of arranging three troughs tilted at different angles. The second is the original design of the flat-base trough allowing optimal interception of the caustic surfaces of this non-focussing device. By ray-tracing analysis of the different trough shapes and absorber plate orientation, we emphasise the design criteria for achievement of a high intercept factor throughout the day without tracking and demonstrate the superiority of the flat-base collector over the double-parabolic design. In test experiments we show that the high temperatures (≈180 °C) necessary for some industrial process heat applications can be achieved. Also test results of the efficiency of the proposed systems are presented which indicate that the flat-base trough with vertical absorber plate is superior to the double-parabolic trough with horizontal absorber plate
Multivariant design and multiple criteria analysis of building refurbishments

Energy Technology Data Exchange (ETDEWEB)

Kaklauskas, A.; Zavadskas, E. K.; Raslanas, S. [Faculty of Civil Engineering, Vilnius Gediminas Technical University, Vilnius (Lithuania)

2005-07-01

In order to design and realize an efficient building refurbishment, it is necessary to carry out an exhaustive investigation of all solutions that form it. The efficiency level of the considered building's refurbishment depends on a great many of factors, including: cost of refurbishment, annual fuel economy after refurbishment, tentative pay-back time, harmfulness to health of the materials used, aesthetics, maintenance properties, functionality, comfort, sound insulation and longevity, etc. Solutions of an alternative character allow for a more rational and realistic assessment of economic, ecological, legislative, climatic, social and political conditions, traditions and for better the satisfaction of customer requirements. They also enable one to cut down on refurbishment costs. In carrying out the multivariant design and multiple criteria analysis of a building refurbishment much data was processed and evaluated. Feasible alternatives could be as many as 100,000. How to perform a multivariant design and multiple criteria analysis of alternate alternatives based on the enormous amount of information became the problem. Method of multivariant design and multiple criteria of a building refurbishment's analysis were developed by the authors to solve the above problems. In order to demonstrate the developed method, a practical example is presented in this paper. (author)
Canberra Alpha Sentry Installation Functional Design Criteria (FDC)

International Nuclear Information System (INIS)

WHITE, W.F.

1999-01-01

This document provides the functional design criteria for the installation of the Canberra Alpha Sentry System at selected locations within the Plutonium Finishing Plant (PFP). The equipment being installed is identified by part number in Section 3 and the locations are given in Section 5. The design, procurement and installation are assigned to Fluor Federal Services
On the construction of experimental designs for a given task by jointly optimizing several quality criteria: Pareto-optimal experimental designs.

Science.gov (United States)

Sánchez, M S; Sarabia, L A; Ortiz, M C

2012-11-19

Experimental designs for a given task should be selected on the base of the problem being solved and of some criteria that measure their quality. There are several such criteria because there are several aspects to be taken into account when making a choice. The most used criteria are probably the so-called alphabetical optimality criteria (for example, the A-, E-, and D-criteria related to the joint estimation of the coefficients, or the I- and G-criteria related to the prediction variance). Selecting a proper design to solve a problem implies finding a balance among these several criteria that measure the performance of the design in different aspects. Technically this is a problem of multi-criteria optimization, which can be tackled from different views. The approach presented here addresses the problem in its real vector nature, so that ad hoc experimental designs are generated with an algorithm based on evolutionary algorithms to find the Pareto-optimal front. There is not theoretical limit to the number of criteria that can be studied and, contrary to other approaches, no just one experimental design is computed but a set of experimental designs all of them with the property of being Pareto-optimal in the criteria needed by the user. Besides, the use of an evolutionary algorithm makes it possible to search in both continuous and discrete domains and avoid the need of having a set of candidate points, usual in exchange algorithms. Copyright © 2012 Elsevier B.V. All rights reserved.
Recommended revisions to Nuclear Regulatory Commission seismic design criteria. Technical report

International Nuclear Information System (INIS)

Coats, D.W.

1980-05-01

This report recommends changes in the Nuclear Regulatory Commission's (NRC's) criteria now used in the seismic design of nuclear power plants. Areas covered include ground motion, soil-structure interaction, structures, and equipment and components. Members of the Engineering Mechanics Section of the Nuclear Test Engineering Division at Lawrence Livermore Laboratory (LLL) generally agreed upon the recommendations, which are based on (1) reports developed under the NRC's Task Action Plan A-40, (2) other available engineering literature, and (3) recommendations of nationally recognized experts retained by LLL specifically for this task
2D Decision-Making for Multi-Criteria Design Optimization

National Research Council Canada - National Science Library

Engau, A; Wiecek, M. M

2006-01-01

The high dimensionality encountered in engineering design optimization due to large numbers of performance criteria and specifications leads to cumbersome and sometimes unachievable tradeoff analyses...
The Insulation for Machines Having a High Lifespan Expectancy, Design, Tests and Acceptance Criteria Issues

Directory of Open Access Journals (Sweden)

Olivier Barré

2017-02-01

Full Text Available The windings insulation of electrical machines will remain a topic that is updated frequently. The criteria severity requested by the electrical machine applications increases continuously. Manufacturers and designers are always confronted with new requirements or new criteria with enhanced performances. The most problematic requirements that will be investigated here are the extremely long lifespan coupled to critical operating conditions (overload, supply grid instabilities, and critical operating environments. Increasing lifespan does not have a considerable benefit because the purchasing price of usual machines has to be compared to the purchasing price and maintenance price of long lifespan machines. A machine having a 40-year lifespan will cost more than twice the usual price of a 20-year lifetime machine. Systems which need a long lifetime are systems which are crucial for a country, and those for which outage costs are exorbitant. Nuclear power stations are such systems. It is certain that the used technologies have evolved since the first nuclear power plant, but they cannot evolve as quickly as in other sectors of activities. No-one wants to use an immature technology in such power plants. Even if the electrical machines have exceeded 100 years of age, their improvements are linked to a patient and continuous work. Nowadays, the windings insulation systems have a well-established structure, especially high voltage windings. Unfortunately, a high life span is not only linked to this result. Several manufacturers’ improvements induced by many years of experiment have led to the writing of standards that help the customers and the manufacturers to regularly enhance the insulation specifications or qualifications. Hence, in this publication, the authors will give a step by step exhaustive review of one insulation layout and will take time to give a detailed report on the standards that are linked to insulation systems. No standard can
Justification of disintegration testing beyond current FDA criteria using in vitro and in silico models

Directory of Open Access Journals (Sweden)

Uebbing L

2017-04-01

Full Text Available Lukas Uebbing,1,2,* Lukas Klumpp,1,3,* Gregory K Webster,4 Raimar Löbenberg1 1Faculty of Pharmacy and Pharmaceutical Sciences, Katz Group-Rexall Centre for Pharmacy and Health Research, University of Alberta, Edmonton, Canada; 2Institute of Pharmacy and Biochemistry, Johannes Gutenberg University, Mainz, 3Institute of Pharmaceutical Technology, Goethe University Frankfurt, Frankfurt, Germany; 4Global Research and Development, AbbVie Inc., North Chicago, IL, USA *These authors contributed equally to this work Abstract: Drug product performance testing is an important part of quality-by-design approaches, but this process often lacks the underlying mechanistic understanding of the complex interactions between the disintegration and dissolution processes involved. Whereas a recent draft guideline by the US Food and Drug Administration (FDA has allowed the replacement of dissolution testing with disintegration testing, the mentioned criteria are not globally accepted. This study provides scientific justification for using disintegration testing rather than dissolution testing as a quality control method for certain immediate release (IR formulations. A mechanistic approach, which is beyond the current FDA criteria, is presented. Dissolution testing via United States Pharmacopeial Convention Apparatus II at various paddle speeds was performed for immediate and extended release formulations of metronidazole. Dissolution profile fitting via DDSolver and dissolution profile predictions via DDDPlus™ were performed. The results showed that Fickian diffusion and drug particle properties (DPP were responsible for the dissolution of the IR tablets, and that formulation factors (eg, coning impacted dissolution only at lower rotation speeds. Dissolution was completely formulation controlled if extended release tablets were tested and DPP were not important. To demonstrate that disintegration is the most important dosage form attribute when dissolution is
Advanced composite structures. [metal matrix composites - structural design criteria for spacecraft construction materials

Science.gov (United States)

1974-01-01

A monograph is presented which establishes structural design criteria and recommends practices to ensure the design of sound composite structures, including composite-reinforced metal structures. (It does not discuss design criteria for fiber-glass composites and such advanced composite materials as beryllium wire or sapphire whiskers in a matrix material.) Although the criteria were developed for aircraft applications, they are general enough to be applicable to space vehicles and missiles as well. The monograph covers four broad areas: (1) materials, (2) design, (3) fracture control, and (4) design verification. The materials portion deals with such subjects as material system design, material design levels, and material characterization. The design portion includes panel, shell, and joint design, applied loads, internal loads, design factors, reliability, and maintainability. Fracture control includes such items as stress concentrations, service-life philosophy, and the management plan for control of fracture-related aspects of structural design using composite materials. Design verification discusses ways to prove flightworthiness.
Design criteria document, electrical system, K-Basin essential systems recovery, Project W-405

International Nuclear Information System (INIS)

Hoyle, J.R.

1994-01-01

This Design Criteria Document provides the criteria for design and construction of electrical system modifications for 100K Area that are essential to protect the safe operation and storage of spent nuclear fuel in the K-Basin facilities
Design criteria for the structural analysis of shipping cask containment vessels

International Nuclear Information System (INIS)

Anon.

1979-01-01

10 CFR Part 71, Sections 71.35 and 71.36, require that packages used to transport radioactive materials meet specified normal and hypothetical accident conditions. Acceptable design criteria are presented for use in the structural analysis of the containment vessels of Type B packages used to transport irradiated nuclear fuel. Alternative design criteria meeting the structural requirements of 10 CFR Part 71, Section 71.35 and 71.36, may also be used
Maintaining Department of Energy facilities general design criteria

International Nuclear Information System (INIS)

Metzler, J.F.

1985-01-01

A General Design Criteria (GDC) Planning Board has been established in the Department of Energy to streamline the improvement and maintenance of the GDC Manual. This Planning Board, composed of a membership from field organizations and Headquarters programmatic offices, started work on 15 enhancements to the GDC Manual. One of those enhancements details natural phenomena hazards criteria. In the past year the Planning Board submitted a major recommendation which has been implemented into what is known as the GDC Improvements project. The result of this project pledges to dramatically increase the GDC Manual's utilization and effectiveness
78 FR 38091 - Airworthiness Criteria: Proposed Airship Design Criteria for Lockheed Martin Aeronautics Model...

Science.gov (United States)

2013-06-25

..., 2012 Lockheed Martin Aeronautics submitted an application for type certification for the model LMZ1M..., views, or arguments as they may desire. Commenters should identify the proposed design criteria on the... Lockheed Martin Aeronautics submitted an application for type certification for the model LMZ1M airship...
2D Decision-Making for Multi-Criteria Design Optimization

National Research Council Canada - National Science Library

Engau, A; Wiecek, M. M

2006-01-01

.... To facilitate those analyses and enhance decision-making and design selection, we propose to decompose the original problem by considering only pairs of criteria at a time, thereby making tradeoff...
Food chain design using multi criteria decision making, an approach to complex design issues

NARCIS (Netherlands)

Linnemann, A.R.; Hendrix, E.M.T.; Apaiah, R.K.; Boekel, van M.A.J.S.

2015-01-01

Designing a food supply chain for a completely new product involves many stakeholders and knowledge from disciplines in natural and social sciences. This paper describes how Multi Criteria Decision Making (MCDM) facilitated designing a food supply chain in a case of Novel Protein Foods. It made the
Planning, design and technological criteria of conventional and nuclear shelters

International Nuclear Information System (INIS)

Sadoon, A.S.

1989-01-01

The thesis aims to establish a special criteria for building the shelters in two types. The conventional and nuclear, in respect to planning design and technological aspects, and finally establishing a special reference of planning, design and technology for Iraq which can be used when planning or designing a conventional or nuclear shelter. The thesis included four chapters, the first chapter included definition of shelters, and explanation of the effects of all types of weapons on buildings, and the second chapter included definition of planning and design concepts of shelters in its two types and analytical studies for international examples. The third chapter covered definition for technologies of structural, mechanical, electrical and sanitary systems. The fourth chapter included details of a case study in order to approach the results of research which included the conclusions, recommendations, criteria and prospects of planning design and technological aspects. 51 tabs.; 180 figs.; 32 refs.; 15 apps
Design criteria of integrated reactors based on transients

International Nuclear Information System (INIS)

Zanocco, P.; Gimenez, M.; Delmastro, D.

1999-01-01

A new tendency in integrated reactors conceptual design is to include safety criteria through accident analysis. In this work, the effect of design parameters in a Loss of Heat Sink transient using design maps is analyzed. Particularly, geometry related parameters and reactivity coefficients are studied. Also the effect of primary relief/safety valve during the transient is evaluated. A design map for valve area vs. coolant density reactivity coefficient is obtained. A computer code (HUARPE) is developed in order to simulate these transients. Coolant, steam dome, pressure vessel structures and core models are implemented. This code is checked against TRAC with satisfactory results. (author)

Safety Design Criteria of Indian Sodium Cooled Fast Reactors

International Nuclear Information System (INIS)

Pillai, P.; Chellapandi, P.; Chetal, S.C.; Vasudeva Rao, P.R.

2013-01-01

• Important feedback has been gained through the design and safety review of PFBR. • The safety criteria document prepared by AERB and IGCAR would provide important input to prepare the dedicated document for the Sodium cooled Fast Reactors at the national and international level. • A common approach with regard to safety, among countries pursuing fast reactor program, is desirable. • Sharing knowledge and experimental facilities on collaborative basis. • Evolution of strong safety criteria – fundamental to assure safety
Overview of core designs and requirements/criteria for core restraint systems

International Nuclear Information System (INIS)

Sutherland, W.H.

1984-09-01

The requirements and lifetime criteria for the design of a Liquid Metal Fast Breeder Reactor (LMFBR) Core Restraint System are presented. A discussion of the three types of core restraint systems used in LMFBR core design is given. Details of the core restraint system selected for FFTF are presented and the reasons for this selection given. Structural analysis procedures being used to manage the FFTF assembly irradiations are discussed. Efforts that are ongoing to validate the calculational methods and lifetime criteria are presented
Design criteria for Reedy Creek Demonstration Project

International Nuclear Information System (INIS)

Felicione, F.S.; Logan, J.A.

1980-11-01

This document defines the basic criteria for the 100-ton/day pilot plant which will use the Andco-Torrax pyrolysis process at Walt Disney World in Orlando, Florida, to produce hot water. The waste will simulate transuranic wastes which are stored at INEL. The Andco-Torrax process is designed to convert mixed municipal refuse into energy and is called slagging pyrolysis solid waste conversion
Compliance to Universal Design Criteria in Nursing Homes of Tehran

Directory of Open Access Journals (Sweden)

Morteza Nasiri

2016-07-01

Conclusion: The findings of this study showed that the majority of nursing homes evaluated did not follow the universal design criteria. Therefore, providing the proper guidelines and policies to promote the universal design observance in nursing homes is considered as a major necessity.
Safety Design Criteria (SDC) for Gen-IV Sodium-cooled Fast Reactor

International Nuclear Information System (INIS)

Nakai, Ryodai

2013-01-01

SDC Development Background & Objectives: • Safety Design Criteria (SDC) Development for Gen-IV SFR: – Proposed at the GIF Policy Group (PG) meeting in October 2010 –SDC “harmonization” is increasingly important for: • Realization of enhanced safety designs meeting to Gen-IV safety goals and safety approach common to SFR systems; • Preparation for the forthcoming licensing in the near future; • Because Gen-IV SFR are progressing into conceptual design stage. • The SDC is the Reference criteria: – Of the designs of safety-related Structures, Systems & Components that are specific to the SFR system; – For clarifying the requisites systematically & comprehensively; – When the technology developers apply the basic safety approach and use the codes & standards for conceptual design of the Gen-IV SFR system
Safety approach to the selection of design criteria for the CRBRP reactor refueling system

International Nuclear Information System (INIS)

Meisl, C.J.; Berg, G.E.; Sharkey, N.F.

1979-01-01

The selection of safety design criteria for Liquid Metal Fast Breeder Reactor (LMFBR) refueling systems required the extrapolation of regulations and guidelines intended for Light Water Reactor refueling systems and was encumbered by the lack of benefit from a commercially licensed predecessor other than Fermi. The overall approach and underlying logic are described for developing safety design criteria for the reactor refueling system (RRS) of the Clinch River Breeder Reactor Plant (CRBRP). The complete selection process used to establish the criteria is presented, from the definition of safety functions to the finalization of safety design criteria in the appropriate documents. The process steps are illustrated by examples
Justification of disintegration testing beyond current FDA criteria using in vitro and in silico models.

Science.gov (United States)

Uebbing, Lukas; Klumpp, Lukas; Webster, Gregory K; Löbenberg, Raimar

2017-01-01

Drug product performance testing is an important part of quality-by-design approaches, but this process often lacks the underlying mechanistic understanding of the complex interactions between the disintegration and dissolution processes involved. Whereas a recent draft guideline by the US Food and Drug Administration (FDA) has allowed the replacement of dissolution testing with disintegration testing, the mentioned criteria are not globally accepted. This study provides scientific justification for using disintegration testing rather than dissolution testing as a quality control method for certain immediate release (IR) formulations. A mechanistic approach, which is beyond the current FDA criteria, is presented. Dissolution testing via United States Pharmacopeial Convention Apparatus II at various paddle speeds was performed for immediate and extended release formulations of metronidazole. Dissolution profile fitting via DDSolver and dissolution profile predictions via DDDPlus™ were performed. The results showed that Fickian diffusion and drug particle properties (DPP) were responsible for the dissolution of the IR tablets, and that formulation factors (eg, coning) impacted dissolution only at lower rotation speeds. Dissolution was completely formulation controlled if extended release tablets were tested and DPP were not important. To demonstrate that disintegration is the most important dosage form attribute when dissolution is DPP controlled, disintegration, intrinsic dissolution and dissolution testing were performed in conventional and disintegration impacting media (DIM). Tablet disintegration was affected by DIM and model fitting to the Korsmeyer-Peppas equation showed a growing effect of the formulation in DIM. DDDPlus was able to predict tablet dissolution and the intrinsic dissolution profiles in conventional media and DIM. The study showed that disintegration has to occur before DPP-dependent dissolution can happen. The study suggests that
Investigation on Stress-Rupture Behavior of a Chopped-Glass-Fiber Composite for Automotive Durability Design Criteria

Energy Technology Data Exchange (ETDEWEB)

Ren, W

2001-08-24

Practical and inexpensive testing methods were developed to investigate stress-rupture properties of a polymeric composite with chopped glass fiber reinforcement for automotive applications. The material was tested in representative automotive environments to generate experimental data. The results indicate that environments have substantial effects on the stress-rupture behavior. The data were analyzed and developed into stress-rupture design criteria to address one of the durability aspects of the material for automotive structural applications.
High level radioactive waste management facility design criteria

International Nuclear Information System (INIS)

Sheikh, N.A.; Salaymeh, S.R.

1993-01-01

This paper discusses the engineering systems for the structural design of the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS). At the DWPF, high level radioactive liquids will be mixed with glass particles and heated in a melter. This molten glass will then be poured into stainless steel canisters where it will harden. This process will transform the high level waste into a more stable, manageable substance. This paper discuss the structural design requirements for this unique one of a kind facility. A special emphasis will be concentrated on the design criteria pertaining to earthquake, wind and tornado, and flooding
Equipment design for reliability testing of protection system

International Nuclear Information System (INIS)

Situmorang, Johnny; Tjahjono, H.; Santosa, A. Z.; Tjahjani, S.DT.; Ismu, P.H; Haryanto, D.; Mulyanto, D.; Kusmono, S

1999-01-01

The equipment for reliability testing of cable of protection system has been designed as a a furnace with the electric heater have a 4 kW power, and need time 10 minute to reach the designed maximum temperature 3000C. The dimension of furnace is 800 mm diameter and 2000 mm length is isolated use rockwool isolator and coated by aluminium. For the designed maximum temperature the surface temperature is 78 0c. Assemble of specimens is arranged horizontally in the furnace. The failure criteria will be defined based on the behaviour of the load circuit in each line of cable specimens
Overview of core designs and requirements/criteria for core restraint systems

International Nuclear Information System (INIS)

Sutherland, W.H.

1984-01-01

The requirements and lifetime criteria for the design of a Liquid Metal Fast Breeder Reactor (LMFBR) Core Restraint System is presented. A discussion of the three types of core restraint systems used in LMFBR core design is given. Details of the core restraint system selected for FFTF are presented and the reasons for this selection given. Structural analysis procedures being used to manage the FFTF assembly irradiations are discussed. Efforts that are ongoing to validate the calculational methods and lifetime criteria are presented. (author)
Design Processes and Criteria for the X-51A Flight Vehicle Airframe

National Research Council Canada - National Science Library

Lane, Jeffrey

2007-01-01

.... This paper summarizes the X-51A vehicle mission requirements, system design, design processes used for airframe synthesis, design safety factors, success criteria and issues facing the incorporation...
Packaging design criteria, transfer and disposal of 102-AP mixer pump

International Nuclear Information System (INIS)

Carlstrom, R.F.

1994-01-01

A mixer pump installed in storage tank 241-AP-102 (102-AP) has failed. This pump is referred to as the 102-AP mixer pump (APMP). The APMP will be removed from 102-AP 1 and a new pump will be installed. The main purpose of the Packaging Design Criteria (PDC) is to establish criteria necessary to design and fabricate a shipping container for the transfer and storage of the APMP from 102-AP. The PDC will be used as a guide to develop a Safety Evaluation for Packaging (SEP)
Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2009-05-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.
Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

International Nuclear Information System (INIS)

2009-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.
Functional design criteria for the self-installing liquid observation well

International Nuclear Information System (INIS)

Parra, S.A.

1996-01-01

This document presents the functional Design Criteria for installing liquid observation wells (LOWs) into single-shell tanks containing ferrocyanide and organic wastes. The LOWs will be designed to accommodate the deployment of gamma, neutron, and electromagnetic induction probes and to interface with the existing tank structure and environment
Fuel safety criteria technical review - Results of OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria

International Nuclear Information System (INIS)

Hollasky, N.; Valtonen, K.; Hache, G.; Gross, H.; Bakker, K.; Recio, M.; Bart, G.; Zimmermann, M.; Van Doesburg, W.; Killeen, J.; Meyer, R.O.; Speis, T.

2000-01-01

of the assessment of the safety criteria, the TF members looked at various issues, as they relate to one or more criteria, that have become of special interest. These topics included high burnup, core management, MOX, mixed cores, incomplete control rod insertion, and axial offset anomaly. Also, an attempt was made to assess the current level of methods and codes, which are used to verify the criteria and margins. As code development activities are widespread, the Task Force could not identify all such activities but focused on those needed to adequately analyse the effects of new design elements. The Task Force did not extensively review all ongoing and future research programs. However, a few examples of research programs are given that contribute to investigating the phenomena and mechanisms of fuel behavior under transient / accident conditions. These include hot-cell testing at Argonne National Laboratory in the U.S., the Halden Reactor Project in Norway, research and development work by Belgonucleaire in Belgium, the Cabri test reactor and related programs in France, and the Nuclear Safety Research Reactor program in Japan. As a result of all above assessments, the Task Force considers that the current framework of fuel safety criteria remains generally applicable, being largely unaffected by the 'new' or modern design elements; the levels (numbers) in the individual safety criteria may, however, change in accordance with the particular fuel and core design features. Some of these levels have already been - or are continuously being - adjusted; level adjustments of several other criteria (RIA, LOCA) also appear to be needed, on the basis of experimental data and the analysis thereof. For this (re)assessment of fuel safety criteria, the following process is recommended: (a) Continue to develop best-estimate (nominal) analysis methods, together with a suitable uncertainty analysis, in all areas of safety analysis (b) Continue to perform experimental verification
Criteria for selection of target materials and design of high-efficiency-release targets for radioactive ion beam generation

CERN Document Server

Alton, G D; Liu, Y

1999-01-01

In this report, we define criteria for choosing target materials and for designing, mechanically stable, short-diffusion-length, highly permeable targets for generation of high-intensity radioactive ion beams (RIBs) for use at nuclear physics and astrophysics research facilities based on the ISOL principle. In addition, lists of refractory target materials are provided and examples are given of a number of successful targets, based on these criteria, that have been fabricated and tested for use at the Holifield Radioactive Ion Beam Facility (HRIBF).
Design Criteria for Process Wastewater Pretreatment Facilities

Science.gov (United States)

1988-05-01

Stripping Column H13 ’Re Purpose: The purpose of this report, is to provide design criteria for pretreatment needs for ’ I. INTRODUCTION ’". discharge of...which a portion of the vessel is filled with packing. Packing materials vary from corrugated steel to bundles of fibers (Langdon et al., 1972) to beds...concentration(s) using Table 20. Wastewater treatability studies should be considered as a process-screening tool for all wastewater streams for
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...

Design criteria for plutonium gloveboxes

International Nuclear Information System (INIS)

Anon.

1981-01-01

The standard defines criteria for the design of glovebox systems to be used for the handling of plutonium in any form or isotopic composition or when mixed with other elements or compounds. The glovebox system is a series of physical barriers provided with glove ports and gloves, through which process and maintenance operations may be performed, together with an operating ventilation system. The system minimizes the potential for release of radioactive material to the environment, protects operators from contamination, and mitigates the consequences of abnormal condiations. The standard covers confinement, construction, materials, windows, glove ports, gloves, equipment insertion and removal, lighting, ventilation, fire protection, criticality prevention, services and utilities, radiation shielding, waste systems, monitoring and alarm systems, safeguards, quality assurance, and decommissioning
California-Oregon 500-kV transmission line development of design criteria

International Nuclear Information System (INIS)

Simpson, K.D.

1990-01-01

The California-Oregon Transmission Project (COTP) encompassed the design and construction of a third 500-kV ac intertie between California and the Pacific Northwest Transmission system. Sargent ampersand Lundy's (S ampersand L) scope of work in the COTP includes the design of approximately 150 miles of new single-circuit, 500-kV transmission line from southern Oregon to the vicinity of Redding, California. This paper presents the development of the design criteria for this segment of the project, which crosses diverse topographic and climatic regions. This project is an example of the increasing utilization of computers in transmission line engineering. Almost all aspects of design involved the use of the computer. Also, the development of the design criteria for this project coincided with an early release of the TLWorkstation software package by EPRI. TLWorkstation is an engineering workstation containing a family of programs for various aspects of transmission line design. This engineering software allows for increasing refinement in the design and economic optimization of transmission lines and is becoming an important design tool for transmission engineers
Recording length criteria as applied in ultrasonic testing

International Nuclear Information System (INIS)

Fischer, E.; Kroening, M.; Schober, H.; Fischdick, H.

1983-01-01

An appreciable method used to assess the quality and integrity of safety-related components in light water reactors is the ultrasonic examination, in which case great importance is attributed to the criteria pertaining to recording length and permissible defect size. The development of the recording length criteria as applied when employing this method of examination is portrayed, the latter being based on the criteria which have proven themselves throughout long years of practice in the examination of conventional components. When taking these criteria into account the application of conventional ultrasonic techniques often leads to problems in the case of thick-walled components the reason being that indications are overrated. Taking the design of reactor components as the basic point of consideration, modified criteria are derived particularly when the size of discontinuities calculated by fracture mechanics analyses is taken into account. The introduction of new ultrasonic examination techniques such as, for example, focussed probes revealed that a considerably more realistic assessment is possible and consequently results in a reduction of unnecessary repairs. A comparison of the size of indications determined using conventional and analytical technqiues renders possible the anchoring of an intermediate stage in the evaluation of indications which is encompassed in the consideration of the bundle divergence. Thus a new concept is realized for the evaluation of ultrasonic indications detected in reactor components, which in the meantime has found its way into the associated regulatory guides. (orig.)
Design criteria tank farm storage and staging facility

International Nuclear Information System (INIS)

Lott, D.T.

1995-01-01

Tank Farms Operations must store/stage material and equipment until work packages are ready to work. Consumable materials are also required to be stored for routine and emergency work. Safety issues based on poor housekeeping and material deterioration due to weather damage has resulted from inadequate storage space. It has been determined that a storage building in close proximity to the Tank Farm work force would be cost effective. This document provides the design criteria for the design of the storage and staging buildings near 272AW and 272WA buildings
Decontamination and decommissioning criteria for use in design of new plutonium facilities

International Nuclear Information System (INIS)

Paschall, R.K.

1975-01-01

Decontamination and decommissioning (D and D) criteria were assembled for use in designing new plutonium facilities. These criteria were gathered from literature searches and visits to many plutonium facilities around the country. The recommendations of reports and experienced personnel were used. Since total D and D costs can be millions of dollars, improved designs to facilitate D and D will result in considerable savings in cost and time and will help to leave the site for unrestricted future use after D and D. Finally, better design will reduce hazards and improve safety during the D and D effort
Investigation on Stress-Rupture Behavior of a Chopped-Glass-Fiber Composite for Automotive Durability Design Criteria; FINAL

International Nuclear Information System (INIS)

Ren, W

2001-01-01

Practical and inexpensive testing methods were developed to investigate stress-rupture properties of a polymeric composite with chopped glass fiber reinforcement for automotive applications. The material was tested in representative automotive environments to generate experimental data. The results indicate that environments have substantial effects on the stress-rupture behavior. The data were analyzed and developed into stress-rupture design criteria to address one of the durability aspects of the material for automotive structural applications
Human Factors Design Criteria for Future Systems. FAADS Design Criteria Evolving from the Sgt. York Follow-On Evaluation 1

Science.gov (United States)

1989-05-01

and MIL-., TD -11172C. These are the most widely used documents providing human factors design criteria for the development of military systems through...4) 4bd 4)(.E c4- z - v -. r-f .r40 m 0 S -( OD Q) 0k .1 .o1 u .d 44). o- C.~) V QCf 44)) :0 J0 Al4 L .4Uv.-4 C4)LI.-44(U(E *4)4)( U . S- M 0 a *-P 4
Nuclear Fuel Safety Criteria Technical Review - Second edition

International Nuclear Information System (INIS)

Beck, Winfried; Blanpain, Patrick; Fuketa, Toyoshi; Gorzel, Andreas; Hozer, Zoltan; Kamimura, Katsuichiro; Koo, Yang-Hyun; Maertens, Dietmar; Nechaeva, Olga; Petit, Marc; Rehacek, Radomir; Rey-Gayo, Jose Maria; Sairanen, Risto; Sonnenburg, Heinz-Guenther; Valach, Mojmir; Waeckel, Nicolas; Yueh, Ken; Zhang, Jinzhao; Voglewede, John

2012-01-01

Most of the current nuclear fuel safety criteria were established during the 1960's and early 1970's. Although these criteria were validated against experiments with fuel designs available at that time, a number of tests were based on unirradiated fuels. Additional verification was performed as these designs evolved, but mostly with the aim of showing that the new designs adequately complied with existing criteria, and not to establish new limits. In 1996, the OECD Nuclear Energy Agency (NEA) reviewed existing fuel safety criteria, focusing on new fuel and core designs, new cladding materials and industry manufacturing processes. The results were published in the Nuclear Fuel Safety Criteria Technical Review of 2001. The NEA has since re-examined the criteria. A brief description of each criterion and its rationale are presented in this second edition, which will be of interest to both regulators and industry (fuel vendors, utilities)
Preparation of acceptance tests and criteria for the Test Blanket Systems to be operated in ITER

Energy Technology Data Exchange (ETDEWEB)

Laan, J.G. van der, E-mail: JaapG.vanderLaan@iter.org [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Cuquel, B. [AIRBUS Defence and Space S.A.S., 13115 Saint Paul Lez Durance (France); Demange, D.; Ghidersa, B.-E. [Karlsruhe Institute of Technology, Karlsruhe (Germany); Giancarli, L.M.; Iseli, M.; Jourdan, T. [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Nevière, J.-C. [Comex-Nucleaire, 13115 Saint Paul Lez Durance (France); Pascal, R.; Ring, W. [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France)

2015-10-15

Highlights: • Initial guideline for acceptance testing and acceptance criteria for Test Blanket Systems in ITER. • These tests complement those required by the applicable codes and standards, and regulations. • Completion of TBS manufacture will be followed by Factory Acceptance Testing, prior to shipment. • Next steps are “Reception Inspection Tests”, and on-site pre-installation and components tests. • This guideline allows the detailing of the TBS specific test plans and their scheduling. - Abstract: This paper describes the main acceptance criteria and required acceptance tests for the components of the six Test Blanket Systems to be installed and operated in ITER. It summarizes the guide-line toward the establishment of detailed test plans for the TBS, starting from the end-product at the ITER Members factories, and to generally define the type of tests that have to be performed on the ITER site after shipment, and/or prior to the systems final commissioning phase.
Value/impact of design criteria for cast ductile iron shipping casks

International Nuclear Information System (INIS)

1983-01-01

The ductile failure criteria proposed in the Base report appear appropriate except that stress intensity values, S/sub m/ should be based on lower safety factors and ductility should be added as a criterion. A safety factor for stress intensity, s/sub m/ of 4 is recommended rather than 3 on minimum ultimate tensile strength, S/sub u/ in accordance with ASME code philosophy of assigning higher safety factors to cast ductile iron than to steel. This more conservative approach has no impact on costs since the selection of wall thickness is controlled by shielding rather than by stress considerations. The addition of a ductility criterion is recommended because of the problems associated with the selection of appropriate brittle failure criteria and the potential for cast ductile iron to have extremely low elongation at failure. Neither a materials nor a linear elastic fracture mechanics (LEFM) approach appear to be viable for demonstrating the prevention of brittle failure in cast ductile iron shipping casks. It is possible that the analytic methods predict brittle failure because of extremely conservative assumptions whereas real casks may not fail. Model drop tests could be used to demonstrate containment integrity. It is estimated that a risk committment of at least $1,000,000 would be required for engineering, design, model fabrication and testing. Before taking such risks, a mechanism should be found to obtain concurrence from NRC that the results of the test would be acceptable. Probabilistic approaches or model testing could be used to demonstrate the acceptability of cast ductile iron casks from a brittle failure point of view. Before probabilistic methods can be used, the NRC would have to be persuaded to accept the approach of the Competent Authority in West Germany or more formalized methods for probabilistic risk assessments
MCO combustible gas management leak test acceptance criteria; TOPICAL

International Nuclear Information System (INIS)

SHERRELL, D.L.

1999-01-01

Existing leak test acceptance criteria for mechanically sealed and weld sealed multi-canister overpacks (MCO) were evaluated to ensure that MCOs can be handled and stored in stagnant air without compromising the Spent Nuclear Fuel Project's overall strategy to prevent accumulation of combustible gas mixtures within MCO's or within their surroundings. The document concludes that the integrated leak test acceptance criteria for mechanically sealed and weld sealed MCOs (1 x 10(sup -5) std cc/sec and 1 x 10(sup -7) std cc/sec, respectively) are adequate to meet all current and foreseeable needs of the project, including capability to demonstrate compliance with the NFPA 60 Paragraph 3-3 requirement to maintain hydrogen concentrations[within the air atmosphere CSB tubes] t or below 1 vol% (i.e., at or below 25% of the LFL)
Nevada test site defense waste acceptance criteria, certification, and transfer requirements

International Nuclear Information System (INIS)

1988-10-01

The Nevada Test Site (NTS) Defense Waste Acceptance Criteria, Certification and Transfer Requirements establishes procedures and criteria for safe transfer, disposal, and storage of defense transuranic, low-level, and mixed waste at the NTS. Included are an overview of the NTS defense waste management program; the NTS waste acceptance criteria for transuranic, low-level, and mixed wastes; waste certification requirements and guidance; application to submit waste; and requirements for waste transfer and receipt. 5 figs., 16 tabs
Integrating Green Building Criteria Into Housing Design Processes Case Study: Tropical Apartment At Kebon Melati, Jakarta

Science.gov (United States)

Farid, V. L.; Wonorahardjo, S.

2018-05-01

The implementation of Green Building criteria is relatively new in architectural practice, especially in Indonesia. Consequently, the integration of these criteria into design process has the potential to change the design process itself. The implementation of the green building criteria into the conventional design process will be discussed in this paper. The concept of this project is to design a residential unit with a natural air-conditioning system. To achieve this purpose, the Green Building criteria has been implemented since the beginning of the design process until the detailing process on the end of the project. Several studies was performed throughout the design process, such as: (1) Conceptual review, where several professionally proved theories related to Tropical Architecture and passive design are used for a reference, and (2) Computer simulations, such as Computational Fluid Dynamics (CFD) and wind tunnel simulation, used to represent the dynamic response of the surrounding environment towards the building. Hopefully this paper may become a reference for designing a green residential building.
Fundamental criteria for the design of high-performance Josephson nondestructive readout random access memory cells and experimental confirmation

International Nuclear Information System (INIS)

Henkels, W.H.

1979-01-01

Fundamental design criteria for Josephson nondestructive readout random access memory (NDRO RAM) cells are presented, within the context of an LSI array environment. Emphasis is placed upon principles which are relevant to high performance. The criteria are elucidated via a specific design which is simulated and then experimentally evaluated in a technology with a smallest critical dimension of 5 μm. The specific cell differs from previously tested Josephson NDRO cells in several respects; namely, the cell stores only approx.8Phi 0 , employs interferometer gates and an external damping resistor, allows switching into device resonances, and eliminates the need for a special initialization cycle. The cell-selection scheme, employing triple coincidence, results in larger operating margins and smaller operating currents than have previously been achieved. The large operating margins and all basic cell design criteria were experimentally verified. The experimental interferometer gate characteristics were analyzed in detail and found to be describable by simple models. In addition, it was discovered that single flux quantum transitions in the interferometer gates could be exploited beneficially in order to enhance the insensitivity of operating margins to fabrication tolerances
Fostering and Assessing Infographic Design for Learning: The Development of Infographic Design Criteria

Science.gov (United States)

Nuhoglu Kibar, Pinar; Akkoyunlu, Buket

2017-01-01

In this ever more digital and visual world, it has become more vital that students are encouraged to create content during the learning process through effective visualization of their knowledge. Infographics are an effective method for such visualization. The current study therefore proposes an infographic design rubric (IDR) as a criteria-based…
Design Criteria in Revitalizing Old Warehouse District on the Kalimas Riverbank Area of Surabaya City

Directory of Open Access Journals (Sweden)

Endang Titi Sunarti Darjosanjoto

2015-09-01

Full Text Available Neglected warehouse buildings along the Kalimas River have created a poor urban façade in terms of visual quality. However the city government is planning to encourage tourism activities that take advantage of Kalimas River and its surrounding environment. If there is no good plan in accordance with the concept of local identity for old city of Surabaya, it will reduce it as a tourist attraction. In reference to the issue above, design criteria needs to be compiled for revitalizing the old warehouse district, which is expected to revive the identity of this district and be able to support the city’s tourism. This study was conducted by recording field observations, and the data was analyzed using the character appraisal method. The character appraisal analysis method is presented in the form of street picture data, which is divided into determined segments. The results show that there are five components including place attachment, sustainable urban design, green open space design, ecological riverfront design, and activity support that should be considered in the revitalization of the warehouse district. Those components are divided into two parts: building and open space at the riverbank. There are 13 design criteria for building at the riverbank, while there are 14 design criteria for open space at the riverbank. These design criteria can enrich the warehouse district’s revitalization by improving the visual quality of the urban environment.Keywords: design criteria; warehouse district; riverbank; Surabaya; revitalization.
Test Rig Design and Presentation for a Hydraulic Yaw System

DEFF Research Database (Denmark)

Stubkier, Søren; Pedersen, Henrik C.; Andersen, Torben Ole

2013-01-01

The design and development of a hydraulic yaw system for multi MWturbines is presented and the concept explained. As part of the development of the new concept a full scale test rig for a 5 MW wind turbine has been designed and constructed. The test rig is presented along with its unique design...... features. The design process is outlined to give insight in the design criteria driving the design. Loads and yaw demands are based on the IEC 61400-1 standard for wind turbine design, and the loads for this examination are extrapolated from the FAST aero elastic design software. The concepts are based...... on a 5 MW offshore turbine. After the system presentation, measurement results are presented to verify the behavior of the system. The loads to the system are applied by torque controlled electrical servo drives, which can add a load of up to 3 MNm to the system. This gives an exact picture of the system...
Typical design/qualification acceptance criteria for newly installed pipelines and equipment components of VVER-type NPPs

International Nuclear Information System (INIS)

Masopust, R.

2003-01-01

This paper describes in general the typical design/qualification acceptance criteria and seismic acceptance criteria in particular that are applicable for important to safety newly installed pipelines and equipment components of VVER-type already existing NPPs, specifically during the design verification phase of this newly installed equipment. These criteria are currently used for VVER 440-213 and VVER 1000 NPPs in Czech Republic and in Slovakia. The similar criteria are also used in Hungary. (author)
Functional Design Criteria - plutonium stabilization and handling (PUSH) project W-460

International Nuclear Information System (INIS)

NELSON, D.W.

1999-01-01

This Functional Design Criteria (FDC) contains information to guide the design of the Stabilization and Packaging Equipment necessary to oxidize and package the remaining plutonium-bearing Special Nuclear Materials (SNM) currently in the Plutonium Finishing Plant (PFP) inventory. The FDC also guides the design of vault modifications to allow storage of 3013 packages of stabilized SNM for up to 50 years
Functional Design Criteria plutonium stabilization and handling (PUSH) project W-460

Energy Technology Data Exchange (ETDEWEB)

NELSON, D.W.

1999-09-02

This Functional Design Criteria (FDC) contains information to guide the design of the Stabilization and Packaging Equipment necessary to oxidize and package the remaining plutonium-bearing Special Nuclear Materials (SNM) currently in the Plutonium Finishing Plant (PFP) inventory. The FDC also guides the design of vault modifications to allow storage of 3013 packages of stabilized SNM for up to 50 years.

77 FR 45282 - NRC Position on the Relationship Between General Design Criteria and Technical Specification...

Science.gov (United States)

2012-07-31

... Position on the Relationship Between General Design Criteria and Technical Specification Operability AGENCY... relationship between the general design criteria (GDC) for nuclear power plants and technical specification... Communications Branch, Division of Policy and Rulemaking, Office Nuclear Reactor Regulation, Mail Stop: OWFN-12-D...
Advanced Neutron Source radiological design criteria

International Nuclear Information System (INIS)

Westbrook, J.L.

1995-08-01

The operation of the proposed Advanced Neutron Source (ANS) facility will present a variety of radiological protection problems. Because it is desired to design and operate the ANS according to the applicable licensing standards of the Nuclear Regulatory Commission (NRC), it must be demonstrated that the ANS radiological design basis is consistent not only with state and Department of Energy (DOE) and other usual federal regulations, but also, so far as is practicable, with NRC regulations and with recommendations of such organizations as the Institute of Nuclear Power Operations (INPO) and the Electric Power Research Institute (EPRI). Also, the ANS radiological design basis is in general to be consistent with the recommendations of authoritative professional and scientific organizations, specifically the National Council on Radiation Protection and Measurements (NCRP) and the International Commission on Radiological Protection (ICRP). As regards radiological protection, the principal goals of DOE regulations and guidance are to keep occupational doses ALARA [as low as (is) reasonably achievable], given the current state of technology, costs, and operations requirements; to control and monitor contained and released radioactivity during normal operation to keep public doses and releases to the environment ALARA; and to limit doses to workers and the public during accident conditions. Meeting these general design objectives requires that principles of dose reduction and of radioactivity control by employed in the design, operation, modification, and decommissioning of the ANS. The purpose of this document is to provide basic radiological criteria for incorporating these principles into the design of the ANS. Operations, modification, and decommissioning will be covered only as they are affected by design
Development of a software tool and criteria evaluation for efficient design of small interfering RNA

International Nuclear Information System (INIS)

Chaudhary, Aparna; Srivastava, Sonam; Garg, Sanjeev

2011-01-01

Research highlights: → The developed tool predicted siRNA constructs with better thermodynamic stability and total score based on positional and other criteria. → Off-target silencing below score 30 were observed for the best siRNA constructs for different genes. → Immunostimulation and cytotoxicity motifs considered and penalized in the developed tool. → Both positional and compositional criteria were observed to be important. -- Abstract: RNA interference can be used as a tool for gene silencing mediated by small interfering RNAs (siRNA). The critical step in effective and specific RNAi processing is the selection of suitable constructs. Major design criteria, i.e., Reynolds's design rules, thermodynamic stability, internal repeats, immunostimulatory motifs were emphasized and implemented in the siRNA design tool. The tool provides thermodynamic stability score, GC content and a total score based on other design criteria in the output. The viability of the tool was established with different datasets. In general, the siRNA constructs produced by the tool had better thermodynamic score and positional properties. Comparable thermodynamic scores and better total scores were observed with the existing tools. Moreover, the results generated had comparable off-target silencing effect. Criteria evaluations with additional criteria were achieved in WEKA.
Criteria for design of the Yucca Mountain structures, systems and components for fault displacement

International Nuclear Information System (INIS)

Stepp, C.; Hossain, Q.; Nesbit, S.; Pezzopane, S.; Hardy, M.

1995-01-01

The DOE intends to design the Yucca Mountain high-level waste facility structures, systems and components (SSCs) for fault displacements to provide reasonable assurance that they will meet the preclosure safety performance objectives established by 10 CFR Part 60. To the extent achievable, fault displacement design of the facility will follow guidance provided in the NRC Staff Technical Position. Fault avoidance will be the primary design criterion, especially for spatially compact or clustered SSCs. When fault avoidance is not reasonably achievable, expected to be the case for most spatially extended SSCs, engineering design procedures and criteria or repair and rehabilitation actions, depending on the SSC's importance to safety, are provided. SSCs that have radiological safety importance will be designed for fault displacements that correspond to the hazard exceedance frequency equal to their established seismic safety performance goals. Fault displacement loads are generally localized and may cause local inelastic response of SSCs. For this reason, the DOE intends to use strain-based design acceptance criteria similar to the strain-based criteria used to design nuclear plant SSCs for impact and impulsive loads
Design Report for a 19-pin carbide test-bundle in a ring-subassembly of the test zone of KNK II/2

International Nuclear Information System (INIS)

Haefner, H.E.

1982-03-01

This report describes a 19-rod carbide test bundle in an annular oxide ring element placed at the position 201 of the test zone in the second core of KNK II as well as its behavior during the period of operation. The selected fuel rod concept includes low pellet density and a relatively large gap width as well as helium bonding between fuel and cladding. Characteristic design and operation data are: rod diameter 8.5 mm, pellet diameter 7.0 mm, maximum nominal linear rating 800 W/cm, maximum nominal burnup 70 MWd/kgHM. This report exclusively deals with the carbide test bundle and its individual components; it describes methods, criteria and results concerning the design. The annular carrier element with its head and foot is treated in a separate report. The loadability of the test bundle and its individual components is demonstrated by generally valid standards for strength criteria [de
Design Criteria for Bagless Transfer System (BTS) Packaging System

International Nuclear Information System (INIS)

RISENMAY, H.R.

2000-01-01

This document provides the criteria for the design and installation of a Bagless Transfer System (BTS); Blend, Sieve and Balance Equipment; and Supercritical Fluid Extraction System (SFE). The project consists of 3 major modules: (1) Bagless Transfer System (BTS) Module; (2) Blend, Sieve and Balance Equipment; and (3) Supercritical Fluid Extraction (SFE) Module
Design criteria for a self-actuated shutdown system to ensure limitation of core damage

International Nuclear Information System (INIS)

Deane, N.A.; Atcheson, D.B.

1981-09-01

Safety-based functional requirements and design criteria for a self-actuated shutdown system (SASS) are derived in accordance with LOA-2 success criteria and reliability goals. The design basis transients have been defined and evaluated for the CDS Phase II design, which is a 2550 MWt mixed oxide heterogeneous core reactor. A partial set of reactor responses for selected transients is provided as a function of SASS characteristics such as reactivity worth, trip points, and insertion times
Applicability of Various Load Test Interpretation Criteria in Measuring Driven Precast Concrete Pile Uplift Capacity

Directory of Open Access Journals (Sweden)

Maria Cecilia M. Marcos

2018-04-01

Full Text Available This paper presented a comprehensive analysis of load test interpretation criteria to determine their suitability to driven precast concrete (PC pile uplift capacity. A database was developed containing static pile load tests and utilized for the evaluation. The piles were round and square cross-sections under drained and undrained loading. To explore and compare their behavior, the stored data were categorized into four groups. In general, the trends of every criterion for the four groups were notably the same. In both drained and undrained loading, slightly larger interpreted capacities were demonstrated by square piles than by round piles. Moreover, round piles demonstrated more ductile load-displacement response than square piles especially in undrained loading. Statistical analyses presented that smaller values of displacements exhibited higher coefficient of variation. The drained and undrained tests were compared and results showed less variability in drained than undrained loading and capacity ratios (Qx/QCHIN in drained loading were slightly higher than in undrained loading. The interrelationship and applicability of these criteria as well as the design recommendations in terms of normalized capacity and displacement were given based on the analyses.
R20 Programme: The development of grouting technique. Stop criteria and field tests

International Nuclear Information System (INIS)

Hollmen, K.

2008-01-01

This work is a part of the project 'Grouting Technique' by Posiva Oy, which is responsible for the final disposal of spent nuclear fuel in Finland. This study attempts to collect disperse information about the design parameters of the grouting and about a field-test stop criterion, which differs from the prevailing practice. The literature study describes salient processes of grouting design in sufficient extent. Different methods for grouting stop criterion are described in more detail. Grouting design based on selected grouting theory, grouting and evaluating of the grouting results are presented in the experiential part of this study. This study focuses on rock tunnel grouting using cement-based grout. The requirements for water tightness, which are set down by customer, direct the grouting design. Information about fractures in rock mass, which surrounds the rock facility, is the prime initial data for grouting design. In grouting work, fracturing is generally studied by water loss measurements performed in investigation, probe and grouting holes. Besides the water loss measurement, the Posiva Flow Log -tool, which measures location and transmissivity for every single fracture, is used in ONKALO. Grouting pressure and grout must be chosen together and case-specifically. Both pressure and yield strength of grout are influencing the penetration length of grout in a fracture. Grouting pressure must be high enough to ensure sufficient penetration length, but pressure must be under the level where rock mass breaks to avoid hydraulic fracturing. Raising the water to dry material ratio reduces the yield strength of grout, in which case the grouting pressure can be lowered. Stop criterion for grouting aims to define the point, when the result of the grouting is adequate, and the grouting after that point is uneconomical. Properly specified stop criterion minimizes extra grout volume and reduces the running time of grouting work. From the references, three different
78 FR 38411 - Vogtle Electric Generating Plant, Unit 4; Inspections, Tests, Analyses, and Acceptance Criteria

Science.gov (United States)

2013-06-26

... Plant, Unit 4; Inspections, Tests, Analyses, and Acceptance Criteria AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria completion. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the inspections, tests...
Seismic design criteria for nuclear powerplants

International Nuclear Information System (INIS)

Jennings, P.C.; Guzman, R.A.

1975-01-01

There are three main aspects of the problem of selection of seismic design criteria for major projects such as nuclear power plants. These are the description of the appropriate level of shaking to be considered, usually given in the form of design spectra; the allowable response of the structure, usually specified in terms of allowable stresses and deflections; and the capability of the structure to dissipate energy, commonly given in the form of fractions of critical damping. In this presentation only the first of these features is examined, with particular application to nuclear power plants. Under these restrictions, the most important parts of the problem become the determination of the amplitude of the design spectra corresponding to the safe shutdown earthquake (SSE) and the question of whether the shape of the spectra recommended by Regulatory Guide 1.60 (U. S. Atomic Energy Commission, 1973) is appropriate for the particular application. In the course of working out the details of the approach, it was found useful to reexamine a number of concepts including the use of response spectra or peak values of ground motion parameters, the shape of the design spectra, problems in attenuation and scaling, and the use of motions on the ground surface or bedrock motions. There is nothing fundamentally new in the suggested approach, although some of the features may not have been applied to the problem of selecting design spectra for nuclear power plants in the way suggested. The approach is applied only to nuclear power plants but it is not limited to this application
STRUCTURAL DESIGN CRITERIA FOR TARGET/BLANKET SYSTEM COMPONENT MATERIALS FOR THE ACCELERATOR PRODUCTION OF TRITIUM PROJECT

Energy Technology Data Exchange (ETDEWEB)

W. JOHNSON; R. RYDER; P. RITTENHOUSE

2001-01-01

The design of target/blanket system components for the Accelerator Production of Tritium (APT) plant is dependent on the development of materials properties data specified by the designer. These data are needed to verify that component designs are adequate. The adequacy of the data will be related to safety, performance, and economic considerations, and to other requirements that may be deemed necessary by customers and regulatory bodies. The data required may already be in existence, as in the open technical literature, or may need to be generated, as is often the case for the design of new systems operating under relatively unique conditions. The designers' starting point for design data needs is generally some form of design criteria used in conjunction with a specified set of loading conditions and associated performance requirements. Most criteria are aimed at verifying the structural adequacy of the component, and often take the form of national or international standards such as the ASME Boiler and Pressure Vessel Code (ASME B and PV Code) or the French Nuclear Structural Requirements (RCC-MR). Whether or not there are specific design data needs associated with the use of these design criteria will largely depend on the uniqueness of the conditions of operation of the component. A component designed in accordance with the ASME B and PV Code, where no unusual environmental conditions exist, will utilize well-documented, statistically-evaluated developed in conjunction with the Code, and will not be likely to have any design data needs. On the other hand, a component to be designed to operate under unique APT conditions, is likely to have significant design data needs. Such a component is also likely to require special design criteria for verification of its structural adequacy, specifically accounting for changes in materials properties which may occur during exposure in the service environment. In such a situation it is common for the design criteria
Fail-safe design criteria for computer-based reactor protection systems

International Nuclear Information System (INIS)

Keats, A.B.

1980-01-01

The increasing quantity and complexity of the instrumentation required in nuclear power plants provides a strong incentive for using on-line computers as the basis of the control and protection systems. On-line computers using multiplexed sampled data are already well established but their application to nuclear reactor protection systems requires special measures to satisfy the very high reliability which is demanded in the interests of safety and availability. Some existing codes of practice relating to segregation of replicated subsysttems continue to be applicable and lead to division of the computer functions into two distinct parts. The first computer, referred to as the Trip Algorithm Computer may also control the multiplexer. Voting on each group of status inputs yielded by the trip algorithm computers is performed by the Vote Algorithm Computer. The conceptual disparities between hardwired reactor-protection systems and those employing computers also rise to a need for some new criteria. An important objective of these criteria, minimising the need for a failure-mode-and-effect-analysis of the computer software, but is achieved almost entirely by 'hardware' properties of the system: the systematic use of hardwired test inputs which cause excursions of the trip algorithms into the tripped state in a uniquely ordered but easily recognisable sequence, and the use of hardwired 'pattern recognition logic' which generates a dynamic 'healthy' stimulus for the shutdown actuators only in response to the unique sequence generated by the hardwired input signal pattern. The adoption of the proposed design criteria ensure not only failure-to-safety in the hardware but the elimination, or at least minimisation, of the dependence on the correct functioning of the computer software for the safety system. (auth)
Proceedings of the workshop on structural design criteria for HTR

International Nuclear Information System (INIS)

Breitbach, G.; Schubert, F.; Nickel, H.

1989-04-01

The papers demonstrate the status of high temperature reactor technology with regard to its realization in the nuclear power industry of various countries (FRG, USA, Japan) as well as to the development of safety rules in Germany. The design criteria for HTR could be presented. The criteria already determine definitely and almost completely the relevant requirements of the component rules. The informations include the technical boundary conditions with regard to safety, the metallic high temperature components, a particular section dealing with the reactor pressure vessel, especially with the prestressed concrete vessel, and the structural graphite components. (DG)
Guidelines for the development of natural phenomena hazards design criteria for surface facilities

International Nuclear Information System (INIS)

Nelson, T.A.; Hossain, Q.A.; Murray, R.C.

1992-01-01

This paper discusses the rationale behind the guidelines, criteria, and methodologies that are currently used for natural phenomena hazard design and evaluation of DOE nuclear and non-nuclear facilities. The bases for the performance goals and usage categories specified in UCRL-15910 are examined, and the sources of intentional conservatism in the analyses, design, and evaluation methods and criteria are identified. Outlines of recent developments/changes in DOE Orders related to Natural Phenomena hazard mitigation are also presented. Finally, the authors recommend the use of DOE methodologies as embodied in UCRL-15910 for design and evaluation of surface facilities of the high level nuclear waste repository site
Functional design criteria 241-AP-102 Flexible Receiver System

International Nuclear Information System (INIS)

Roblyer, S.P.

1995-01-01

A mixer pump was installed in the 1.07 m (42-in.) riser of the central pump pit of tank 241-AP-102 to mitigate potential fluid separation particle sedimentation by mixing the tank's contents. The mixer pump performed this function until failure. Its removal is now necessary to meet possible tank content removal commitments or other corrective actions. The proposed removal procedure requires a flexible receiver that will provide a barrier to contamination during removal and transfer of the pump to the mixer pump storage container. This document describes the functional design criteria of the flexible receiver. These criteria include the functional and performance requirements of the flexible receiver as a barrier to contamination during normal conditions and contingencies and the instrumentation requirements
Development of a novel set of criteria to select methodology for designing product service systems

Directory of Open Access Journals (Sweden)

Tuananh Tran

2016-04-01

Full Text Available This paper proposes eight groups of twenty nine scoring criteria that can help designers and practitioners to compare and select an appropriate methodology for a certain problem in designing product service system (PSS. PSS has been researched for more than a decade and is now becoming more and more popular in academia as well as industry. Despite that fact, the adoption of PSS is still limited for its potential. One of the main reasons is that designing PSS itself is a challenge. Designers and developers face difficulties in choosing appropriate PSS design methodologies for their projects so that they can design effective PSS offerings. By proposing eight groups of twenty nine scoring criteria, this paper enables a “step by step” process to identify the most appropriate design methodology for a company’s PSS problem. An example is also introduced to illustrate the use of the proposed scoring criteria and provide a clear picture of how different design methodologies can be utilized at their best in terms of application.
Proficiency testing criteria for clearance level in solid waste gamma measurement in Taiwan.

Science.gov (United States)

Chen, Chun-Liang; Wang, Jeng-Jong; Chiu, Huang-Sheng

2013-11-01

To guarantee the measurement quality for clearance level in solid waste material, the Institute of Nuclear Energy Research (INER) established the criteria for proficiency testing of clearance level measurement. INER and the Taiwan Accreditation Foundation (TAF) organized the Technique Committee Meeting twice to discuss these criteria in 2011. The participating laboratories must completely conform to the ISO/IEC 17025, and they also must meet the requirements of the criteria. According to the criteria, the participating laboratories analyzed the minimum detectable amount (MDA) and that should be less than 20% of the clearance level (AMDA) given in the Atomic Energy Council's (AEC) "Regulations on Clearance Level for Radioactive Waste Management". The testing results should conform to the deviation and traceability requirements. Copyright © 2013 Elsevier Ltd. All rights reserved.
Licensing topical report: interpretation of general design criteria for high-temperature gas-cooled reactors

International Nuclear Information System (INIS)

Orvis, D.D.; Raabe, P.H.

1980-01-01

This Licensing Topical Report presents a set of General Design Criteria (GDC) which is proposed for applicability to licensing of graphite-moderated, high-temperature gas-cooled reactors (HTGRs). Modifications as necessary to reflect HTGR characteristics and design practices have been made to the GDC derived for applicability to light-water-cooled reactors and presented in Appendix A of Part 50, Title 10, Code of Federal Regulations, including the Introduction, Definitions, and Criteria. It is concluded that the proposed set of GDC affords a better basis for design and licensing of HTGRs
Proposed waste form performance criteria and testing methods for low-level mixed waste

International Nuclear Information System (INIS)

Franz, E.M.; Fuhrmann, M.; Bowerman, B.; Bates, S.; Peters, R.

1994-08-01

This document describes proposed waste form performance criteria and testing method that could be used as guidance in judging viability of a waste form as a physico-chemical barrier to releases of radionuclides and RCRA regulated hazardous components. It is assumed that release of contaminants by leaching is the single most important property by which the effectiveness of a waste form is judged. A two-tier regimen is proposed. The first tier includes a leach test required by the Environmental Protection Agency and a leach test designed to determine the net forward leach rate for a variety of materials. The second tier of tests are to determine if a set of stresses (i.e., radiation, freeze-thaw, wet-dry cycling) on the waste form adversely impact its ability to retain contaminants and remain physically intact. It is recommended that the first tier tests be performed first to determine acceptability. Only on passing the given specifications for the leach tests should other tests be performed. In the absence of site-specific performance assessments (PA), two generic modeling exercises are described which were used to calculate proposed acceptable leach rates

Design criteria for prestressed concrete pressure vessels for high temperature reactors

International Nuclear Information System (INIS)

Schimmelpfennig, K.

1991-01-01

This paper summarizes the work on design criteria for concrete structures of Prestressed Concrete Reactor Vessels (PCRVs), which has been carried out since 1984 by a couple of competent institutions. After some basic considerations on the safety demands on PCRVs, especially their Prestressed Concrete Structure (PCS), and the consequences for an elevated level of quality to be ensured by the design criteria, an impression is given, first, by what means a higher quality standard is gained with respect to selection of materials and specification of material data in comparison to the usual building industry and what kind of criteria on this behalf should be fixed in a PCRV code. As a further quality increasing feature, the specific demands on design analysis as practised according to the present state of science and as to be treated within a code are discussed. This concerns analyses for steady state and transient temperatures as well as stress and strain analyses for service and ultimate load conditions. It is outlined to what degree calculation models should be detailed, which includes statements about admissible idealizations. As a central topic the question is discussed in what way the ultimate load capacity has to be evaluated, thereby presenting results of some investigations pointing out the conditions under which the design is determined by the different kinds of ultimate load conditions. Finally, some reflections on the demands on monitoring the PCS behaviour during its lifetime and on several questions still to be answered in this field are expressed. (orig.)
Upgrading instrumentation and control in nuclear power plants. Design criteria

International Nuclear Information System (INIS)

Rodriguez Rodriguez, M.C.; Alvarez Menendez, A.

1997-01-01

The use of programmed digital technology in Protection, Control, Monitoring and Information Systems in new generation nuclear power plants, or the use of this technology to replace or upgrade existing systems based on wired analog instrumentation and electromechanical relays, has led to new international standards which establish new design requirements or adapt existing requirements to this technology. Additionally, both regulatory organisations and the industry are discussing the reliability of this technology, regarding common mode failures that may occur in redundant protection channels, due to the use of equipment and software with the same characteristics. The first part of this paper addresses the most important aspects of new international standards regarding classification criteria for I and C systems, equipment and functions, depending on their importance to safety and the design criteria applicable to each category. Special attention is drawn to requirements concerning software quality assurance and the design of new control rooms. The paper then goes on to discuss the different technical solutions being implemented, using equipment and software diversification, in order to prevent the possibility of common mode failures affecting the protection function. (Author)
Qualitative criteria and thresholds for low noise asphalt mixture design

Science.gov (United States)

Vaitkus, A.; Andriejauskas, T.; Gražulytė, J.; Šernas, O.; Vorobjovas, V.; Kleizienė, R.

2018-05-01

Low noise asphalt pavements are cost efficient and cost effective alternative for road traffic noise mitigation comparing with noise barriers, façade insulation and other known noise mitigation measures. However, design of low noise asphalt mixtures strongly depends on climate and traffic peculiarities of different regions. Severe climate regions face problems related with short durability of low noise asphalt mixtures in terms of considerable negative impact of harsh climate conditions (frost-thaw, large temperature fluctuations, hydrological behaviour, etc.) and traffic (traffic loads, traffic volumes, studded tyres, etc.). Thus there is a need to find balance between mechanical and acoustical durability as well as to ensure adequate pavement skid resistance for road safety purposes. Paper presents analysis of the qualitative criteria and design parameters thresholds of low noise asphalt mixtures. Different asphalt mixture composition materials (grading, aggregate, binder, additives, etc.) and relevant asphalt layer properties (air void content, texture, evenness, degree of compaction, etc.) were investigated and assessed according their suitability for durable and effective low noise pavements. Paper concluded with the overview of requirements, qualitative criteria and thresholds for low noise asphalt mixture design for severe climate regions.
Evaluation report(1): on design criteria for KALIMER metal fuel

International Nuclear Information System (INIS)

Hwang, Woan; Lee, Byoung Oon; Kim, Young Il

2001-04-01

Fuel rods, assembly ducts and their components in KALIMER should be designed to maintain the integrities and to assure their reliable in-reactor performances under the steady state and operational transient conditions which are included in design basis category. And the fuel system must be designed with enough engineering margin to minimize and prevent the failures under ab-normal operational condition, like an accident.In this report, some design limits and the criteria for the fuel assembly ducts for KALIMER are driven by evaluating the irradiation data of metallic fuel based on experimental data from ANL in USA, CRIEPI in Japan and RIAR in Russia
Evaluation report(1): on design criteria for KALIMER metal fuel

Energy Technology Data Exchange (ETDEWEB)

Hwang, Woan; Lee, Byoung Oon; Kim, Young Il

2001-04-01

Fuel rods, assembly ducts and their components in KALIMER should be designed to maintain the integrities and to assure their reliable in-reactor performances under the steady state and operational transient conditions which are included in design basis category. And the fuel system must be designed with enough engineering margin to minimize and prevent the failures under ab-normal operational condition, like an accident.In this report, some design limits and the criteria for the fuel assembly ducts for KALIMER are driven by evaluating the irradiation data of metallic fuel based on experimental data from ANL in USA, CRIEPI in Japan and RIAR in Russia.
78 FR 65007 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3

Science.gov (United States)

2013-10-30

... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00026; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria completion...
78 FR 53483 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3

Science.gov (United States)

2013-08-29

... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00025; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria (ITAAC) completion...
78 FR 53484 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 4

Science.gov (United States)

2013-08-29

... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00026; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 4 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria (ITAAC) completion...
The Bulimia Test--Revised: Validation with "DSM-IV" Criteria for Bulimia Nervosa.

Science.gov (United States)

Thelen, Mark H.; And Others

1996-01-01

The Bulimia Test--Revised (BULIT-R) was given to 23 female subjects who met the criteria for bulimia in the "Diagnostic and Statistical Manual of Mental Disorders" (DSM-IV) and 124 female controls. The BULIT-R appears to be a valid instruction for identifying individuals who meet DSM-IV criteria for bulimia. (SLD)
Criteria for the designation of radioactively contaminated land

International Nuclear Information System (INIS)

Titley, J.; Mobbs, S.; Burgess, P.; Hitchins, G.; Sinclair, P.

1999-01-01

This report examines the criteria for the designation of radioactively contaminated land. It should be read in conjunction with reference to another output from the project i.e. Environment Agency report, Technical Support Material for the Regulation of Radioactively Contaminated Land 1999. This report deals with the intervention on radioactively contaminated sites i.e. where no change of land use is anticipated and where the land has become contaminated as a result of previous land use and not current practices. (author)
An approach to development of structural design criteria for highly irradiated core components

International Nuclear Information System (INIS)

Nelson, D.V.

1980-01-01

The advent of the fast breeder reactor presents novel challenges in structural design and materials engineering. For instance, the core components of these reactors experience high energy neutron irradiation at elevated temperature, which causes significant time-dependent changes in material behaviour, such as a progressive loss of ductility. New structural design criteria are needed to extend elevated temperature design-by-analysis to account for these changes. Alloys best able to cope with the demands of the core operating environment are being explored and their structural behaviour characterized. The purpose of this paper is to illustrate an approach used in the development of core component structural design criteria. To do this, several design rules, plus brief rationale, from draft RDT Standards F9-7, -8 and -9 will be presented. These recently completed standards ('Structural Design Guidelines for Breeder Reactor Core Components') were prepared for the U.S. Department of Energy and represent a consensus among most organizations participating in the U.S. breeder program. (author)
Criteria for accepting piping thermal expansion movements during FFTF plant startup

International Nuclear Information System (INIS)

Clark, G.L.; Anderson, M.J.

1981-03-01

A deflection measurement program was conducted as a final step in the design qualification of the Fast Flux Test Facility liquid sodium piping. Measurements were obtained from the ambient empty position, through the 400 0 F (204 0 C) sodium fill, to an 800 0 F (427 0 C) maximum iso-thermal test condition. The program was designed to confirm that the pipe responded as predicted under both deadweight and thermal expansion loads. This paper describes the design of the test programs; the criteria used to select appropriate measurement locations from the approximately 4000 supports used on this pipe; and the criteria used to accept test results
Microseismic Monitoring Design Optimization Based on Multiple Criteria Decision Analysis

Science.gov (United States)

Kovaleva, Y.; Tamimi, N.; Ostadhassan, M.

2017-12-01

Borehole microseismic monitoring of hydraulic fracture treatments of unconventional reservoirs is a widely used method in the oil and gas industry. Sometimes, the quality of the acquired microseismic data is poor. One of the reasons for poor data quality is poor survey design. We attempt to provide a comprehensive and thorough workflow, using multiple criteria decision analysis (MCDA), to optimize planning micriseismic monitoring. So far, microseismic monitoring has been used extensively as a powerful tool for determining fracture parameters that affect the influx of formation fluids into the wellbore. The factors that affect the quality of microseismic data and their final results include average distance between microseismic events and receivers, complexity of the recorded wavefield, signal-to-noise ratio, data aperture, etc. These criteria often conflict with each other. In a typical microseismic monitoring, those factors should be considered to choose the best monitoring well(s), optimum number of required geophones, and their depth. We use MDCA to address these design challenges and develop a method that offers an optimized design out of all possible combinations to produce the best data acquisition results. We believe that this will be the first research to include the above-mentioned factors in a 3D model. Such a tool would assist companies and practicing engineers in choosing the best design parameters for future microseismic projects.
Design loads, loading combinations and structural acceptance criteria for BWR containments in the United States

International Nuclear Information System (INIS)

Edwards, N.W.

1979-01-01

The definition of loads, loading combinations, and structural acceptance criteria used for the design and evaluation of BWR containments in the Unites States has become much more comprehensive over the past decade. The Mark I pressure suppression containment vessels were designed for a static design pressure, a design temperature, dead load and static equivalent earthquake. The current Mark III containments are being designed to accommodate many more loads such as safety relief valve discharge loads, and suppression pool hydrodynamic loadings associated with the steam condensation phenomena as well as pressure and temperature transients for a range of pipe break sizes. Consistent with the more comprehensive definition of loads and loading combinations, the ASME Code presently establishes structural acceptance criteria with different margins of safety by the definition of Service Level Assignments A, B, C and D. Acting in a responsible manner, United States utilities are currently evaluating and modifying existing containment vessels to account for the more detailed load definition and structural acceptance criteria. (orig.)
Functional design criteria for the self-installing liquid observation well. Revision 2

International Nuclear Information System (INIS)

Parra, S.A.

1995-01-01

This document presents the functional design criteria for installing liquid observation wells (LOWs) into single-shell tanks containing ferrocyanide or organic wastes. The LOWs will be designed to accommodate the deployment of gamma, neutron, and electromagnetic induction probes and to interface with the existing tank structure and environment
Impact of ANSI 2009 criteria for performance testing in TLD personnel monitoring

International Nuclear Information System (INIS)

MeenaI, P.; Rakesh, R.B.; Srivastava, Kshama; KoIambe, D.H.; Sapra, B.K.

2014-01-01

External Quality Assurance in TLD Personnel Monitoring Service was initiated in 1985, for periodic performance evaluation of various TLD Laboratories through postal exercise. Presently, all the 16 laboratories involved in Personnel Monitoring Service are covered under QA exercise. Since beginning, American National Standards Institute (ANSI) criteria have been adopted for performance testing in QA exercise. Presently, ANSI 2001 performance criteria along with ISO trumpet curve analysis method are being used for performance evaluation. In 2009, ANSI modified the performance evaluation criteria and this study evaluates its impact and feasibility of implementation of ANSI 2009 criteria in the quality assurance program for personnel monitoring. The performance of some laboratories evaluated using both ANSI 2001 and ANSI 2009 criteria have been discussed. The study shows that the ANSI 2009 criteria is more stringent and encourages even distribution of bias and standard deviation. This can be implemented with suitable modifications for performance evaluation
Development of nuclear design criteria for neutron spallation sources

Energy Technology Data Exchange (ETDEWEB)

Sordo, F.; Abanades, A. [E.T.S. Industriales, Madrid Polytechnic University, UPM, J.Gutierrez Abascal, 2 -28006 Madrid (Spain)

2008-07-01

Spallation neutron sources allow obtaining high neutronic flux for many scientific and industrial applications. In recent years, several proposals have been made about its use, notably the European Spallation Source (ESS), the Japanese Spallation Source (JSNS) and the projects of Accelerator-Driven Subcritical reactors (ADS), particularly in the framework of EURATOM programs. Given their interest, it seems necessary to establish adequate design basis for guiding the engineering analysis and construction projects of this kind of installations. In this sense, all works done so far seek to obtain particular solutions to a particular design, but there has not been any general development to set up an engineering methodology in this field. In the integral design of a spallation source, all relevant physical processes that may influence its behaviour must be taken into account. Neutronic aspects (emitted neutrons and their spectrum, generation performance..), thermomechanical (energy deposition, cooling conditions, stress distribution..), radiological (spallation waste activity, activation reactions and residual heat) and material properties alteration due to irradiation (atomic displacements and gas generation) must all be considered. After analysing in a systematic manner the different options available in scientific literature, the main objective of this thesis was established as making a significant contribution to determine the limiting factors of the main aspects of spallation sources, its application range and the criteria for choosing optimal materials. To achieve this goal, a series of general simulations have been completed, covering all the relevant physical processes in the neutronic and thermal-mechanical field. Finally, the obtained criteria have been applied to the particular case of the design of the spallation source of subcritical reactors PDX-ADS and XT-ADS. These two designs, developed under the European R and D Framework Program, represent nowadays
Development of nuclear design criteria for neutron spallation sources

International Nuclear Information System (INIS)

Sordo, F.; Abanades, A.

2008-01-01

Spallation neutron sources allow obtaining high neutronic flux for many scientific and industrial applications. In recent years, several proposals have been made about its use, notably the European Spallation Source (ESS), the Japanese Spallation Source (JSNS) and the projects of Accelerator-Driven Subcritical reactors (ADS), particularly in the framework of EURATOM programs. Given their interest, it seems necessary to establish adequate design basis for guiding the engineering analysis and construction projects of this kind of installations. In this sense, all works done so far seek to obtain particular solutions to a particular design, but there has not been any general development to set up an engineering methodology in this field. In the integral design of a spallation source, all relevant physical processes that may influence its behaviour must be taken into account. Neutronic aspects (emitted neutrons and their spectrum, generation performance..), thermomechanical (energy deposition, cooling conditions, stress distribution..), radiological (spallation waste activity, activation reactions and residual heat) and material properties alteration due to irradiation (atomic displacements and gas generation) must all be considered. After analysing in a systematic manner the different options available in scientific literature, the main objective of this thesis was established as making a significant contribution to determine the limiting factors of the main aspects of spallation sources, its application range and the criteria for choosing optimal materials. To achieve this goal, a series of general simulations have been completed, covering all the relevant physical processes in the neutronic and thermal-mechanical field. Finally, the obtained criteria have been applied to the particular case of the design of the spallation source of subcritical reactors PDX-ADS and XT-ADS. These two designs, developed under the European R and D Framework Program, represent nowadays
Integral Criteria for Measuring the Quality of Teacher Evaluation

Directory of Open Access Journals (Sweden)

Olga Navickienė

2012-07-01

Full Text Available Purpose—To construct the knowledge evaluation quality integral criteria, which allows to ascertain whether the different teachers properly assess the students’ knowledge. The criteria has been tested setting up the educational experiment and examining the six mathematics lecturers’ assessments.Design/methodology/approach—This research involved the Mykolas Romeris University students of Public Administration degree second year and Management of Organizations degree first year. The test questions for students were designed using the mathematical knowledge assessment information system, which allows for closed-ended mathematical test, to obtain statistical data about test takers, to perform quality analysis of the test; in the middle and the end of the semester.Findings—The construction technique for the evaluation quality criteria of the students’ working results assessment, which were performed by six different lecturers, during practical trainings, seminars, laboratory and other sessions is proposed in this article.Research limitations/implications—The constructed evaluation criteria is universal: it does not depend on the particular subject; it can be applied to several groups, courses or lecturers. It depends on three calculated indicators I, S, K, which show in two ways obtained estimates of the measured information compatibility of degrees, marks matching and correlation terms.Practical implications—The integral criteria has been tested examining the six mathematics lecturers’ assessments.Originality/Value—Constructing the criteria have been used the educational measurement models of authors of this article and other researchers, however its’ connection to general (integral criteria, best of authors’ knowledge, is original and have not be researched before.Keywords: knowledge evaluation, quality of teacher evaluation, evaluation of teachers, mathematical modeling.Research type: research paper.
Guidance for Developing Principal Design Criteria for Advanced (Non-Light Water) Reactors

Energy Technology Data Exchange (ETDEWEB)

Holbrook, Mark [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kinsey, Jim [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-03-01

In July 2013, the US Department of Energy (DOE) and US Nuclear Regulatory Commission (NRC) established a joint initiative to address a key portion of the licensing framework essential to advanced (non-light water) reactor technologies. The initiative addressed the “General Design Criteria for Nuclear Power Plants,” Appendix A to10 Code of Federal Regulations (CFR) 50, which were developed primarily for light water reactors (LWRs), specific to the needs of advanced reactor design and licensing. The need for General Design Criteria (GDC) clarifications in non-LWR applications has been consistently identified as a concern by the industry and varied stakeholders and was acknowledged by the NRC staff in their 2012 Report to Congress1 as an area for enhancement. The initiative to adapt GDC requirements for non-light water advanced reactor applications is being accomplished in two phases. Phase 1, managed by DOE, consisted of reviews, analyses and evaluations resulting in recommendations and deliverables to NRC as input for NRC staff development of regulatory guidance. Idaho National Laboratory (INL) developed this technical report using technical and reactor technology stakeholder inputs coupled with analysis and evaluations provided by a team of knowledgeable DOE national laboratory personnel with input from individual industry licensing consultants. The DOE national laboratory team reviewed six different classes of emerging commercial reactor technologies against 10 CFR 50 Appendix A GDC requirements and proposed guidance for their adapted use in non-LWR applications. The results of the Phase 1 analysis are contained in this report. A set of draft Advanced Reactor Design Criteria (ARDC) has been proposed for consideration by the NRC in the establishment of guidance for use by non-LWR designers and NRC staff. The proposed criteria were developed to preserve the underlying safety bases expressed by the original GDC, and recognizing that advanced reactors may take

Wind Generators Test Bench. Optimal Design of PI Controller

Directory of Open Access Journals (Sweden)

TUDORACHE, T.

2011-08-01

Full Text Available This paper proposes a novel and robust strategy for the optimal design of the drive system integrated in a wind generators test bench. The PI regulator coefficients used in control systems are usually computed based on simplified hypotheses and then tuned manually so as the system response meet certain specifications in terms of stability, accuracy and speed. The proposed methodology permits the automatic identification of PI regulator coefficients using intelligent optimization algorithms, the initial guess for the search procedure being determined based on particular simplified hypotheses. The proposed procedure can help the design engineers to drastically reduce the effort for finding the best PI regulator coefficients offering a range of feasible solutions depending on the imposed optimum criteria. The characteristics and performances of the optimization strategy are highlighted by using it for the design of a DC motor drive system used to simulate the wind prime mover integrated in a wind generators test bench.
Argentine criteria on nuclear safety and emergencies: their impact on the Argos PHWR 380 design

International Nuclear Information System (INIS)

Gonzalez, A. J.

1988-01-01

This paper describes first the safety criteria of the Argentine regulatory authority with emphasis on the probabilistic safety criteria based on a limitation of individual risks. Then, it is presented a discussion on emergency criteria in relation to evacuation and relocation measures. Finally, the paper briefly describes the design of an Argentine offer for a safer heavy water reactor where these criteria are applied. 9 figs., 1 tab., 46 refs. (author)
Sustainable and safe design of footwear integrating ecological footprint and risk criteria.

Science.gov (United States)

Herva, Marta; Álvarez, Antonio; Roca, Enrique

2011-09-15

The ecodesign of a product implies that different potential environmental impacts of diverse nature must be taken into account considering its whole life cycle, apart from the general design criteria (i.e. technical, functional, ergonomic, aesthetic or economic). In this sense, a sustainability assessment methodology, ecological footprint (EF), and environmental risk assessment (ERA), were combined for the first time to derive complementary criteria for the ecodesign of footwear. Four models of children's shoes were analyzed and compared. The synthetic shoes obtained a smaller EF (6.5 gm(2)) when compared to the leather shoes (11.1 gm(2)). However, high concentrations of hazardous substances were detected in the former, even making the Hazard Quotient (HQ) and the Cancer Risk (CR) exceed the recommended safety limits for one of the synthetic models analyzed. Risk criteria were prioritized in this case and, consequently, the design proposal was discarded. For the other cases, the perspective provided by the indicators of different nature was balanced to accomplish a fairest evaluation. The selection of fibers produced under sustainable criteria and the reduction of the materials consumption was recommended, since the area requirements would be minimized and the absence of hazardous compounds would ensure safety conditions during the use stage. Copyright © 2011 Elsevier B.V. All rights reserved.
Advanced concepts, analysis approaches and criteria for nuclear piping system design

International Nuclear Information System (INIS)

Tang, H.T.; Tagart, S.W. Jr.; Tang, Y.K.

1992-01-01

Recent research in piping system design and analysis has resulted in advancements on damping values, independent support motion (ISM), static coefficient method, simplified inelastic method and ASME code criteria changes. In the support area, passive type of supports such as energy-absorbing device and gap stopper have been developed. These advancements provide bases for improved and cost-effective design of future nuclear piping systems. (author)
Development of biological criteria for the design of advanced hydropower turbines

Energy Technology Data Exchange (ETDEWEB)

Cada, Glenn F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Coutant, Charles C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Whitney, Richard R. [Leavenworth, WA (United States)

1997-03-01

A review of the literature related to turbine-passage injury mechanisms suggests the following biological criteria should be considered in the design of new turbines: (1) pressure; (2) cavitation; (3) shear and turbulence; and (4) mechanical injury. Based on the study’s review of fish behavior in relation to hydropower facilities, it provides a number of recommendations to guide both turbine design and additional research.
Conceptual framework for potential implementations of multi criteria decision making (MCDM) methods for design quality assessment

NARCIS (Netherlands)

Harputlugil, T.; Prins, M.; Tanju Gültekin, A.; Ilker Topçu, Y.

2011-01-01

Architectural design can be considered as a process influenced by many stakeholders, each of which has different decision power. Each stakeholder might have his/her own criteria and weightings depending on his/her own perspective and role. Hence design can be seen as a multi-criteria decision making
Multi-Canister Overpack (MCO) Combustible Gas Management Leak Test Acceptance Criteria (OCRWM)

International Nuclear Information System (INIS)

SHERRELL, D.L.

2000-01-01

The purpose of this document is to support the Spent Nuclear Fuel Project's combustible gas management strategy while avoiding the need to impose any requirements for oxygen free atmospheres within storage tubes that contain multi-canister overpacks (MCO). In order to avoid inerting requirements it is necessary to establish and confirm leak test acceptance criteria for mechanically sealed and weld sealed MCOs that are adequte to ensure that, in the unlikely event the leak test results for any MCO were to approach either of those criteria, it could still be handled and stored in stagnant air without compromising the SNF Project's overall strategy to prevent accumulation of combustible gas mixtures within MCOs or within their surroundings. To support that strategy, this document: (1) establishes combustible gas management functions and minimum functional requirements for the MCO's mechanical seals and closure weld(s); (2) establishes a maximum practical value for the minimum required initial MCO inert backfill gas pressure; and (3) based on items 1 and 2, establishes and confirms leak test acceptance criteria for the MCO's mechanical seal and final closure weld(s)
Probabilistic Evaluation of Eurocode 5 Fire Design Criteria of a ...

African Journals Online (AJOL)

Structural reliability analysis for a three-hinge timber portal frame subjected to fire was undertaken. Eight modes of failure were identified for the frame and limit state function was formulated for each failure mode. The limit state functions were based on the Eurocode 5 design criteria. Uncertainties in the timber material ...
Implementation of decommissioning criteria in the conceptual design of the MRS facility

International Nuclear Information System (INIS)

Gross, D.L.; Wilcox, A.D.; Huang, S.

1986-01-01

The US Department of Energy (DOE) selected the Ralph M. Parsons Company (RMP) to prepare the conceptual design of the Monitored Retrievable Storage (MRS) Facility. The purpose of this facility is to consolidate and temporarily store spent fuel from civilian nuclear power plants. In addition, it will overpack, handle, and store high-level radioactive waste from non-defense related sources. The Functional Design Criteria (FDC) prepared by Pacific Northwest Laboratories, as well as 10 CFR 72, requires the facility to be designed for decommissioning, with provisions to facilitate decontamination of structures and equipment to minimize the volume of radioactive wastes and contaminated equipment at the time of decommissioning. Many problems associated with decommissioning a nuclear facility have been identified in recent years and the design for the MRS Facility presents a unique opportunity for RMP to implement decommissioning criteria into the conceptual design of a major nuclear facility. The provisions made in the design to facilitate decommissioning include good housekeeping during operations, controlled personnel access, access for equipment removal, equipment design, installed radiation monitors, adequate work space, installed decontamination systems and areas, control of all effluents, and operational documentation. These topics will be the major points of discussion for this paper
Study-design selection criteria in systematic reviews of effectiveness of health systems interventions and reforms: A meta-review.

Science.gov (United States)

Rockers, Peter C; Feigl, Andrea B; Røttingen, John-Arne; Fretheim, Atle; de Ferranti, David; Lavis, John N; Melberg, Hans Olav; Bärnighausen, Till

2012-03-01

At present, there exists no widely agreed upon set of study-design selection criteria for systematic reviews of health systems research, except for those proposed by the Cochrane Collaboration's Effective Practice and Organisation of Care (EPOC) review group (which comprises randomized controlled trials, controlled clinical trials, controlled before-after studies, and interrupted time series). We conducted a meta-review of the study-design selection criteria used in systematic reviews available in the McMaster University's Health Systems Evidence or the EPOC database. Of 414 systematic reviews, 13% did not indicate any study-design selection criteria. Of the 359 studies that described such criteria, 50% limited their synthesis to controlled trials and 68% to some or all of the designs defined by the EPOC criteria. Seven out of eight reviews identified at least one controlled trial that was relevant for the review topic. Seven percent of the reviews included either no or only one relevant primary study. Our meta-review reveals reviewers' preferences for restricting synthesis to controlled experiments or study designs that comply with the EPOC criteria. We discuss the advantages and disadvantages of the current practices regarding study-design selection in systematic reviews of health systems research as well as alternative approaches. Copyright © 2012. Published by Elsevier Ireland Ltd.
Proficiency testing criteria for clearance level in solid waste gamma measurement in Taiwan

International Nuclear Information System (INIS)

Chen, Chun-Liang; Wang, Jeng-Jong; Chiu, Huang-Sheng

2013-01-01

To guarantee the measurement quality for clearance level in solid waste material, the Institute of Nuclear Energy Research (INER) established the criteria for proficiency testing of clearance level measurement. INER and the Taiwan Accreditation Foundation (TAF) organized the Technique Committee Meeting twice to discuss these criteria in 2011. The participating laboratories must completely conform to the ISO/IEC 17025, and they also must meet the requirements of the criteria. According to the criteria, the participating laboratories analyzed the minimum detectable amount (MDA) and that should be less than 20% of the clearance level (AMDA) given in the Atomic Energy Council's (AEC) “Regulations on Clearance Level for Radioactive Waste Management”. The testing results should conform to the deviation and traceability requirements. - Highlights: • The participating laboratories must completely conform to the ISO/IEC 17025 • The proficiency testing items were basically in two categories, box and barrel types • Analyzed the MDA and that should be less than 20% of the release level given in the AEC. • The are three limitations: MDA< AMDA, -0.25< Bi<+0.5, and En≤1.0 and uncertainty<20%
Physical criteria for the design and assessment of restoration schemes in the United Kingdom

International Nuclear Information System (INIS)

Humphries, R.N.; McQuire, G.E.

1994-01-01

The restoration of colliery wastes and open pit coal sites in the United Kingdom (UK) is undertaken according to a land use strategy plan and detailed specifications that have been agreed upon with the planning authorities. For two of the major land uses in the UK, agriculture and forestry, data on physical criteria (climate, site features and soils) are available to assist in the planning and design of land use strategies and specification of restoration treatments. Similar criteria could also be developed for the restoration of semi natural vegetation and habitats for landscape, wildlife, and amenity uses. Three examples are described illustrating the use of the physical criteria in the design of schemes, the specification of treatments, and the assessment of achievements
Seismic re-evaluation criteria for Bohunice V1 reconstruction

International Nuclear Information System (INIS)

Campbell, R.; Schlund, H.; Warnken, L.

2001-01-01

Bohunice V1 in Slovakia is a Russian designed two unit WWER 440, Model 230 Pressurized Water Reactor. The plant was not originally designed for earthquake. Subsequent and ongoing reassessments now confirm that the seismic hazard at the site is significant. EBO, the plant owner has contracted with a consortium lead by Siemens AG (REKON) to do major reconstruction of the plant to significantly enhance its safety systems by the addition of new systems and the upgrading of existing systems. As part of the reconstruction, a complete seismic assessment and upgrading is required for existing safety relevant structures, systems and components. It is not practical to conduct this reassessment and upgrading using criteria applied to new design of nuclear power plants. Alternate criteria may be used to achieve adequate safety goals. Utilities in the U.S. have faced several seismic issues with operating NPPs and to resolve these issues, alternate criteria have been developed which are much more cost effective than use of criteria for new design. These alternate criteria incorporate the knowledge obtained from investigation of the performance of equipment in major earthquakes and include provisions for structures and passive equipment to deform beyond the yield point, yet still provide their essential function. IAEA has incorporated features of these alternate criteria into draft Technical Guidelines for application to Bohunice V1 and V2. REKON has developed plant specific criteria and procedures for the Bohunice V1 reconstruction that incorporate major features of the U.S. developed alternate criteria, comply to local codes and which envelop the draft IAEA Technical Guidelines. Included in these criteria and procedures are comprehensive walkdown screening criteria for equipment, piping, HVAC and cable raceways, analytical criteria which include inelastic energy absorption factors defined on an element basis and testing criteria which include specific guidance on interpretation
Sustainable and safe design of footwear integrating ecological footprint and risk criteria

International Nuclear Information System (INIS)

Herva, Marta; Alvarez, Antonio; Roca, Enrique

2011-01-01

Highlights: → The ecological footprint (EF) is a suitable screening indicator to assist the assessment of the sustainability of an ecodesign proposal. → The EF does not consider the risk derived from hazardous substances in its evaluation. → Environmental risk assessment (ERA) successfully complemented the evaluation of the EF providing safety criteria. → Options that exceeded the safety limits for Hazard Quotient and Cancer Risk where discarded, thus guaranteeing the protection of children. → Trade-offs among criteria could be established by the application of fuzzy logic techniques to derive an ecodesign index. - Abstract: The ecodesign of a product implies that different potential environmental impacts of diverse nature must be taken into account considering its whole life cycle, apart from the general design criteria (i.e. technical, functional, ergonomic, aesthetic or economic). In this sense, a sustainability assessment methodology, ecological footprint (EF), and environmental risk assessment (ERA), were combined for the first time to derive complementary criteria for the ecodesign of footwear. Four models of children's shoes were analyzed and compared. The synthetic shoes obtained a smaller EF (6.5 gm 2 ) when compared to the leather shoes (11.1 gm 2 ). However, high concentrations of hazardous substances were detected in the former, even making the Hazard Quotient (HQ) and the Cancer Risk (CR) exceed the recommended safety limits for one of the synthetic models analyzed. Risk criteria were prioritized in this case and, consequently, the design proposal was discarded. For the other cases, the perspective provided by the indicators of different nature was balanced to accomplish a fairest evaluation. The selection of fibers produced under sustainable criteria and the reduction of the materials consumption was recommended, since the area requirements would be minimized and the absence of hazardous compounds would ensure safety conditions during the
Sustainable and safe design of footwear integrating ecological footprint and risk criteria

Energy Technology Data Exchange (ETDEWEB)

Herva, Marta [Sustainable Processes and Products Engineering Group, Department of Chemical Engineering, University of Santiago de Compostela, Campus Vida, 15705 Santiago de Compostela (Spain); Alvarez, Antonio [Industrias de Diseno Textil, S.A., Edificio Inditex, Av. de la Diputacion s/n, Poligono de Sabon, 15142 Arteixo - A Coruna (Spain); Roca, Enrique, E-mail: enrique.roca@usc.es [Sustainable Processes and Products Engineering Group, Department of Chemical Engineering, University of Santiago de Compostela, Campus Vida, 15705 Santiago de Compostela (Spain)

2011-09-15

Highlights: {yields} The ecological footprint (EF) is a suitable screening indicator to assist the assessment of the sustainability of an ecodesign proposal. {yields} The EF does not consider the risk derived from hazardous substances in its evaluation. {yields} Environmental risk assessment (ERA) successfully complemented the evaluation of the EF providing safety criteria. {yields} Options that exceeded the safety limits for Hazard Quotient and Cancer Risk where discarded, thus guaranteeing the protection of children. {yields} Trade-offs among criteria could be established by the application of fuzzy logic techniques to derive an ecodesign index. - Abstract: The ecodesign of a product implies that different potential environmental impacts of diverse nature must be taken into account considering its whole life cycle, apart from the general design criteria (i.e. technical, functional, ergonomic, aesthetic or economic). In this sense, a sustainability assessment methodology, ecological footprint (EF), and environmental risk assessment (ERA), were combined for the first time to derive complementary criteria for the ecodesign of footwear. Four models of children's shoes were analyzed and compared. The synthetic shoes obtained a smaller EF (6.5 gm{sup 2}) when compared to the leather shoes (11.1 gm{sup 2}). However, high concentrations of hazardous substances were detected in the former, even making the Hazard Quotient (HQ) and the Cancer Risk (CR) exceed the recommended safety limits for one of the synthetic models analyzed. Risk criteria were prioritized in this case and, consequently, the design proposal was discarded. For the other cases, the perspective provided by the indicators of different nature was balanced to accomplish a fairest evaluation. The selection of fibers produced under sustainable criteria and the reduction of the materials consumption was recommended, since the area requirements would be minimized and the absence of hazardous compounds would
Design of high temperature Engineering Test Reactor (HTTR)

International Nuclear Information System (INIS)

Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio

1994-09-01

Construction of High Temperature Engineering Test Reactor (HTTR) is now underway to establish and upgrade basic technologies for HTGRs and to conduct innovative basic research at high temperatures. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30 MW in thermal output and outlet coolant temperature of 850degC for rated operation and 950degC for high temperature test operation. It is planned to conduct various irradiation tests for fuels and materials, safety demonstration tests and nuclear heat application tests. JAERI received construction permit of HTTR reactor facility in February 1990 after 22 months of safety review. This report summarizes evaluation of nuclear and thermal-hydraulic characteristics, design outline of major systems and components, and also includes relating R and D result and safety evaluation. Criteria for judgment, selection of postulated events, major analytical conditions for anticipated operational occurrences and accidents, computer codes used in safety analysis and evaluation of each event are presented in the safety evaluation. (author)
Design criteria for the light duty utility arm system end effectors

International Nuclear Information System (INIS)

Pardini, A.F.

1995-01-01

This document provides the criteria for the design of end effectors that will be used as part of the Light Duty Utility Arm (LDUA) System. The LDUA System consists of a deployment vehicle, a vertical positioning mast, a light duty multi-axis robotic arm, a tank riser interface and confinement, a tool interface plate, a control system, and an operations control trailer. The criteria specified in this document will apply to all end effector systems being developed for use on or with the LDUA system at the Hanford site. The requirement stipulated in this document are mandatory
Applications of Logic Coverage Criteria and Logic Mutation to Software Testing

Science.gov (United States)

Kaminski, Garrett K.

2011-01-01

Logic is an important component of software. Thus, software logic testing has enjoyed significant research over a period of decades, with renewed interest in the last several years. One approach to detecting logic faults is to create and execute tests that satisfy logic coverage criteria. Another approach to detecting faults is to perform mutation…
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
Studies on design principles and criteria of fuels and graphites for experimental multi-purpose very high temperature reactor

International Nuclear Information System (INIS)

Arai, Taketoshi; Sato, Sadao; Tani, Yutaro

1977-12-01

Design principles and criteria of fuels and graphites have been studied to determine the main design parameters of a reference core MARK-III of the Experimental Multi-purpose Very High Temperature Reactor. The present status of research and development for HTGR fuels and graphites is reviewed from a standpoint of their integrity and safety aspects, and is compared to the specific design requirements for the VHTR fuels and graphites. Consequently, reasonable materials specifications, safety criteria and design analysis methods are presented for coated fuel particle, fuel compact, graphite sleeve, core support graphite and neutron absorber material. These design principles and criteria will be refined by further experimental investigations. (auth.)

Inelastic analysis acceptance criteria for radioactive material transportation containers

International Nuclear Information System (INIS)

Ammerman, D.J.; Ludwigsen, J.S.

1993-01-01

The design criteria currently used in the design of radioactive material (RAM) transportation containers are taken from the ASME Boiler and Pressure Vessel Code (ASME, 1992). These load-based criteria are ideally suited for pressure vessels where the loading is quasistatic and all stresses are in equilibrium with externally applied loads. For impact events, the use of load-based criteria is less supportable. Impact events tend to be energy controlled, and thus, energy-based acceptance criteria would appear to be more appropriate. Determination of an ideal design criteria depends on what behavior is desired. Currently there is not a design criteria for inelastic analysis for RAM nation packages that is accepted by the regulatory agencies. This lack of acceptance criteria is one of the major factors in limiting the use of inelastic analysis. In this paper inelastic analysis acceptance criteria based on stress and strain-energy density will be compared for two stainless steel test units subjected to impacts onto an unyielding target. Two different material models are considered for the inelastic analysis, a bilinear fit of the stress-strain curve and a power law hardening model that very closely follows the stress-strain curve. It is the purpose of this paper to stimulate discussion and research into the area of strain-energy density based inelastic analysis acceptance criteria
ITER structural design criteria and their extension to advanced reactor blankets

International Nuclear Information System (INIS)

Majumdar, S.; Kalinin, G.

2000-01-01

Applications of the recent ITER structural design criteria (ISDC) are illustrated by two components. First, the low-temperature-design rules are applied to copper alloys that are particularly prone to irradiation embrittlement at relatively low fluences at certain temperatures. Allowable stresses are derived and the impact of the embrittlement on allowable surface heat flux of a simple first-wall/limiter design is demonstrated. Next, the high-temperature-design rules of ISDC are applied to evaporation of lithium and vapor extraction (EVOLVE), a blanket design concept currently being investigated under the US Advanced Power Extraction (APEX) program. A single tungsten first-wall tube is considered for thermal and stress analyses by finite-element method
Vision-based methodology for collaborative management of qualitative criteria in design

DEFF Research Database (Denmark)

Tollestrup, Christian

2006-01-01

establishes a field of tension that summarises the abstract criteria and pinpoints the desired uniqueness of the product. The Interaction Vision allows the team members to design the behaviour of the product without deciding on physical features, thus focusing on the cognitive aspects of the product...
The design and testing of sodium pumps in the UK to meet the CDFR cavitation criteria

International Nuclear Information System (INIS)

Preece, G.E.; Macleod, I.D.; Wilkinson, D.

2002-01-01

A primary objective in the design of the sodium pumps for the UK Commercial Demonstration Fast Reactor has been to avoid cavitation during normal operation. This requirement arises from the need to avoid blade erosion and also, in the case of the Primary Sodium Pumps (PSP), the generation of cavitation noise which might otherwise interfere with instrumentation installed to detect noise of boiling in the core. This paper outlines the approach adopted to achieve a pump design with good cavitation performance and the programme of model testing carried out in a water loop to establish the cavitation boundaries for incipient cavitation of selected designs using both visual and acoustic techniques
Monitoring programmes for internal exposure: designing criteria

International Nuclear Information System (INIS)

Rojo, Ana M.; Gomez Parada, Ines.

2007-01-01

The purpose of this document is to offer guidance for the decision whether a monitoring programme is required and how it should be designed. It can be also used as a tool for making the standing programmes consistent with the most recent publications on internal dosimetry, such as ISO 20553 'Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material', specific publications of the IAEA and ICRP, and including the conclusions of the OMINEX Project ('Optimisation of Monitoring for Internal Exposures') and IDEAS Project. It is established that the general purpose of the monitoring is verify that each worker is protected adequately against risks from radionuclide intakes and document that the protection complies with legal requirements. The criteria for a particular monitoring programme designing is based on the magnitude of the probable intake and the possibility of detecting a significant event when it occurs. So, the risk assessment for each work process must be evaluated and each worker is classified accordingly. This classification implies the acceptance of reference effective dose values (1 y 6 mSv/y ). (author) [es
Criteria for initiation of delamination in quasi-static punch-shear tests of a carbon-fiber composite material.

Energy Technology Data Exchange (ETDEWEB)

Chin, Eric Brian [Sandia National Lab. (SNL-CA), Livermore, CA (United States); English, Shawn Allen [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Briggs, Timothy [Sandia National Lab. (SNL-CA), Livermore, CA (United States)

2015-09-01

V arious phenomenological delamination initiation criteria are analyzed in quasi - static punch - shear tests conducted on six different geometries. These six geometries are modeled and analyzed using elastic, large - deformation finite element analysis. Analysis output is post - processed to assess different delamination initiation criteria, and their applicability to each of the geometries. These criteria are compared to test results to assess whether or not they are appropriate based on what occurred in testing. Further, examinations of CT scans and ultrasonic images o f test specimens are conducted in the appendix to determine the sequence of failure in each test geometry.
Design Driven Testing Test Smarter, Not Harder

CERN Document Server

Stephens, M

2010-01-01

The groundbreaking book Design Driven Testing brings sanity back to the software development process by flipping around the concept of Test Driven Development (TDD) - restoring the concept of using testing to verify a design instead of pretending that unit tests are a replacement for design. Anyone who feels that TDD is "Too Damn Difficult" will appreciate this book. Design Driven Testing shows that, by combining a forward-thinking development process with cutting-edge automation, testing can be a finely targeted, business-driven, rewarding effort. In other words, you'll learn how to test
General design criteria for diesel-generator sets for nuclear power plants

International Nuclear Information System (INIS)

Rangarao, G.

1975-01-01

The design criteria for diesel-generators for nuclear power plants are examined. Applicable standards, loading, design performance, and characteristics to be considered in the selection of diesel-generator set and its auxiliary system are discussed. Also, engineered safety features loads together with loss of power safe shutdown loads and their starting sequence, analysis of voltage and frequency response and the diesel-generator ability to start various load blocks successfully to meet the reactor emergency core cooling requirements are discussed
The 1994 Forum on Appropriate Criteria and Methods for Seismic Design of Nuclear Piping

International Nuclear Information System (INIS)

Slagis, G.C.

1995-01-01

A record of the 1994 Forum on Appropriate Criteria and Methods for Seismic Design of Nuclear Piping is provided. The focus of the forum was the design-by-rule method for seismic design of piping. Issues such as acceptance criteria, ductility considerations, demonstration of margin, training, verification and costs were discussed. The use of earthquake experience data, including the recent Northridge earthquake, to justify a design-by-rule method was explored. The majority of the participants felt there are not significant advantages to developing a design-by-rule approach for new plant design. One major disadvantage was considered by many to be training. Extensive training will be required to properly implement a design-by-rule approach. Verification of designs was considered by the majority to be equally important for design-by-rule as for design-by-analysis. If a design-by-rule method is going to be effective, the method will have to be based on ductility considerations (UBC approach). A significant issue will be justification of seismic margins with liberal rules. The UBC approach is being questioned by some because of the recent structural cracking problems in the Northridge earthquake
Interpretive criteria for mupirocin susceptibility testing of Staphylococcus spp. using CLSI guidelines.

LENUS (Irish Health Repository)

Creagh, S

2012-02-03

Mupirocin is an antimicrobial agent commonly used to treat staphylococcal infection or to eliminate persistent carriage. To date, interpretive criteria have not been established to define susceptibility or resistance when performing mupirocin susceptibility testing. In this evaluation, using CLSI guidelines, a total of 502 staphylococci comprising 219 methicillin-sensitive Staphylococcus aureus, 222 methicillin-resistant S. aureus and 61 coagulase-negative staphylococci are tested by broth microdilution, disc diffusion and E-test. Disc diffusion using 5 microg mupirocin discs was found to be a reliable method to distinguish susceptible and resistant strains. Minimum inhibitory concentration (MIC) determination was required to differentiate low-level and high-level resistance to mupirocin. E-test was found to be an accurate alternative to broth microdilution for the routine determination of MIC values of staphylococci to mupirocin. Broth microdilution and disc-diffusion results were plotted on a scattergram, and error rates were calculated. No errors were found using susceptibility criteria of < 4 microg\\/mL (MIC) and > 19 mm (zone diameter).
Seismic design criteria and their application to major hazard plant within the United Kingdom

International Nuclear Information System (INIS)

Alderson, M.A.H.G.

1982-12-01

The nature of seismic motions and the implications are briefly described and the development of seismic design criteria for nuclear power plants in various countries is described including possible future developments. The seismicity of the United Kingdom is briefly reviewed leading to the present position on seismic design criteria for nuclear power plants within the United Kingdom. Damage from past destructive earthquakes is reviewed and the existing codes of practice and standards are described. Finally the effect of earthquakes on major hazard plant is discussed in general terms including the seismic analysis of a typical plant item. (author)
Criteria required for an acceptable point-of-care test for UTI detection: Obtaining consensus using the Delphi technique.

Science.gov (United States)

Weir, Nichola-Jane M; Pattison, Sally H; Kearney, Paddy; Stafford, Bob; Gormley, Gerard J; Crockard, Martin A; Gilpin, Deirdre F; Tunney, Michael M; Hughes, Carmel M

2018-01-01

Urinary Tract Infections (UTIs) are common bacterial infections, second only to respiratory tract infections and particularly prevalent within primary care. Conventional detection of UTIs is culture, however, return of results can take between 24 and 72 hours. The introduction of a point of care (POC) test would allow for more timely identification of UTIs, facilitating improved, targeted treatment. This study aimed to obtain consensus on the criteria required for a POC UTI test, to meet patient need within primary care. Criteria for consideration were compiled by the research team. These criteria were validated through a two-round Delphi process, utilising an expert panel of healthcare professionals from across Europe and United States of America. Using web-based questionnaires, panellists recorded their level of agreement with each criterion based on a 5-point Likert Scale, with space for comments. Using median response, interquartile range and comments provided, criteria were accepted/rejected/revised depending on pre-agreed cut-off scores. The first round questionnaire presented thirty-three criteria to the panel, of which 22 were accepted. Consensus was not achieved for the remaining 11 criteria. Following response review, one criterion was removed, while after revision, the remaining 10 criteria entered the second round. Of these, four were subsequently accepted, resulting in 26 criteria considered appropriate for a POC test to detect urinary infections. This study generated an approved set of criteria for a POC test to detect urinary infections. Criteria acceptance and comments provided by the healthcare professionals also supports the development of a multiplex point of care UTI test.
The application of the multi-criteria analysis in evaluating of the road designs

Directory of Open Access Journals (Sweden)

Kuzović Ljubiša T.

2015-01-01

Full Text Available The analysis of the suitability of applying multi-criteria ranking of road design variants places the emphasis on the danger of fixing the ranking results, by the impact of subjective factors, in the process of determining relevant criteria and their relative weights. This danger is illustrated using two real examples. In the first example, subjective factors did not have a decisive influence since all of the most significant technical exploitation economic and ecological indicators, determined in the appropriate study and project documentation, were taken into account while determining relevant criteria and their relative weights. In the second example, subjective factors had a more decisive influence since all of the most significant technical exploitation economic and ecological indicators, determined in the appropriate study and project documentation, were not taken into account while determining relevant criteria and their relative weights.
9 CFR 310.25 - Contamination with microorganisms; process control verification criteria and testing; pathogen...

Science.gov (United States)

2010-01-01

... criteria and testing; pathogen reduction standards. (a) Criteria for verifying process control; E. coli... 1 (E.coli) Establishments that slaughter more than one type of livestock or both livestock and... E. coli that is approved as an AOAC Official Method of the AOAC International (formerly the...
Test design requirements: Thermal conductivity probe testing

International Nuclear Information System (INIS)

Heath, R.E.

1985-01-01

This document establishes the test design requirements for development of a thermal conductivity probe test. The thermal conductivity probe determines in situ thermal conductivity using a line source transient heat conduction analysis. This document presents the rationale for thermal conductivity measurement using a thermal conductivity probe. A general test description is included. Support requirements along with design constraints are detailed to allow simple design of the thermal conductivity probe and test. The schedule and delivery requirements of the responsible test designer are also included. 7 refs., 1 fig
Prestressed concrete reactor vessels: review of design and failure criteria

International Nuclear Information System (INIS)

Endebrock, E.G.

1975-03-01

The design and failure criteria of prestressed concrete reactor vessels (PCRVs) are reviewed along with the analysis methods. The mechanical properties of concrete under multiaxial stresses are not adequately quantified or described to permit an accurate analysis of a PCRV. Structural analysis of PCRVs almost universally utilizes a finite element which encounters difficulties in numerical solution of the governing equations and in treatment of fractured elements. (U.S.)
Design criteria of primary coolant chemistry in SMART-P

International Nuclear Information System (INIS)

Choi, Byung Seon; Kim, Ah Young; Kim, Seong Hoon; Yoon, Ju Hyeon; Zee, Sung Qunn

2005-01-01

SMART-P differs significantly from commercially designed PWRs. Materials inventories used in SMART-P differ from that at PWRs. All surfaces of the primary circuit with the primary coolant are either made from or plated with stainless steel. The material of steam generator (SG) is also different from that of the standard material of the commercially operating PWRs: titanium alloy for the steam generator tubes. Also, SMART-P primary coolant technology differs from that in PWRs: ammonia is used as a pH raising agent and hydrogen formed due to radiolytic processes is kept in specific range by ammonia dosing. Nevertheless, main objectives of the SMART-P primary coolant are the same as at PWRs: to assure primary system pressure boundary integrity, fuel cladding integrity and to minimize out-of-core radiation buildup. The objective of this work is to introduce the design criteria for the primary water chemistry for SMART-P from the viewpoint of the system characteristics and the chemical design concept
Kinetic and empirical design criteria for constructed wetlands

International Nuclear Information System (INIS)

Nix, P.G.; Gulley, J.R.

1995-01-01

A study was conducted to demonstrate the capabilities of wetlands as long-term, self-sustaining natural systems for the treatment of large quantities of waste water released from tailings ponds after mine abandonment. Constructed wetlands were built and planted with aquatic plants. The experimental design included three replicate trenches for each of two treatment systems. The objective of the research was to assess the optimum contaminant loading rates which would result in an acceptable quality of the effluent water. Using empirical data (i.e., hydrocarbon loading rates versus effluent quality), the optimal range of hydrocarbon loading was 5 to 25 gTEH/m 2/ month. Using more conservative kinetic data (i.e. microbial mineralization rates), the range of optimal treatment effectiveness was 9.6 to 13.2 gTEH/m 2/ month. The two design criteria methodologies were calculated using two independent analytical methods. The similarity in results was judged to be a confirmation of their accuracy. 20 refs., 5 figs
Waste Receiving and Processing Facility, Module 1: Volume 7, Project design criteria

International Nuclear Information System (INIS)

1992-03-01

This Project Design Criteria document for the WRAP facility at the Hanford Site is presented within a systems format. The WRAP Module 1 facility has been categorized into eight (8) engineering systems for design purposes. These systems include: receiving, shipping and storage, nondestructive assay/nondestructive examination (NDA/NDE), waste process, internal transportation, building, heating ventilation and air conditioning (HVAC), process control, and utilities. Within each system section of this document, the system-specific requirements are identified. The scope of the system is defined, the design goals are identified and the functional requirements are detailed
Design of Test Facility to Evaluate Boric Acid Precipitation Following a LOCA

Energy Technology Data Exchange (ETDEWEB)

Suh, Jeong-Kwan; Song, Yong-Jae [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

The U.S.NRC has identified a concern that debris associated with generic safety issue (GSI) - 191 may affect the potential precipitation of boric acid due to one or more of the following phenomena: - Reducing mass transport (i.e. mixing) between the core and the lower plenum (should debris accumulate at the core inlet) - Reduced lower plenum volume (should debris settle in the lower plenum), and, - Increased potential for boric acid precipitation (BAP) in the core (should debris accumulate in suspension in the core) To address these BAP issues, KHNP is planning to conduct validation tests by constructing a BAP test facility. This paper describes the design of test facility to evaluate BAP following a LOCA. The design of BAP test facility has been developed by KHNP. To design the test facility, test requirements and success criteria were established, and scaling analysis of power-to-volume method, Ishii-Kataoka method, and hierarchical two-tiered method were investigated. The test section is composed of two fuel assemblies with half of full of prototypic FA height. All the fuel rods are heated by the electric power supplier. The BAP tests in the presence of debris, buffering agents, and boron will be performed following the test matrix.

Packaging design criteria (onsite) project W-520 immobilized low-activity waste transportation system

International Nuclear Information System (INIS)

BOEHNKE, W.M.

2001-01-01

A plan is currently in place to process the high-level radioactive wastes that resulted from uranium and plutonium recovery operations from Spent Nuclear Fuel at the Hanford Site, Richland, Washington. Currently, millions of gallons of high-level radioactive waste in the form of liquids, sludges, and saltcake are stored in many large underground tanks onsite. This waste will be processed and separated into high-level and low-activity fractions. Both fractions will then be vitrified (i.e., blended with molten borosilicate glass) in order to encapsulate the toxic radionuclides. The immobilized low-activity waste (ILAW) glass will be poured into LAW canisters, allowed to cool and harden to solid form, sealed by welding, and then transported to a double-lined trench in the 200 East Area for permanent disposal. This document presents the packaging design criteria (PDC) for an onsite LAW transportation system, which includes the ILAW canister, ILAW package, and transport vehicle and defines normal and accident conditions. This PDC provides the basis for the ILAW onsite transportation system design and fabrication and establishes the transportation safety criteria that the design will be evaluated against in the Package Specific Safety Document (PSSD). It provides the criteria for the ILAW canister, cask and transport vehicles and defines normal and accident conditions. The LAW transportation system is designed to transport stabilized waste from the vitrification facility to the ILAW disposal facility developed by Project W-520. All ILAW transport will take place within the 200 East Area (all within the Hanford Site)
Healthcare Building Sustainability Assessment tool - Sustainable Effective Design criteria in the Portuguese context

International Nuclear Information System (INIS)

Castro, Maria de Fátima; Mateus, Ricardo; Bragança, Luís

2017-01-01

Tools and methods to improve current practices and quality in the healthcare building sector are necessary to support decision-making at different building life cycle phases. Furthermore, Healthcare Building Sustainability Assessment (HBSA) Methods are based on criteria organised into different levels, such as categories and indicators. These criteria highlight aspects of significant importance when designing and operating a sustainable healthcare building. To bring more objectivity to the sustainability assessments, the standardisation bodies (CEN and ISO) proposed core indicators that should be used in the evaluation of the environmental, societal and economic performances of buildings. Nevertheless, relying on state of the art analysis, it is possible to conclude that there are aspects of major importance for the operation of healthcare buildings that are not considered in the HBSA methods. Thus, the aim of this paper is to discuss the context of sustainability assessment methods in the field of healthcare buildings and to present a proposal for the incorporation of Sustainable-Effective Design (SED) criteria in a new HBSA method. The used research method is innovative since in the development of the list of sustainability criteria it considers the opinion of main healthcare buildings' stakeholders, the existing healthcare assessment methods and the ISO and CEN standardisation works in the field of the methods to assess the sustainability of construction works. As a result, the proposed method is composed of fifty-two sustainability indicators that cover the different dimensions of the sustainability concept to support decision making during the design of a new or retrofitted healthcare building in urban areas. - Highlights: •A new system to assess the sustainability of healthcare buildings is presented. •We propose a method to develop the list of sustainability indicators for hospitals. •We propose a new concept – Sustainable-Effective Design (SED
Criteria for seismic evaluation and potential design fixes for WWER type nuclear power plants

International Nuclear Information System (INIS)

Stevenson, J.D.

1995-01-01

The purpose for this document is to provide a criteria for the seismic evaluation and development of potential design fixes for structures, systems and components for the WWER type Nuclear power plants. The design fixes are divided into two categories, detailed and easy fixes. Detailed fixes are typically applicable to building structures, components for which there is little or no seismic capacity information, large tanks and vital systems and components which make up the reactor cooling system and components which perform support or auxiliary functions. In case of the design of 'easy fixes', the criteria presented may be used for both the seismic design as well as for the evaluation of structures, systems and components to which easy fix design applies. Easy fixes are situations where seismic capacities of structures, systems and components can be significantly increased with relatively minor, inexpensive fixes usually associated with anchorage modification of safety related structures, systems and components or those that could interact with safety related structures, systems and components. Often these fixes can be accomplished while the plant is in operation
Criteria for seismic evaluation and potential design fixes for WWER type nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Stevenson, J D [Stevenson and Associates, Cleveland, OH (United States)

1995-07-01

The purpose for this document is to provide a criteria for the seismic evaluation and development of potential design fixes for structures, systems and components for the WWER type Nuclear power plants. The design fixes are divided into two categories, detailed and easy fixes. Detailed fixes are typically applicable to building structures, componentsfor which there is little or no seismic capacity information, large tanks and vital systems and components which make up the reactor cooling system and components which perform support or auxiliary functions. In case of the design of 'easy fixes', the criteria presented may be used for both the seismic design as well as for the evaluation of structures, systems and components to which easy fix design applies. Easy fixes are situations where seismic capacities of structures, systems and components can be significantly increased with relatively minor, inexpensive fixes usually associated with anchorage modification of safety related structures, systems and components or those that could interact with safety related structures, systems and components. Often these fixes can be accomplished while the plant is in operation.
Design requirements, criteria and methods for seismic qualification of CANDU power plants

International Nuclear Information System (INIS)

Singh, N.; Duff, C.G.

1979-10-01

This report describes the requirements and criteria for the seismic design and qualification of systems and equipment in CANDU nuclear power plants. Acceptable methods and techniques for seismic qualification of CANDU nuclear power plants to mitigate the effects or the consequences of earthquakes are also described. (auth)
LMFBR safety criteria and guidelines for consideration in the design of future plants

International Nuclear Information System (INIS)

1990-01-01

For many years the Commission of the European Communities has been conducting activities aimed at the progressive harmonization of safety requirements and criteria applied to nuclear installations in the Community. These activities cover thermal and fast reactors. This publication represents a major achievement in reaching this goal. The document, which has been prepared in the framework of activities of the CEC fast-reactor safety working group (SWG), consists of safety criteria and guidelines for fast reactors. It represents the common view of all EC Member States which have a fast-reactor programme or are interested in fast-reactor development. The criteria and guidelines are structured according to different types of possible faults, such as core reactivity faults, general cooling faults, subassembly faults, faults outside the core and causes external to the station. Only those events are considered which are in the design basis of current fast-reactor projects. Proposed measures or guidelines to satisfy the criteria are based on the present knowledge and proven technology
A MULTI CRITERIA APPROACH TO DESIGNING THE CELLULAR MANUFACTURING SYSTEM

Directory of Open Access Journals (Sweden)

Rika Ampuh Hadiguna

2005-01-01

Full Text Available Cellular manufacturing system design problems such as design framework, manufacturing cells layout and layout evaluation. The research objective is developing the framework to designing manufacturing cells with considering the organization and management aspects in shopfloor. In this research have compared the existing layout with proposed layout which applied the multi criteria approach. The proposed method is combining Analytical Hierarchy Process (AHP, Clustering and heuristic approach. The result has show that grouping with Single Linkage Clustering (SLC to be selected as manufacturing cells. The comparison of clustering weight is 0,567, 0,245 and 0,188 for SLC, Complete Linkage Clustering (CLC and Average Linkage Clustering (ALC, respectively. This result shows that generating layout by using grouping result from SLC. The evaluation result shows that types of manufacturing cells better than process layout which used the existing system.
Preliminary selection criteria for the Yucca Mountain Project waste package container material

International Nuclear Information System (INIS)

Halsey, W.G.

1991-01-01

The Department of Energy's Yucca Mountain Project (YMP) is evaluating a site at Yucca Mountain in Nevada for construction of a geologic repository for the storage of high-level nuclear waste. Lawrence Livermore National Laboratory's (LLNL) Nuclear Waste Management Project (NWMP) has the responsibility for design, testing, and performance analysis of the waste packages. The design is performed in an iterative manner in three sequential phases (conceptual design, advanced conceptual design, and license application design). An important input to the start of the advanced conceptual design is the selection of the material for the waste containers. The container material is referred to as the 'metal barrier' portion of the waste package, and is the responsibility of the Metal Barrier Selection and Testing task at LLNL. The selection will consist of several steps. First, preliminary, material-independent selection criteria will be established based on the performance goals for the container. Second, a variety of engineering materials will be evaluated against these criteria in a screening process to identify candidate materials. Third, information will be obtained on the performance of the candidate materials, and final selection criteria and quantitative weighting factors will be established based on the waste package design requirements. Finally, the candidate materials will be ranked against these criteria to determine whether they meet the mandated performance requirements, and to provide a comparative score to choose the material for advanced conceptual design activities. This document sets forth the preliminary container material selection criteria to be used in screening candidate materials. 5 refs
Reliability based code calibration of fatigue design criteria of nuclear Class-1 piping

International Nuclear Information System (INIS)

Mishra, J.; Balasubramaniyan, V.; Chellapandi, P.

2016-01-01

Fatigue design of Class-l piping of NPP is carried out using Section-III of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel code. The fatigue design criteria of ASME are based on the concept of safety factor, which does not provide means for the management of uncertainties for consistently reliable and economical designs. In this regards, a work is taken up to estimate the implicit reliability level associated with fatigue design criteria of Class-l piping specified by ASME Section III, NB-3650. As ASME fatigue curve is not in the form of analytical expression, the reliability level of pipeline fittings and joints is evaluated using the mean fatigue curve developed by Argonne National Laboratory (ANL). The methodology employed for reliability evaluation is FORM, HORSM and MCS. The limit state function for fatigue damage is found to be sensitive to eight parameters, which are systematically modelled as stochastic variables during reliability estimation. In conclusion a number of important aspects related to reliability of various piping product and joints are discussed. A computational example illustrates the developed procedure for a typical pipeline. (author)
Rethinking exergy efficiency in favor of exergy sustainability as a criteria for design. Paper no. IGEC-1-ID12

International Nuclear Information System (INIS)

Seager, T.P.

2005-01-01

'Full text:' Engineering design in power generation or conversion has typically focused on minimizing exergy losses (entropy gains), or maximizing economic returns. Both entropy minimization and profit maximization are readily obtainable and acceptable objective criteria for design of thermodynamic processes. However, alternative criteria are imaginable. This research presents a framework for considering minimal environmental impact or maximum renewability as alternative design criteria. In the environmental case, fuel source is based upon an exergetic environmental metric called pollution potential. In the case of renewability, a life-cycle metric describing the replacement time frame of the fuel source is employed. When coupled, the two metrics together partially assess the overall sustainability of the design. (author)
Criteria for the PNE seismic network

International Nuclear Information System (INIS)

Pruvost, N.L.

1978-01-01

A 1976 treaty between the United States and the Soviet Union permits a local seismic network to be deployed at the site of a peaceful nuclear explosion to monitor the event. Criteria for the design and selection of the data-acquisition equipment for such a network are provided. Constraints imposed by the protocol of the treaty, the environment, and the expected properties of seismic signals (based on experiences at the Nevada Test Site) are discussed. Conclusions are drawn about the desired operating mode. Criteria for a general seismic instrumentation system are described
Snell Envelope with Small Probability Criteria

Energy Technology Data Exchange (ETDEWEB)

Del Moral, Pierre, E-mail: Pierre.Del-Moral@inria.fr; Hu, Peng, E-mail: Peng.Hu@inria.fr [Universite de Bordeaux I, Centre INRIA Bordeaux et Sud-Ouest and Institut de Mathematiques de Bordeaux (France); Oudjane, Nadia, E-mail: Nadia.Oudjane@edf.fr [EDF R and D Clamart (France)

2012-12-15

We present a new algorithm to compute the Snell envelope in the specific case where the criteria to optimize is associated with a small probability or a rare event. This new approach combines the Stochastic Mesh approach of Broadie and Glasserman with a particle approximation scheme based on a specific change of measure designed to concentrate the computational effort in regions pointed out by the criteria. The theoretical analysis of this new algorithm provides non asymptotic convergence estimates. Finally, the numerical tests confirm the practical interest of this approach.
The Non-absoluteness of the Leading Position of the Frequency ——On the Vocabulary Design Criteria of Teaching Chinese to Speakers of Other Language

Directory of Open Access Journals (Sweden)

Ma Qinghua

2017-10-01

Full Text Available The design criteria of the vocabulary outline of the second language teaching vary according to the teaching objectives. Under the same objective, the criteria are often more than one. The multiple criteria are sometimes compatible and sometimes conflicting. Through analyzing and evaluating the advantages and disadvantages of the new Chinese Proficiency Test (HSK Vocabulary Outline, this paper reveals the interactions between the task objectives, the criterion conditions and processing strategies, as well as the interaction relationships between the multiple criteria features of the vocabulary outline designing process, and then abstracts the general principles and overall rules. The research results subvert the habitual knowledge that the frequency criterion position ranked first, which is always popular at least in the Chinese academic circle. It finds that the leading position of frequency criterion only exists in the criteria compatibility model. In the conflict model of the locutionary criteria, the stylistic criterion and syntactic criterion are strong criteria, while the word frequency criterion relegates to the weak position. In the conflict model of the locutionary and illocutionary criteria, the illocutionary criterion is strong criterion, while the locutionary criterion relegates to the weak position, which indicates that the language can’t be above its purpose of usage. This research is conducive to the improvement of the vocabulary outline. It also has certain practical significance to the disciplinary theories of Teaching Chinese to Speakers of Other Language or even to the whole second language teaching.
22 CFR 96.6 - Performance criteria for designation as an accrediting entity.

Science.gov (United States)

2010-04-01

... other similar functions; (f) Except in the case of a public entity, that it operates independently of... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Performance criteria for designation as an accrediting entity. 96.6 Section 96.6 Foreign Relations DEPARTMENT OF STATE LEGAL AND RELATED SERVICES...
An intelligent, knowledge-based multiple criteria decision making advisor for systems design

Science.gov (United States)

Li, Yongchang

In systems engineering, design and operation of systems are two main problems which always attract researcher's attentions. The accomplishment of activities in these problems often requires proper decisions to be made so that the desired goal can be achieved, thus, decision making needs to be carefully fulfilled in the design and operation of systems. Design is a decision making process which permeates through out the design process, and is at the core of all design activities. In modern aircraft design, more and more attention is paid to the conceptual and preliminary design phases so as to increase the odds of choosing a design that will ultimately be successful at the completion of the design process, therefore, decisions made during these early design stages play a critical role in determining the success of a design. Since aerospace systems are complex systems with interacting disciplines and technologies, the Decision Makers (DMs) dealing with such design problems are involved in balancing the multiple, potentially conflicting attributes/criteria, transforming a large amount of customer supplied guidelines into a solidly defined set of requirement definitions. Thus, one could state with confidence that modern aerospace system design is a Multiple Criteria Decision Making (MCDM) process. A variety of existing decision making methods are available to deal with this type of decision problems. The selection of the most appropriate decision making method is of particular importance since inappropriate decision methods are likely causes of misleading engineering design decisions. With no sufficient knowledge about each of the methods, it is usually difficult for the DMs to find an appropriate analytical model capable of solving their problems. In addition, with the complexity of the decision problem and the demand for more capable methods increasing, new decision making methods are emerging with time. These various methods exacerbate the difficulty of the selection
Clinical relevance of the proposed sexual addiction diagnostic criteria: relation to the Sexual Addiction Screening Test-Revised.

Science.gov (United States)

Carnes, Patrick J; Hopkins, Tiffany A; Green, Bradley A

2014-01-01

The present article examines and compares the various diagnostic rubrics proposed to codify symptoms of sexual addiction, and then briefly summarizes the ongoing controversy on whether sexual addiction is a valid construct. Using the diagnostic criteria proposed by , the prevalence rate of each criterion is examined in terms of scores on the Sexual Addiction Screening Test-Revised scales (). Differences in diagnostic criteria endorsement associated with sex, sexual orientation, and setting were also explored. Results from a clinical sample of men and women seeking treatment for sexual addiction demonstrated clinical relevance of the criteria, in that all but 3 criteria are endorsed at more than 50% of participants screening positive for sexual addiction on the Sexual Addiction Screening Test-Revised. Sex differences were also noted for endorsement rates of several of the criteria. Finally, several proposed criteria may pose a higher clinical threshold and thus be utilized by clinicians to identify patients with increased pathology. Results are discussed in the context of existing diagnostic frameworks across etiological perspectives.
Design and testing of shape memory alloy actuation mechanism for flapping wing micro unmanned aerial vehicles

Science.gov (United States)

Kamaruzaman, N. F.; Abdullah, E. J.

2017-12-01

Shape memory alloy (SMA) actuator offers great solution for aerospace applications with low weight being its most attractive feature. A SMA actuation mechanism for the flapping micro unmanned aerial vehicle (MAV) is proposed in this study, where SMA material is the primary system that provides the flapping motion to the wings. Based on several established design criteria, a design prototype has been fabricated to validate the design. As a proof of concept, an experiment is performed using an electrical circuit to power the SMA actuator to evaluate the flapping angle. During testing, several problems have been observed and their solutions for future development are proposed. Based on the experiment, the average recorded flapping wing angle is 14.33° for upward deflection and 12.12° for downward deflection. This meets the required design criteria and objective set forth for this design. The results prove the feasibility of employing SMA actuators in flapping wing MAV.
Evaluation of a School Building in Turkey According to the Basic Sustainable Design Criteria

Science.gov (United States)

Arslan, H. D.

2017-08-01

In Turkey, as well as many other developing countries, the significance of sustainable education buildings has only recently become recognized and the issue of sustainability issue has not been sufficiently involved in laws and regulations. In this study, first of all architectural sustainability with basic design criteria has been explained. After that selected type primary school project in Turkey has been evaluated according to the sustainable design criteria. Type project of school buildings significantly limits the sustainability performance expected from buildings. It is clear that type projects shorten the planning time as they include a designing process that is independent of settlement and they are repeated in various places with different characteristics, indeed. On the other hand; abundance of disadvantages such as the overlook of the natural physical and structural properties of the location mostly restricts the sustainable design of the building. For sustainable buildings, several factors such as the environment, land, climate, insolation, direction etc. shall be taken into consideration at the beginning stage. Therefore; implementation of type projects can be deemed to be inappropriate for sustainability.
Identification of Anisotropic Criteria for Stratified Soil Based on Triaxial Tests Results

Science.gov (United States)

Tankiewicz, Matylda; Kawa, Marek

2017-09-01

The paper presents the identification methodology of anisotropic criteria based on triaxial test results. The considered material is varved clay - a sedimentary soil occurring in central Poland which is characterized by the so-called "layered microstructure". The strength examination outcomes were identified by standard triaxial tests. The results include the estimated peak strength obtained for a wide range of orientations and confining pressures. Two models were chosen as potentially adequate for the description of the tested material, namely Pariseau and its conjunction with the Jaeger weakness plane. Material constants were obtained by fitting the model to the experimental results. The identification procedure is based on the least squares method. The optimal values of parameters are searched for between specified bounds by sequentially decreasing the distance between points and reducing the length of the searched range. For both considered models the optimal parameters have been obtained. The comparison of theoretical and experimental results as well as the assessment of the suitability of selected criteria for the specified range of confining pressures are presented.
Canister storage building compliance assessment DOE Order 6430.1A, General Design Criteria

International Nuclear Information System (INIS)

BLACK, D.M.

1999-01-01

This document presents the Project's position on compliance with DOE Order 6430.1A ''General Design Criteria.'' No non-compliances are shown. The compliance statements have been reviewed and approved by DOE. Open items are scheduled to be closed prior to project completion

Solving the Problem of Multiple-Criteria Building Design Decisions with respect to the Fire Safety of Occupants: An Approach Based on Probabilistic Modelling

Directory of Open Access Journals (Sweden)

Egidijus Rytas Vaidogas

2015-01-01

Full Text Available The design of buildings may include a comparison of alternative architectural and structural solutions. They can be developed at different levels of design process. The alternative design solutions are compared and ranked by applying methods of multiple-criteria decision-making (MCDM. Each design is characterised by a number of criteria used in a MCDM problem. The paper discusses how to choose MCDM criteria expressing fire safety related to alternative designs. Probability of a successful evacuation of occupants from a building fire and difference between evacuation time and time to untenable conditions are suggested as the most important criteria related to fire safety. These two criteria are treated as uncertain quantities expressed by probability distributions. Monte Carlo simulation of fire and evacuation processes is natural means for an estimation of these distributions. The presence of uncertain criteria requires applying stochastic MCDM methods for ranking alternative designs. An application of the safety-related criteria is illustrated by an example which analyses three alternative architectural floor plans prepared for a reconstruction of a medical building. A MCDM method based on stochastic simulation is used to solve the example problem.
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
Probabilistic risk criteria and their application to nuclear chemical plant design

International Nuclear Information System (INIS)

Arthur, T.; Barnes, D.S.; Brown, M.L.; Taig, A.R.; Johnston, B.D.; Hayns, M.

1989-01-01

A nuclear chemical plant safety strategy is presented. The use of risk criteria in design is demonstrated by reference to a particular area of the plant. This involves the application of Probabilistic Risk Assessment (PRA) techniques. Computer programs developed by the UK Atomic Energy Authority (UKAEA) at its Safety and Reliability Directorate (SRD) are used toe valuate and analyze the resultant fault trees. the magnitude of releases are estimated and individual and societal risks determined. The paper concludes that the application of PRA to a nuclear chemical plant can be structured in such a way as to allow a designer to work to quantitative risk targets
Technical regulations on the general design and safety criteria for design and construction of nuclear reactors of May 1975

International Nuclear Information System (INIS)

1975-05-01

These Technical Regulations published on 5th September 1975 were made in implementation of Section 33 of Decree No 7/9141 on the procedure for the licensing of nuclear installations. They serve as a guide to licensing authorities, project designers and operators in the nuclear field and therefore provide general criteria for safety standards, engineering codes, siting considerations, design bases for overall environmental radiation protection, and also deal with reactor core design, instrumentation, control, alarm systems, including an emergency core cooling system. Finally, the safe design of fuel elements must be ensured and fuel storage and handling techniques complied with. (NEA) [fr
Criteria for the design of the control room complex for a nuclear power generating station

International Nuclear Information System (INIS)

Anon.

1981-01-01

This Standard addresses the central control room of a nuclear power generating station and the overall complex in which this room is housed. It is not intended to cover special or normally unattended control rooms, such as those provided for radioactive waste handling or for emergency shutdown operations. The nuclear power generating station control room complex provides a protective envelope for plant operating personnel and for instrument and control equipment vital to the operation of the plant during normal and abnormal conditions. In this capacity, the control room complex must be designed and constructed to meet the following criteria contained in Appendix A of 10CFR50, General Design criteria for Nuclear Power Plants: (1) Criterion 2: design bases for protection against natural phenomena; (2) Criterion 3: fire protection; (3) Criterion 4: environmental and missile design bases; (4) Criterion 5: sharing of structures, systems and components (multiunit stations only); and (5) Criterion 19: control room
Functional design criteria for the retained gas sampler system

International Nuclear Information System (INIS)

Wootan, D.W.

1995-01-01

A Retained Gas Sampler System (RGSS) is being developed to capture and analyze waste samples from Hanford Flammable Gas Watch List Tanks to determine both the quantity and composition of gases retained in the waste. The RGSS consists of three main components: the Sampler, Extractor, and Extruder. This report describes the functional criteria for the design of the RGSS components. The RGSS Sampler is based on the WHC Universal Sampler design with modifications to eliminate gas leakage. The primary function of the Sampler is to capture a representative waste sample from a tank and transport the sample with minimal loss of gas content from the tank to the laboratory. The function of the Extruder is to transfer the waste sample from the Sampler to the Extractor. The function of the Extractor is to separate the gases from the liquids and solids, measure the relative volume of gas to determine the void fraction, and remove and analyze the gas constituents
Field-testing of the ICHD-3 beta diagnostic criteria for classical trigeminal neuralgia

DEFF Research Database (Denmark)

Maarbjerg, Stine; Sørensen, Morten Togo; Gozalov, Aydin

2015-01-01

INTRODUCTION: We aimed to field-test the beta version of the third edition of the International Classification of Headache Disorders (ICHD-3 beta) diagnostic criteria for classical trigeminal neuralgia (TN). The proposed beta draft of the 11th version of the International Classification of Diseases...... (ICD-11 beta) is almost exclusively based on the ICHD-3 beta classification structure although slightly abbreviated. We compared sensitivity and specificity to ICHD-2 criteria, and evaluated the needs for revision. METHODS: Clinical characteristics were systematically and prospectively collected from...
Materials for Hydrogen Storage in Nanocavities: Design criteria

Energy Technology Data Exchange (ETDEWEB)

Reguera, E. [Centro de Investigacion en Ciencia Aplicada y Tecnologia Avanzada del IPN, Unidad Legaria, Legaria 694, Col. Irrigacion (Mexico)

2009-11-15

The adsorption potential for a given adsorbate depends of both, material surface and adsorbate properties. In this contribution the possible guest-host interactions for H{sub 2} within a cavity or on a surface are discussed considering the molecule physical properties. Five different interactions contribute to the adsorption forces for this molecule: 1) quadrupole moment interaction with the local electric field gradient; 1) electron cloud polarization by a charge center; 3) dispersive forces (van der Waals); 4) quadrupole moment versus quadrupole moment between neighboring H{sub 2} molecules, and, 5) H{sub 2} coordination to a metal center. The relative importance of these five interactions for the hydrogen storage in nanocavities is discussed from experimental evidences in order to extract materials design criteria for molecular hydrogen storage. (author)
An approach to criteria, design limits and monitoring in nuclear fuel waste disposal

Energy Technology Data Exchange (ETDEWEB)

Simmons, G R; Baumgartner, P; Bird, G A; Davison, C C; Johnson, L H; Tamm, J A

1994-12-01

The Nuclear Fuel Waste Management Program has been established to develop and demonstrate the technology for safe geological disposal of nuclear fuel waste. One objective of the program is to show that a disposal system (i.e., a disposal centre and associated transportation system) can be designed and that it would be safe. Therefore the disposal system must be shown to comply with safety requirements specified in guidelines, standards, codes and regulations. The components of the disposal system must also be shown to operate within the limits specified in their design. Compliance and performance of the disposal system would be assessed on a site-specific basis by comparing estimates of the anticipated performance of the system and its components with compliance or performance criteria. A monitoring program would be developed to consider the effects of the disposal system on the environment and would include three types of monitoring: baseline monitoring, compliance monitoring, and performance monitoring. This report presents an approach to establishing compliance and performance criteria, limits for use in disposal system component design, and the main elements of a monitoring program for a nuclear fuel waste disposal system. (author). 70 refs., 9 tabs., 13 figs.
An approach to criteria, design limits and monitoring in nuclear fuel waste disposal

International Nuclear Information System (INIS)

Simmons, G.R.; Baumgartner, P.; Bird, G.A.; Davison, C.C.; Johnson, L.H.; Tamm, J.A.

1994-12-01

The Nuclear Fuel Waste Management Program has been established to develop and demonstrate the technology for safe geological disposal of nuclear fuel waste. One objective of the program is to show that a disposal system (i.e., a disposal centre and associated transportation system) can be designed and that it would be safe. Therefore the disposal system must be shown to comply with safety requirements specified in guidelines, standards, codes and regulations. The components of the disposal system must also be shown to operate within the limits specified in their design. Compliance and performance of the disposal system would be assessed on a site-specific basis by comparing estimates of the anticipated performance of the system and its components with compliance or performance criteria. A monitoring program would be developed to consider the effects of the disposal system on the environment and would include three types of monitoring: baseline monitoring, compliance monitoring, and performance monitoring. This report presents an approach to establishing compliance and performance criteria, limits for use in disposal system component design, and the main elements of a monitoring program for a nuclear fuel waste disposal system. (author). 70 refs., 9 tabs., 13 figs
17 CFR Appendix A to Part 38 - Guidance on Compliance With Designation Criteria

Science.gov (United States)

2010-04-01

... the criteria for designation. To the extent that compliance with, or satisfaction of, a criterion for... based on order priority factors other than price and time should include a brief explanation of the... financial integrity of transactions and intermediaries, and the protection of customer funds should include...
Nevada test site low-level and mixed waste repository design in the unsaturated zone

International Nuclear Information System (INIS)

Kawamura, T.A.; Warren, D.M.

1989-01-01

The Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) is used for shallow land disposal of Low-Level Radioactive (LLW) and for retrievable disposal of Mixed Wastes (MW) from various Department of Energy (DOE) facilities. The site is situated in southern Nevada, one of the most arid regions of the United States. Design considerations include vadose zone monitoring in lieu of groundwater monitoring, stringent waste acceptance and packaging criteria, a waste examination and real-time radiography facility, and trench design. 4 refs
Test-retest reliability of the proposed DSM-5 eating disorder diagnostic criteria

Science.gov (United States)

Sysko, Robyn; Roberto, Christina A.; Barnes, Rachel D.; Grilo, Carlos M.; Attia, Evelyn; Walsh, B. Timothy

2012-01-01

The proposed DSM-5 classification scheme for eating disorders includes both major and minor changes to the existing DSM-IV diagnostic criteria. It is not known what effect these modifications will have on the ability to make reliable diagnoses. Two studies were conducted to evaluate the short-term test-retest reliability of the proposed DSM-5 eating disorder diagnoses: anorexia nervosa, bulimia nervosa, binge eating disorder, and feeding and eating conditions not elsewhere classified. Participants completed two independent telephone interviews with research assessors (n=70 Study 1; n=55 Study 2). Fair to substantial agreements (κ= 0.80 and 0.54) were observed across eating disorder diagnoses in Study 1 and Study 2, respectively. Acceptable rates of agreement were identified for the individual eating disorder diagnoses, including DSM-5 anorexia nervosa (κ’s of 0.81 to 0.97), bulimia nervosa (κ=0.84), binge eating disorder (κ’s of 0.75 and 0.61), and feeding and eating disorders not elsewhere classified (κ’s of 0.70 and 0.46). Further, improved short-term test-retest reliability was noted when using the DSM-5, in comparison to DSM-IV, criteria for binge eating disorder. Thus, these studies found that trained interviewers can reliably diagnose eating disorders using the proposed DSM-5 criteria; however, additional data from general practice settings and community samples are needed. PMID:22401974
Toward User Interfaces and Data Visualization Criteria for Learning Design of Digital Textbooks

Science.gov (United States)

Railean, Elena

2014-01-01

User interface and data visualisation criteria are central issues in digital textbooks design. However, when applying mathematical modelling of learning process to the analysis of the possible solutions, it could be observed that results differ. Mathematical learning views cognition in on the base on statistics and probability theory, graph…
Criteria for validation and selection of cognitive tests for investigating the effects of foods and nutrients.

Science.gov (United States)

de Jager, Celeste A; Dye, Louise; de Bruin, Eveline A; Butler, Laurie; Fletcher, John; Lamport, Daniel J; Latulippe, Marie E; Spencer, Jeremy P E; Wesnes, Keith

2014-03-01

This review is an output of the International Life Sciences Institute (ILSI) Europe Marker Initiative, which aims to identify evidence-based criteria for selecting adequate measures of nutrient effects on health through comprehensive literature review. Experts in cognitive and nutrition sciences examined the applicability of these proposed criteria to the field of cognition with respect to the various cognitive domains usually assessed to reflect brain or neurological function. This review covers cognitive domains important in the assessment of neuronal integrity and function, commonly used tests and their state of validation, and the application of the measures to studies of nutrition and nutritional intervention trials. The aim is to identify domain-specific cognitive tests that are sensitive to nutrient interventions and from which guidance can be provided to aid the application of selection criteria for choosing the most suitable tests for proposed nutritional intervention studies using cognitive outcomes. The material in this review serves as a background and guidance document for nutritionists, neuropsychologists, psychiatrists, and neurologists interested in assessing mental health in terms of cognitive test performance and for scientists intending to test the effects of food or food components on cognitive function.
A Particle Swarm Optimization Approach to Composing Serial Test Sheets for Multiple Assessment Criteria

Science.gov (United States)

Yin, Peng-Yeng; Chang, Kuang-Cheng; Hwang, Gwo-Jen; Hwang, Gwo-Haur; Chan, Ying

2006-01-01

To accurately analyze the problems of students in learning, the composed test sheets must meet multiple assessment criteria, such as the ratio of relevant concepts to be evaluated, the average discrimination degree, difficulty degree and estimated testing time. Furthermore, to precisely evaluate the improvement of student's learning performance…
Advancements in flow-induced vibration research and design criteria

International Nuclear Information System (INIS)

Pettigrew, M.J.

2009-01-01

Two-phase flow exists in many nuclear components and, in particular, steam generators. So far relatively little research work has been done on two-phase flow-induced vibration probably because it is difficult to do. Two-phase flows are not homogeneous and are governed by an additional parameter called void fraction. This can lead to different flow patterns or regimes that can change completely the vibration behaviour. Fluidelastic instability, random turbulence excitation and detailed flow characteristics are being investigated in tube bundles subjected to two-phase cross flow. Fluidelastic instability of a tube bundle preferentially flexible in the flow direction was observed probably for the first time. This is particularly relevant to the problem of in-plane vibration of nuclear steam generator U-tubes and has resulted in changes in our design criteria. Unexpected quasi-periodic excitation forces were also measured in the tube bundle. These are attributed to an alternating wake in the lift direction and to fluctuating momentum flux in the drag direction. Vibration damping due to two-phase flow is very dependent on void fraction and appears directly related to the interface surface area between phases. Maximum damping values correspond to the transitions between flow regimes. Fibre optic probes were developed to measure the characteristics of two-phase flows. These probes are used to take detailed measurements in a triangular array of tubes in cross flow. The results show that the flow tends to stream between the tubes. These studies have yielded interesting results but have raised more questions that could lead to improved design criteria. The more puzzling results will be discussed in this presentation. Some of the dynamic phenomena will be illustrated by animation. (author)
Design report for an annular fuel element for accommodation of a carbide test bundle on the ring position of the KNK II/2 test zone

International Nuclear Information System (INIS)

Haefner, H.E.

1982-03-01

This report describes an annular oxide element with Mark II rods for accommodation of a 19-pin carbide test bundle on position 201 in the test zone of the second core of KNK II as well as its behavior during the period of operation. The ring element comprises within a driver wrapper in three rows of pins 102 fuel pins of 7.6 mm diameter and six structural rods for fixing the spark eroded spacers. The report deals with the ring element with its individual components fuel rod, bundle, wrappers, head and foot and describes methods, criteria and results concerning the design. The carbide test bundle to be accommodated by the annular carrier element will be treated in a separate report. The loadability of the annular element with its components is demonstrated by generally valid standards for strength criteria
Operating experience and design criteria of sodium valves

International Nuclear Information System (INIS)

Markford, D.

1974-01-01

The information presented refers to sodium valve development for KNK and SNR-300 as well as for sodium test facilities on the INTERATOM site at Bensberg. Well in advance of KNK-I a number of sodium test facilities have been operated containing small and medium size valves of different design and manufacturer. The more stringent requirements for long range safe and reliable operation in KNK-I put forth a development program for the main primary and secondary circuit sodium valves. Operational experience gave rise to modification of the stem seal arrangement mainly, so KNK-II (which is the fast core for KNK reactor) will be run with modified sodium valves. Main pipe diameters in SNR-300 are in the range of 600 mm. Valve designs with rising shafts would require excessive space in the primary circuit cavities, therefore efforts have been directed towards introduction of different type valves. Due to the requirements of after-heat-removal a valve type with control capability had to be chosen. A special design of butterfly valves was selected for the primary and secondary circuits of SNR-300. The development and tests performed with this type of valve are described. In the field of small sodium valves, tests with a 50 mm diameter freeze-seal valve are reported, and the current status of bellows-seal-valves to be inserted into SNR-300 is discussed. (U.S.)
The development of criteria for the design of insulation for nuclear reactors

International Nuclear Information System (INIS)

Furber, B.N.; Hopkins, I.H.G.; Stuart, R.A.

1976-01-01

In 1960 when the early design studies for the Oldbury Power Station were being carried out the use of insulation in a reactor environment was quite novel. No manufacturer had previous experience of this particular application of insulation. The paper describes the work carried out to establish the design criteria for Magnox and subsequent Advanced Gas Cooled Reactors (AGR) and indicates some of the new problems of the High Temperature Reactor (HTR). Unless otherwise stated the work was carried out by The Nuclear Power Group Ltd. (TNPG) and the conclusions express the present thinking of that Company. (author)

Small Business Conformity with Quality Website Design Criteria in a Marketing Communication Context

Directory of Open Access Journals (Sweden)

Martine Robinson Beachboard

2017-10-01

Full Text Available Aim/Purpose: Professional companies selling persuasive-communication services via the World Wide Web need to be exemplars of effective informing practices. Their credibility is at risk if their websites do not excel in marketing message and use of medium. Their unique brands need to be expressed through website technology and content, or they cannot compete successfully. Background: Compares marketing communication consultants’ websites with expert criteria. Methodology: Content analysis of 40 advertising agency websites. Contribution: Links an evaluation of advertising agency compliance with expert website criteria to established branding constructs. Findings: Most small advertising agencies could improve their brand reputations through better compliance with experts’ recommended website design and content criteria. Recommendations for Practitioners: A hierarchy of recommendations for practitioners is offered, addressing ease and importance. Impact on Society: Clarity and credibility of message and medium improve our ability to practice effective informing. Future Research: Explore online communications of specialized populations such as digital marketing experts.
Design and Management Criteria for Fish, Amphibian, and Reptile Communities Within Created Agricultural Wetlands

Science.gov (United States)

Design and management criteria for created agricultural wetlands in the midwestern United States typically focus on maximizing the ability to process agricultural runoff. Ecological benefits for fish, amphibian, and reptiles are often secondary considerations. One example of this water quality focu...
Panel 1: Safety design criteria

International Nuclear Information System (INIS)

Yllera, Javier

2013-01-01

There is general consensus in the nuclear community, and more after the Fukushima accident, that the deployment of nuclear energy has to be done at the highest levels of nuclear safety and that safety cannot be compromised by other factors. It is well understood that reactors that are being licensed and the new generations of reactors that will be constructed in the future will need to reach higher safety levels than the existing ones. Several countries and international organizations or international groups are launching initiatives to harmonise safety goals, safety requirements, safety objectives, regulations, criteria or safety reference levels. There are differences in the meanings of these terms and the working approaches, but the overall purpose is the same: to specify how new plants can be safer. In this context, the IAEA has an statutory function for developing international nuclear safety standards. The IAEA safety standards are per se not mandatory for IAEA Member States. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA’s standards for use in their national regulations in different ways. The IAEA Safety Standards represent international consensus on what must constitute a high level of safety for nuclear installations. In the area of NPP design, IAEA safety standards that are published are intended to apply primarily to new plants. It might not be practicable to apply all the requirements to plants that are already in operation. In addition, the focus is primarily on plants with water cooled reactors
Test design requirements: Canister-scale heater test

International Nuclear Information System (INIS)

Schauer, M.I.; Craig, P.A.; Stickney, R.G.

1986-03-01

This document establishes the Test Design Requirements for the design of a canister scale heater test to be performed in the Exploratory Shaft test facility. The purpose of the test is to obtain thermomechanical rock mass response data for use in validation of the numerical models. The canister scale heater test is a full scale simulation of a high-level nuclear waste container in a prototypic emplacement borehole. Electric heaters are used to simulate the heat loads expected in an actual waste container. This document presents an overview of the test including objectives and justification for the test. A description of the test as it is presently envisioned is included. Discussions on Quality Assurance and Safety are also included in the document. 12 refs., 1 fig
Testable Design and testing of Microsystems

NARCIS (Netherlands)

Kerkhoff, Hans G.

2005-01-01

The market of microsystems, incorporating microelectronics with e.g. MEMS-based sensors and actuators increases rapidly. The often non-electrical sensors and actuators are notoriously difficult and/or expensive to test. As the entire micro system has to meet certain quality criteria for specific
Banki-Michell Optimal Design by Computational Fluid Dynamics Testing and Hydrodynamic Analysis

Directory of Open Access Journals (Sweden)

Tullio Tucciarelli

2013-04-01

Full Text Available In hydropower, the exploitation of small power sources requires the use of small turbines that combine efficiency and economy. Banki-Michell turbines represent a possible choice for their simplicity and for their good efficiency under variable load conditions. Several experimental and numerical tests have already been designed for examining the best geometry and optimal design of cross-flow type machines, but a theoretical framework for a sequential design of the turbine parameters, taking full advantage of recently expanded computational capabilities, is still missing. To this aim, after a review of the available criteria for Banki-Michell parameter design, a novel two-step procedure is described. In the first step, the initial and final blade angles, the outer impeller diameter and the shape of the nozzle are selected using a simple hydrodynamic analysis, based on a very strong simplification of reality. In the second step, the inner diameter, as well as the number of blades and their shape, are selected by testing single options using computational fluid dynamics (CFD simulations, starting from the suggested literature values. Good efficiency is attained not only for the design discharge, but also for a large range of variability around the design value.
The computer-aided design of a servo system as a multiple-criteria decision problem

NARCIS (Netherlands)

Udink ten Cate, A.J.

1986-01-01

This paper treats the selection of controller gains of a servo system as a multiple-criteria decision problem. In contrast to the usual optimization-based approaches to computer-aided design, inequality constraints are included in the problem as unconstrained objectives. This considerably simplifies
Durability-Based Design Criteria for a Quasi-Isotropic Carbon-Fiber-Reinforced Thermoplastic Automotive Composite

Energy Technology Data Exchange (ETDEWEB)

Naus, Dan J [ORNL; Corum, James [ORNL; Klett, Lynn B [ORNL; Davenport, Mike [ORNL; Battiste, Rick [ORNL; Simpson, Jr., William A [ORNL

2006-04-01

This report provides recommended durability-based design properties and criteria for a quais-isotropic carbon-fiber thermoplastic composite for possible automotive structural applications. The composite consisted of a PolyPhenylene Sulfide (PPS) thermoplastic matrix (Fortron's PPS - Ticona 0214B1 powder) reinforced with 16 plies of carbon-fiber unidirectional tape, [0?/90?/+45?/-45?]2S. The carbon fiber was Hexcel AS-4C and was present in a fiber volume of 53% (60%, by weight). The overall goal of the project, which is sponsored by the U.S. Department of Energy's Office of Freedom Car and Vehicle Technologies and is closely coordinated with the Advanced Composites Consortium, is to develop durability-driven design data and criteria to assure the long-term integrity of carbon-fiber-based composite systems for automotive structural applications. This document is in two parts. Part 1 provides design data and correlations, while Part 2 provides the underlying experimental data and models. The durability issues addressed include the effects of short-time, cyclic, and sustained loadings; temperature; fluid environments; and low-energy impacts (e.g., tool drops and kickups of roadway debris) on deformation, strength, and stiffness. Guidance for design analysis, time-independent and time-dependent allowable stresses, rules for cyclic loadings, and damage-tolerance design guidance are provided.
ERG review of containment failure probability and repository functional design criteria

International Nuclear Information System (INIS)

Gopal, S.

1986-06-01

The Engineering Review Group (ERG) was established by the Office of Nuclear Waste Isolation (ONWI) to help evaluate engineering-related issues in the US Department of Energy's nuclear waste repository program. The June 1984 meeting of the ERG considered two topics: (1) statistical probability for containment of nuclides within the waste package and (2) repository design criteria. This report documents the ERG's comments and recommendations on these two subjects and the ONWI response to the specific points raised by ERG
Failure criteria for low-temperature irradiated organic composite insulation systems

International Nuclear Information System (INIS)

Schutz, J.B.; Fabian, P.E.

1997-01-01

Composite insulation systems in fusion magnet applications are often subjected to conditions of combined through thickness compression and shear at varying stress ratios. Characterization of insulation system strength under these conditions requires unidirectional shear and compression tests, as well as biaxial shear/compression testing to define the systems failure envelope. An appropriate failure criteria would reduce the number of tests required to define this envelope, and would give designers a better estimate of material strengths at intermediate stress ratios. Biaxial shear/compression testing requires the use of metallic sandwich specimens, which are susceptible to activation during irradiation. A reliable failure criteria which eliminates the need for biaxial characterization would also reduce the difficulty and expense involved in radiation effects characterization while still providing a complete failure envelope. Several generalized failure criteria, taken from classical composites analysis, were reformulated for application in the shear/compression quadrant. The maximum stress and Tsai-Hill criteria were found to be inadequate to represent the biaxial failure envelope. The generalized Tsai-Wu tensor quadratic failure criterion was also examined. Application of this criterion requires through thickness tensile strength data. Through thickness tensile strengths of insulation systems have not been routinely characterized, but limited data are available. Utilizing unidirectional through thickness tension, compression, and interlaminar shear strength data, the Tsai-Wu failure criteria was found to agree well with biaxial shear/compression test data
Criteria for controlled atmosphere chambers

International Nuclear Information System (INIS)

Robinson, J.N.

1980-03-01

The criteria for design, construction, and operation of controlled atmosphere chambers intended for service at ORNL are presented. Classification of chambers, materials for construction, design criteria, design, controlled atmosphere chamber systems, and operating procedures are presented. ORNL Safety Manual Procedure 2.1; ORNL Health Physics Procedure Manual Appendix A-7; and Design of Viewing Windows are included in 3 appendices
Dynamic Performance Characteristic Tests of Real Scale Lead Rubber Bearing for the Evaluation of Performance Criteria

International Nuclear Information System (INIS)

Kim, Min Kyu; Kim, Jung-Han; Choi, In-Kil

2014-01-01

Dynamic characteristic tests of full scale lead rubber bearing were performed for the evaluation of performance criteria of isolation system for nuclear power plants. For the dynamic test for a full scale rubber bearing, two 1500mm diameter lead rubber bearings were manufactured. The viewpoints of this dynamic test are determination of an ultimate shear strain level of lead rubber bearing, behavior of rubber bearing according to static and dynamic input motion, sinusoidal and random (earthquake) motion, and 1-dimentional and 2-dimensional input motion. In this study, seismic isolation device tests were performed for the evaluation of performance criteria of isolation system. Through this test, it can be recognized that in the case of considering a mechanical property test, dynamic and multi degree of loading conditions should be determined. But these differences should be examined how much affect to the global structural behavior
Comparison of Epicyclic Gearing Design Methods by Means of Quality Criteria Evaluation

Directory of Open Access Journals (Sweden)

I. V. Leonov

2015-01-01

Full Text Available The performance of modern economy depends on the usage of different machines. Execution of the many tasks a society entrusts to the machinery requires a huge amount of the mechanical energy imparted to the mechanical system due to different engines. Combining the motors and actuators in turn occurs through various transmissions.Among the numerous types of transmission the planetary gears occupy an important place. With a number of advantages and differences from other types of transmission of rotational motion, planetary gear can be used as a gear or a differential gear. The planetary gear firmly holds a leading position for its frequent use in transmissions of various technological and transport vehicles, as it has a convenient layout and high load capacity.Despite the fact that people have been using planetary gears over two thousand years, there is no simple method of their design, allowing both a minimizing design time and an optimization of their performance characteristics and technological qualities.The proposed design method is derived from the classical method of factors. It limits the number of options by isolating a promising region of a set of reduced criteria values of the overall dimensions, one of the main design criteria. A minimizing size criterion optimization is provided through rapprochement of gear sizes in two rows of gearings and proximity to the minimum possible number of teeth from the undercut condition, environment for numerous satellites, and gear assembly as well as through specifying the numbers of teeth of one of the rows to be equal to the arithmetic average of the teeth numbers of the other row.
Recommended revisions to nuclear regulatory commission seismic design criteria

International Nuclear Information System (INIS)

Coats, D.W.

1981-01-01

Task Action Plan (TAP) A-40 was developed by consolidating specific technical assistance studies initiated to identify and quantify the conservatism inherent in the seismic design sequence of current NRC criteria. Task 10 of TAP A-40 provided a technical review of the results of the other nine engineering and seismological tasks in TAP A-40 and recommended changes to the existing NRC criteria based on this review. We used the team approach to accomplish the objectives of Task 10 in an efficient manner and to provide the best technical product possible within the limited time available. The team consisted of a core group of Lawrence Livermore National Laboratory personnel and selected consultants. The recommendations summarized in this paper were not based solely on the results of the tasks in TAP A-40 but went far beyond that data base to encompass all available and appropriate literature. Some recommendations are based on the expertise of core members and consultants that stem from unpublished data, research, and experience. Copies of the pertinent sections of the Standard Review Plan (SRP) and Regulatory Guides as well as the reports developed under TAP A-40 were provided to the participants. These reports, other available engineering literature, and the experience of the consultants and core group provided technical basis for the recommendations. (orig./HP)
Engineering test facility design center

International Nuclear Information System (INIS)

Anon.

1980-01-01

The vehicle by which the fusion program would move into the engineering testing phase of fusion power development is designated the Engineering Test Facility (ETF). The ETF would provide a test bed for reactor components in the fusion environment. In order to initiate preliminary planning for the ETF decision, the Office of Fusion Energy established the ETF Design Center activity to prepare the design of the ETF. This section describes the status of this design
10 CFR Appendix A to Part 30 - Criteria Relating to Use of Financial Tests and Parent Company Guarantees for Providing...

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Criteria Relating to Use of Financial Tests and Parent... MATERIAL Pt. 30, App. A Appendix A to Part 30—Criteria Relating to Use of Financial Tests and Parent... on a demonstration that the parent company passes a financial test. This appendix establishes...
Designing and testing prototypes

NARCIS (Netherlands)

Vereijken, P.; Wijnands, F.; Stol, W.

1995-01-01

This second progress report focuses on designing a theoretical prototype by linking parameters to methods and designing the methods in this context until they are ready for initial testing. The report focuses also on testing and improving the prototype in general and the methods in particular until
40 CFR 80.584 - What are the precision and accuracy criteria for approval of test methods for determining the...

Science.gov (United States)

2010-07-01

... criteria for approval of test methods for determining the sulfur content of motor vehicle diesel fuel, NRLM....584 What are the precision and accuracy criteria for approval of test methods for determining the... available gravimetric sulfur standard in the range of 1-10 ppm sulfur shall not differ from the accepted...
Formal Functional Test Designs: Bridging the Gap Between Test Requirements and Test Specifications

Science.gov (United States)

Hops, Jonathan

1993-01-01

This presentation describes the testing life cycle, the purpose of the test design phase, and test design methods and gives an example application. Also included is a description of Test Representation Language (TRL), a summary of the language, and an example of an application of TRL. A sample test requirement and sample test design are included.
Repository operational criteria analysis

International Nuclear Information System (INIS)

Hageman, J.P.; Chowdhury, A.H.

1992-08-01

The objective of the ''Repository Operational Criteria (ROC) Feasibility Studies'' (or ROC task) was to conduct comprehensive and integrated analyses of repository design, construction, and operations criteria in 10 CFR Part 60 regulations, considering the interfaces and impacts of any potential changes to those regulations. The study addresses regulatory criteria related to the preclosure aspects of the geologic repository. The study task developed regulatory concepts or potential repository operational criteria (PROC) based on analysis of a repository's safety functions and other regulations for similar facilities. These regulatory concepts or PROC were used as a basis to assess the sufficiency and adequacy of the current criteria in 10 CFR Part 60. Where the regulatory concepts were same as current operational criteria, these criteria were referenced. The operations criteria referenced or the PROC developed are given in this report. Detailed analyses used to develop the regulatory concepts and any necessary PROC for those regulations that may require a minor change are also presented. The results of the ROC task showed a need for further analysis and possible major rule change related to the design bases of a geologic repository operations area, siting, and radiological emergency planning

Third Joint GIF–IAEA Workshop on Safety Design Criteria for Sodium-Cooled Fast Reactors, 26-27 February 2013, Vienna, Austria. Summary Report

International Nuclear Information System (INIS)

2013-01-01

The main objectives of the meeting were to: • Present and share information on the work carried out by GIF, the IAEA and the Member States on the definition of safety design criteria for SFR, including safety approach and requirements on general plant design; • Present the document prepared by the GIF-SFR Task Force on Safety Design Criteria; • Present and discuss safety design concepts of SFRs under development in Member States, with particular emphasis on design measures against Design Basis Accidents and Design Extended Conditions, as well as the associated safety evaluations and supporting R&D; • Draft a room document which should be the basis of the discussion for the Panel on Safety Design Criteria of the FR13 Conference in Paris. • Discuss the results and agree on the future actions of the 3rd Joint GIF-IAEA Workshop on Safety of Sodium-Cooled Fast Reactors
42 CFR Appendix F to Part 5 - Criteria for Designation of Areas Having Shortages of Pharmacy Professional(s)

Science.gov (United States)

2010-10-01

... of Pharmacy Professional(s) F Appendix F to Part 5 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF..., App. F Appendix F to Part 5—Criteria for Designation of Areas Having Shortages of Pharmacy... of pharmacy professional(s) if the following three criteria are met: 1. The area is a rational area...
42 CFR Appendix G to Part 5 - Criteria for Designation of Areas Having Shortages of Veterinary Professional(s)

Science.gov (United States)

2010-10-01

... of Veterinary Professional(s) G Appendix G to Part 5 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT... Pt. 5, App. G Appendix G to Part 5—Criteria for Designation of Areas Having Shortages of Veterinary Professional(s) Part I—Geographic Areas A. Criteria for Food Animal Veterinary Shortage. A geographic area will...
Functional design criteria radioactive liquid waste line replacement, Project W-087. Revision 3

International Nuclear Information System (INIS)

McVey, C.B.

1994-01-01

This document provides the functional design criteria for the 222-S Laboratory radioactive waste drain piping and transfer pipeline replacement. The project will replace the radioactive waste drain piping from the hot cells in 222-S to the 219-S Waste Handling Facility and provide a new waste transfer route from 219-S to the 244-S Catch Station in Tank Farms
The 1995 forum on appropriate criteria and methods for seismic design of nuclear piping

International Nuclear Information System (INIS)

Slagis, G.C.

1996-01-01

A record of the 1995 Forum on Appropriate Criteria and Methods for Seismic Design of Nuclear Piping is provided. The focus of the forum was the earthquake experience data base and whether the data base demonstrates that seismic inertia loads will not cause failure in ductile piping systems. This was a follow-up to the 1994 Forum when the use of earthquake experience data, including the recent Northridge earthquake, to justify a design-by-rule method was explored. Two possible topics for the next forum were identified--inspection after an earthquake and design for safe-shutdown earthquake only
Preliminary proposed seismic design and evaluation criteria for new and existing underground hazardous materials storage tanks

International Nuclear Information System (INIS)

Kennedy, R.P.

1991-01-01

The document provides a recommended set of deterministic seismic design and evaluation criteria for either new or existing underground hazardous materials storage tanks placed in either the high hazard or moderate hazard usage catagories of UCRL-15910. The criteria given herein are consistent with and follow the same philosophy as those given in UCRL-15910 for the US Department of Energy facilities. This document is intended to supplement and amplify upon Reference 1 for underground hazardous materials storage tanks
Process, background and design criteria of the gas cleaning at Puertollano IGCC

Energy Technology Data Exchange (ETDEWEB)

Pisa, J. [Elcogas, Madrid (Spain)

1998-11-01

The Puertollano IGCC plant selected cooling by a water-tube boiler with upstream quenching at high velocities that requires a dust-free cooling gas at not less than 250{degree}C in order not to penalise the heat recovery efficiency. A filtration system for gas dedusting in the 250{degree}C temperature range has been installed and will be commissioned at the end of 1997. The gas cleaning concept is completed with a Venturi Scrubber, a COS hydrolysis reactor and a MDEA column to strip the sulphuric acid to yield clean gas. The gasification island is based upon the PRENFLO system which is an entrained-flow system with dry feeding. The selection of the filter system arrangement considered the limited operational experience in comparable operating conditions and acknowledged the flexibility of the filter system versus the cyclone-scrubber as far as easier load variation operation, the reduction of residues needing deposition and increased slag flow, as well as easier maintenance. Additionally to the ceramic test filters in Furstenhausen (PRENFLO) and Deer Park near Houston (SHELL), ceramic candle-type filter were selected in Buggenum and at Wabash River, and for the KoBra plant. The main criteria for the selection of the filter system and the type of candle were: separation efficiency to match clean gas limits; uniform distribution of the dust-laden gas to the filters; wear-resistant routing of the dust-laden gas flow; need for a supporting structure which must cope with sudden pressure fluctuations; optimised pulse gas system; and maintenance and repair. Based upon the above criteria, the PRENFLO concept requirements and the gas turbine specification, an arrangement with two pressure filter vessels with LLB design and filter elements manufactured by Schumacher has been installed in Puertollano. 2 figs., 3 tabs.
Architectural design criteria for f-block metal sequestering agents. 1997 annual progress report

International Nuclear Information System (INIS)

Hay, B.P.; Paine, R.T.; Roundhill, D.M.

1997-01-01

'The objective of this project is to provide the means to optimize ligand architecture for f-block metal recognition. The authors strategy builds on an innovative and successful molecular modeling approach in developing polyether ligand design criteria for the alkali and alkaline earth cations. The hypothesis underlying this proposal is that differences in metal ion binding with multidentate ligands bearing the same number and type of donor groups are primarily attributable to intramolecular steric factors. The authors propose quantifying these steric factors through the application of molecular mechanics models. The proposed research involves close integration of theoretical and experimental chemistry. The experimental work entails synthesizing novel ligands and experimentally determining structures and binding constants for metal ion complexation by series of ligands in which architecture is systematically varied. The theoretical work entails using electronic structure calculations to parameterize a molecular mechanics force field for a range of metal ions and ligand types. The resulting molecular mechanics force field will be used to predict low-energy structures for unidentate, bidentate, and multidentate ligands and their metal complexes through conformational searches. Results will be analyzed to assess the relative importance of several steric factors including optimal M-L length, optimal geometry at the metal center, optimal geometry at the donor atoms (complementarity), and conformation prior to binding (preorganization). An accurate set of criteria for the design of ligand architecture will be obtained from these results. These criteria will enable researchers to target ligand structures for synthesis and thereby dramatically reduce the time and cost associated with metal-specific ligand development.'
Probability-Based Design Criteria of the ASCE 7 Tsunami Loads and Effects Provisions (Invited)

Science.gov (United States)

Chock, G.

2013-12-01

Mitigation of tsunami risk requires a combination of emergency preparedness for evacuation in addition to providing structural resilience of critical facilities, infrastructure, and key resources necessary for immediate response and economic and social recovery. Critical facilities would include emergency response, medical, tsunami refuges and shelters, ports and harbors, lifelines, transportation, telecommunications, power, financial institutions, and major industrial/commercial facilities. The Tsunami Loads and Effects Subcommittee of the ASCE/SEI 7 Standards Committee is developing a proposed new Chapter 6 - Tsunami Loads and Effects for the 2016 edition of the ASCE 7 Standard. ASCE 7 provides the minimum design loads and requirements for structures subject to building codes such as the International Building Code utilized in the USA. In this paper we will provide a review emphasizing the intent of these new code provisions and explain the design methodology. The ASCE 7 provisions for Tsunami Loads and Effects enables a set of analysis and design methodologies that are consistent with performance-based engineering based on probabilistic criteria. . The ASCE 7 Tsunami Loads and Effects chapter will be initially applicable only to the states of Alaska, Washington, Oregon, California, and Hawaii. Ground shaking effects and subsidence from a preceding local offshore Maximum Considered Earthquake will also be considered prior to tsunami arrival for Alaska and states in the Pacific Northwest regions governed by nearby offshore subduction earthquakes. For national tsunami design provisions to achieve a consistent reliability standard of structural performance for community resilience, a new generation of tsunami inundation hazard maps for design is required. The lesson of recent tsunami is that historical records alone do not provide a sufficient measure of the potential heights of future tsunamis. Engineering design must consider the occurrence of events greater than
Assessing the Quality of Academic Libraries on the Web: The Development and Testing of Criteria.

Science.gov (United States)

Chao, Hungyune

2002-01-01

This study develops and tests an instrument useful for evaluating the quality of academic library Web sites. Discusses criteria for print materials and human-computer interfaces; user-based perspectives; the use of factor analysis; a survey of library experts; testing reliability through analysis of variance; and regression models. (Contains 53…
Design criteria and candidate electrical power systems for a reusable Space Shuttle booster.

Science.gov (United States)

Merrifield, D. V.

1972-01-01

This paper presents the results of a preliminary study to establish electrical power requirements, investigate candidate power sources, and select a representative power generation concept for the NASA Space Shuttle booster stage. Design guidelines and system performance requirements are established. Candidate power sources and combinations thereof are defined and weight estimates made. The selected power source concept utilizes secondary silver-zinc batteries, engine-driven alternators with constant speed drive, and an airbreathing gas turbine. The need for cost optimization, within safety, reliability, and performance constraints, is emphasized as being the most important criteria in design of the final system.
Design Criteria, Operating Conditions, and Nickel-Iron Hydroxide Catalyst Materials for Selective Seawater Electrolysis.

Science.gov (United States)

Dionigi, Fabio; Reier, Tobias; Pawolek, Zarina; Gliech, Manuel; Strasser, Peter

2016-05-10

Seawater is an abundant water resource on our planet and its direct electrolysis has the advantage that it would not compete with activities demanding fresh water. Oxygen selectivity is challenging when performing seawater electrolysis owing to competing chloride oxidation reactions. In this work we propose a design criterion based on thermodynamic and kinetic considerations that identifies alkaline conditions as preferable to obtain high selectivity for the oxygen evolution reaction. The criterion states that catalysts sustaining the desired operating current with an overpotential seawater-mimicking electrolyte. The catalyst was synthesized by a solvothermal method and the activity, surface redox chemistry, and stability were tested electrochemically in alkaline and near-neutral conditions (borate buffer at pH 9.2) and under both fresh seawater conditions. The Tafel slope at low current densities is not influenced by pH or presence of chloride. On the other hand, the addition of chloride ions has an influence in the temporal evolution of the nickel reduction peak and on both the activity and stability at high current densities at pH 9.2. Faradaic efficiency close to 100 % under the operating conditions predicted by our design criteria was proven using in situ electrochemical mass spectrometry. © 2016 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.
JSFR design progress related to development of safety design criteria for generation IV sodium-cooled fast reactors. (3) Progress of component design

International Nuclear Information System (INIS)

Enuma, Yasuhiro; Kawasaki, Nobuchika; Orita, Junichi; Eto, Masao; Miyagawa, Takayuki

2015-01-01

In the frame work of generation IV international forum (GIF), safety design criteria (SDC) and safety design guideline (SDG) for the generation IV sodium-cooled fast reactors have been developing in the circumstance of worldwide deployment of SFRs. JAEA, JAPC, MFBR have been investigating design study for JSFR to satisfy SDC in the feasibility study of SDG for Sodium-cooled Fast Reactor (SFR). In addition to the safety measures, maintainability, reparability and manufacturability are taken into account in the JSFR design study. This paper describes the design of main components. Enlargement of the access route for the inspection devices and addition of the access routes were carried out for the reactor structure. The pump-integrated IHX (pump/IHX) was modified for the primary heat exchanger (PHX), which was installed for the decay heat removal in the IHX at the upper plenum, to be removable for improved repair and maintenance. For the steam generator (SG), protective wall tube type design is under investigation as an option with less R and D risks. (author)
Siting a municipal solid waste disposal facility, part II: the effects of external criteria on the final decision.

Science.gov (United States)

Korucu, M Kemal; Karademir, Aykan

2014-02-01

The procedure of a multi-criteria decision analysis supported by the geographic information systems was applied to the site selection process of a planning municipal solid waste management practice based on twelve different scenarios. The scenarios included two different decision tree modes and two different weighting models for three different area requirements. The suitability rankings of the suitable sites obtained from the application of the decision procedure for the scenarios were assessed by a factorial experimental design concerning the effect of some external criteria on the final decision of the site selection process. The external criteria used in the factorial experimental design were defined as "Risk perception and approval of stakeholders" and "Visibility". The effects of the presence of these criteria in the decision trees were evaluated in detail. For a quantitative expression of the differentiations observed in the suitability rankings, the ranking data were subjected to ANOVA test after a normalization process. Then the results of these tests were evaluated by Tukey test to measure the effects of external criteria on the final decision. The results of Tukey tests indicated that the involvement of the external criteria into the decision trees produced statistically meaningful differentiations in the suitability rankings. Since the external criteria could cause considerable external costs during the operation of the disposal facilities, the presence of these criteria in the decision tree in addition to the other criteria related to environmental and legislative requisites could prevent subsequent external costs in the first place.
Neutron absorber qualification and acceptance testing from the designer's perspective

International Nuclear Information System (INIS)

Bracey, W.; Chiocca, R.

2004-01-01

Starting in the mid 1990's, the USNRC began to require less than 100% credit for the 10B present in fixed neutron absorbers spent fuel transport packages. The current practice in the US is to use only 75% of the specified 10B in criticality safety calculations unless extensive acceptance testing demonstrates both the presence of the 10B and uniformity of its distribution. In practice, the NRC has accepted no more than 90% credit for 10B in recent years, while other national competent authorities continue to accept 100%. More recently, with the introduction of new neutron absorber materials, particularly aluminum / boron carbide metal matrix composites, the NRC has also expressed expectations for qualification testing, based in large part on Transnuclear's successful application to use a new composite material in the TN-68 storage / transport cask. The difficulty is that adding more boron than is really necessary to a metal has some negative effects on the material, reducing the ductility and the thermal conductivity, and increasing the cost. Excessive testing requirements can have the undesired effect of keeping superior materials out of spent fuel package designs, without a corresponding justification based on public safety. In European countries and especially in France, 100% credit has been accepted up to now with materials controls specified in the Safety Analysis Report (SAR): Manufacturing process approved by qualification testing Materials manufacturing controlled under a Quality Assurance system. During fabrication, acceptance testing directly on products or on representative samples. Acceptance criteria taking into account a statistical uncertainty corresponding to 3σ. The original and current bases for the reduced 10 B credit, the design requirements for neutron absorber materials, and the experience of Transnuclear and Cogema Logistics with neutron absorber testing are examined. Guidelines for qualification and acceptance testing and process controls
Medication overuse headache and chronic migraine in a specialized headache centre: field-testing proposed new appendix criteria

DEFF Research Database (Denmark)

Zeeberg, P; Olesen, Jes; Jensen, R

2009-01-01

The classification subcommittee of the International Headache Society (IHS) has recently suggested revised criteria for medication overuse headache (MOH) and chronic migraine (CM). We field tested these revised criteria by applying them to the headache population at the Danish Headache Centre...... suggest that the IHS has succeeded in choosing new criteria for CM which are neither too strict, nor too loose. For MOH, a shift to the appendix criteria will increase the number of MOH patients, but take into account the possibility of permanent changes in pain perception due to medication overuse...... and the possibility of a renewed effect of prophylactic drugs due to medication withdrawal. We therefore recommend the implementation of the appendix criteria for both MOH and CM into the main body of the International Classification of Headache Disorders....
Idaho National Laboratory Lead or Lead-Bismuth Eutectic (LBE) Test Facility - R&D Requirements, Design Criteria, Design Concept, and Concept Guidance

Energy Technology Data Exchange (ETDEWEB)

Eric P. Loewen; Paul Demkowicz

2005-05-01

The Idaho National Laboratory Lead-Bismuth Eutectic Test Facility will advance the state of nuclear technology relative to heavy-metal coolants (primarily Pb and Pb-Bi), thereby allowing the U.S. to maintain the pre-eminent position in overseas markets and a future domestic market. The end results will be a better qualitative understanding and quantitative measure of the thermal physics and chemistry conditions in the molten metal systems for varied flow conditions (single and multiphase), flow regime transitions, heat input methods, pumping requirements for varied conditions and geometries, and corrosion performance. Furthering INL knowledge in these areas is crucial to sustaining a competitive global position. This fundamental heavy-metal research supports the National Energy Policy Development Group’s stated need for energy systems to support electrical generation.1 The project will also assist the Department of Energy in achieving goals outlined in the Nuclear Energy Research Advisory Committee Long Term Nuclear Technology Research and Development Plan,2 the Generation IV Roadmap for Lead Fast Reactor development, and Advanced Fuel Cycle Initiative research and development. This multi-unit Lead-Bismuth Eutectic Test Facility with its flexible and reconfigurable apparatus will maintain and extend the U.S. nuclear knowledge base, while educating young scientists and engineers. The uniqueness of the Lead-Bismuth Eutectic Test Facility is its integrated Pool Unit and Storage Unit. This combination will support large-scale investigation of structural and fuel cladding material compatibility issues with heavy-metal coolants, oxygen chemistry control, and thermal hydraulic physics properties. Its ability to reconfigure flow conditions and piping configurations to more accurately approximate prototypical reactor designs will provide a key resource for Lead Fast Reactor research and development. The other principal elements of the Lead-Bismuth Eutectic Test Facility
9 CFR 381.94 - Contamination with Microorganisms; process control verification criteria and testing; pathogen...

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Contamination with Microorganisms... § 381.94 Contamination with Microorganisms; process control verification criteria and testing; pathogen... maintaining process controls sufficient to prevent fecal contamination. FSIS shall take further action as...
Design criteria for stable Pt/C fuel cell catalysts

Directory of Open Access Journals (Sweden)

Josef C. Meier

2014-01-01

Full Text Available Platinum and Pt alloy nanoparticles supported on carbon are the state of the art electrocatalysts in proton exchange membrane fuel cells. To develop a better understanding on how material design can influence the degradation processes on the nanoscale, three specific Pt/C catalysts with different structural characteristics were investigated in depth: a conventional Pt/Vulcan catalyst with a particle size of 3–4 nm and two Pt@HGS catalysts with different particle size, 1–2 nm and 3–4 nm. Specifically, Pt@HGS corresponds to platinum nanoparticles incorporated and confined within the pore structure of the nanostructured carbon support, i.e., hollow graphitic spheres (HGS. All three materials are characterized by the same platinum loading, so that the differences in their performance can be correlated to the structural characteristics of each material. The comparison of the activity and stability behavior of the three catalysts, as obtained from thin film rotating disk electrode measurements and identical location electron microscopy, is also extended to commercial materials and used as a basis for a discussion of general fuel cell catalyst design principles. Namely, the effects of particle size, inter-particle distance, certain support characteristics and thermal treatment on the catalyst performance and in particular the catalyst stability are evaluated. Based on our results, a set of design criteria for more stable and active Pt/C and Pt-alloy/C materials is suggested.
Buckling design criteria for waste package disposal containers in mined salt repositories: Technical report

International Nuclear Information System (INIS)

Mallett, R.H.

1986-12-01

This report documents analytical and experimental results from a survey of the technical literature on buckling of thick-walled cylinders under external pressure. Based upon these results, a load factor is suggested for the design of waste package containers for disposal of high-level radioactive waste in repositories mined in salt formations. The load factor is defined as a ratio of buckling pressure to allowable pressure. Specifically, a load factor which ranges from 1.5 for plastic buckling to 3.0 for elastic buckling is included in a set of proposed buckling design criteria for waste disposal containers. Formulas are given for buckling design under axisymmetric conditions. Guidelines are given for detailed inelastic buckling analyses which are generally required for design of disposal containers

Multiple-Criteria Decision-Making in the Design of Innovative Lock Walls for Barge Impact; Phase 1

National Research Council Canada - National Science Library

Lambert, James

2001-01-01

.... This research project consists of two phases: Phase 1, which culminates with this report, investigated the use of multiple-criteria decision-making in the design process of lock approach walls to consider barge impact and earthquake loads...
Program Helps Design Tests Of Developmental Software

Science.gov (United States)

Hops, Jonathan

1994-01-01

Computer program called "A Formal Test Representation Language and Tool for Functional Test Designs" (TRL) provides automatic software tool and formal language used to implement category-partition method and produce specification of test cases in testing phase of development of software. Category-partition method useful in defining input, outputs, and purpose of test-design phase of development and combines benefits of choosing normal cases having error-exposing properties. Traceability maintained quite easily by creating test design for each objective in test plan. Effort to transform test cases into procedures simplified by use of automatic software tool to create cases based on test design. Method enables rapid elimination of undesired test cases from consideration and facilitates review of test designs by peer groups. Written in C language.
The Combat System Design and Test Criteria for Iguana TM Armored Vehicles

National Research Council Canada - National Science Library

Alper, Irfan

1999-01-01

... acoustic/IR signatures. The Iguana(trademark), a tracked vehicle concept based on a recently patented suspension and track design, could deploy to hot spots world-wide on peacekeeping and combat missions which require extra flexibility to adapt...
Low Density Supersonic Decelerator Flight Dynamics Test-1 Flight Design and Targeting

Science.gov (United States)

Ivanov, Mark

2015-01-01

NASA's Low Density Supersonic Decelerator (LDSD) program was established to identify, develop, and eventually qualify to Test [i.e. Technology] Readiness Level (TRL) - 6 aerodynamic decelerators for eventual use on Mars. Through comprehensive Mars application studies, two distinct Supersonic Inflatable Aerodynamic Decelerator (SIAD) designs were chosen that afforded the optimum balance of benefit, cost, and development risk. In addition, a Supersonic Disk Sail (SSDS) parachute design was chosen that satisfied the same criteria. The final phase of the multi-tiered qualification process involves Earth Supersonic Flight Dynamics Tests (SFDTs) within environmental conditions similar to those that would be experienced during a Mars Entry, Descent, and Landing (EDL) mission. The first of these flight tests (i.e. SFDT-1) was completed on June 28, 2014 with two more tests scheduled for the summer of 2015 and 2016, respectively. The basic flight design for all the SFDT flights is for the SFDT test vehicle to be ferried to a float altitude of 120 kilo-feet by a 34 thousand cubic feet (Mcf) heavy lift helium balloon. Once float altitude is reached, the test vehicle is released from the balloon, spun-up for stability, and accelerated to supersonic speeds using a Star48 solid rocket motor. After burnout of the Star48 motor the vehicle decelerates to pre-flight selected test conditions for the deployment of the SIAD system. After further deceleration with the SIAD deployed, the SSDS parachute is then deployed stressing the performance of the parachute in the wake of the SIAD augmented blunt body. The test vehicle/SIAD/parachute system then descends to splashdown in the Pacific Ocean for eventual recovery. This paper will discuss the development of both the test vehicle and the trajectory sequence including design trade-offs resulting from the interaction of both engineering efforts. In addition, the SFDT-1 nominal trajectory design and associated sensitivities will be discussed
Principle design and data of graphite components

International Nuclear Information System (INIS)

Ishihara, Masahiro; Sumita, Junya; Shibata, Taiju; Iyoku, Tatsuo; Oku, Tatsuo

2004-01-01

The High Temperature Engineering Test Reactor (HTTR) constructed by Japan Atomic Energy Research Institute (JAERI) is a graphite-moderated and helium-gas-cooled reactor with prismatic fuel elements of hexagonal blocks. The reactor internal structures of the HTTR are mainly made up of graphite components. As well known, the graphite is a brittle material and there were no available design criteria for brittle materials. Therefore, JAERI had to develop the design criteria taking account of the brittle fracture behavior. In this paper, concept and key specification of the developed graphite design criteria is described, and also an outline of the quality control specified in the design criteria is mentioned
Explaining the Criteria of Designing Urban Furniture and Landscape, with a Cultural-social Design Approach

Directory of Open Access Journals (Sweden)

Marzieh Allahdadi

2017-09-01

Full Text Available Attention to the deep relationship between human personality and the place in which he lives causes the place to play a crucial role in cultural transformations and prevalence of human life style and formation of values, connections and human activities. Cities are not just a place of transit, but they are also environments that must have mutual communications with the inhabitants in order to realize the meaning of citizen, as there is a distinction between the status of citizenship and urbanization. Urban furniture is one of the elements of urban space that its quantity, beauty and durability play a major role in achieving a healthy and favorable city and satisfies the needs of citizens in terms of performance and beauty. Accordingly, the present study, using descriptive-analytical method and with data collection tools including library and documentary studies, examines the concept of product ecology and answers to the questions whether urban furniture can start or support social interaction or positively affect the roles of citizens? In this paper, the relationship between social-cultural design in urban furniture and the disturbances regarding uneven distribution of elements are identified, and finally the criteria of designing urban furniture and landscape are expressed with a social-design approach.
Architectural design criteria for f-block metal ion sequestering agents. 1998 annual progress report

International Nuclear Information System (INIS)

Dixon, D.A.; Hay, B.P.; Paine, R.T.; Raymond, K.N.; Rogers, R.D.; Roundhill, D.M.

1998-01-01

'The objective of this project is to provide a means to optimize ligand architecture for f-block metal recognition. The authors strategy builds on an innovative and successful molecular modeling approach in developing polyether ligand design criteria for the alkali and alkaline earth cations. The hypothesis underlying this proposal is that differences in metal ion binding with multidentate ligands bearing the same number and type of donor groups are primarily attributable to intramolecular steric factors. They propose quantifying these steric factors through the application of molecular mechanics models. The research involves close integration of theoretical and experimental chemistry. The experimental work entails synthesizing novel ligands and experimentally determining structures and binding constants for metal ion complexation by series of ligands in which architecture is systematically varied. The theoretical work entails using electronic structure calculations to parameterize a molecular mechanics force field for a range of metal ions and ligand types. The resulting molecular mechanics force field will be used to predict low energy structures for unidentate, bidentate, and multidentate ligands and their metal complexes through conformational searches. Results will be analyzed to assess the relative importance of several steric factors including optimal M-L length, optimal geometry at the metal center, optimal geometry at the donor atoms (complementarity), and conformation prior to binding (preorganization). An accurate set of criteria for the design of ligand architecture will be obtained from these results. These criteria will enable researchers to target ligand structures for synthesis and thereby dramatically reduce the time and cost associated with metal-specific ligand development.'
Evidence-based point-of-care tests and device designs for disaster preparedness.

Science.gov (United States)

Brock, T Keith; Mecozzi, Daniel M; Sumner, Stephanie; Kost, Gerald J

2010-01-01

To define pathogen tests and device specifications needed for emerging point-of-care (POC) technologies used in disasters. Surveys included multiple-choice and ranking questions. Multiple-choice questions were analyzed with the chi2 test for goodness-of-fit and the binomial distribution test. Rankings were scored and compared using analysis of variance and Tukey's multiple comparison test. Disaster care experts on the editorial boards of the American Journal of Disaster Medicine and the Disaster Medicine and Public Health Preparedness, and the readers of the POC Journal. Vibrio cholera and Staphylococcus aureus were top-ranked pathogens for testing in disaster settings. Respondents felt that disaster response teams should be equipped with pandemic infectious disease tests for novel 2009 H1N1 and avian H5N1 influenza (disaster care, p disaster settings, respondents preferred self-contained test cassettes (disaster care, p disaster care, p disaster care scenarios, in which Vibrio cholera, methicillin-sensitive and methicillin-resistant Staphylococcus aureus, and Escherichia coli ranked the highest. POC testing should incorporate setting-specific design criteria such as safe disposable cassettes and direct blood sampling at the site of care.
A multi-criteria decision aid methodology to design electric vehicles public charging networks

Directory of Open Access Journals (Sweden)

João Raposo

2015-05-01

Full Text Available This article presents a new multi-criteria decision aid methodology, dynamic-PROMETHEE, here used to design electric vehicle charging networks. In applying this methodology to a Portuguese city, results suggest that it is effective in designing electric vehicle charging networks, generating time and policy based scenarios, considering offer and demand and the city’s urban structure. Dynamic-PROMETHE adds to the already known PROMETHEE’s characteristics other useful features, such as decision memory over time, versatility and adaptability. The case study, used here to present the dynamic-PROMETHEE, served as inspiration and base to create this new methodology. It can be used to model different problems and scenarios that may present similar requirement characteristics.
A multi-criteria decision aid methodology to design electric vehicles public charging networks

Science.gov (United States)

Raposo, João; Rodrigues, Ana; Silva, Carlos; Dentinho, Tomaz

2015-05-01

This article presents a new multi-criteria decision aid methodology, dynamic-PROMETHEE, here used to design electric vehicle charging networks. In applying this methodology to a Portuguese city, results suggest that it is effective in designing electric vehicle charging networks, generating time and policy based scenarios, considering offer and demand and the city's urban structure. Dynamic-PROMETHE adds to the already known PROMETHEE's characteristics other useful features, such as decision memory over time, versatility and adaptability. The case study, used here to present the dynamic-PROMETHEE, served as inspiration and base to create this new methodology. It can be used to model different problems and scenarios that may present similar requirement characteristics.
Numerical multi-criteria optimization methods for alloy design. Development of new high strength nickel-based superalloys and experimental validation

Energy Technology Data Exchange (ETDEWEB)

Rettig, Ralf; Mueller, Alexander; Ritter, Nils C.; Singer, Robert F. [Institute of Science and Technology of Metals, Department of Materials Science and Engineering, University of Erlangen (Germany)

2016-07-01

A new approach for the design of optimum balanced metallic alloys is presented. It is based on a mathematical multi-criteria optimization method which uses different property models to predict the alloy behavior in dependency of composition. These property models are mostly based on computational thermodynamics (CALPHAD-method). The full composition range of the alloying elements can be considered using these models. In alloy design usually several contradicting goals have to be fulfilled. This is handled by the calculation of so-called Pareto-fronts. The aim of our approach is to guide the experimental research towards new alloy compositions that have a high probability of having very good properties. Consequently the number of required test alloys can be massively reduced. The approach will be demonstrated for the computer-aided design of a new Re-free superalloy with nearly identical creep strength as that of Re-containing superalloys. Our starting point for the design was to maintain the good properties of the gamma prime-phase in well-known alloys like CMSX-4 and to maximize the solid solution strengthening of W and Mo. The presented experimental measurements proof the excellent properties.
MITG test assembly design and fabrication

International Nuclear Information System (INIS)

Schock, A.

1983-01-01

The design, analysis, and evaluation of the Modular Isotopic Thermoelectric Generator (MITG), described in an earlier paper, led to a program to build and test prototypical, modules of that generator. Each test module duplicates the thermoelectric converters, thermal insulation, housing and radiator fins of a typical generator slice, and simulates its isotope heat source module by means of an electrical heater encased in a prototypical graphite box. Once the approx. 20-watt MITG module has been developed, it can be assembled in appropriate number to form a generator design yielding the desired power output. The present paper describes the design and fabrication of the MITG test assembly, which confirmed the fabricability of the multicouples and interleaved multifoil insulation called for by the design. Test plans, procedures, instrumentation, results, and post-test analyses, as well as revised designs, fabrication procedures, and performance estimates, are described in subsequent papers in these proceedings
IFE chamber technology testing program in NIF and chamber development test plan

International Nuclear Information System (INIS)

Abdou, M.A.

1995-01-01

Issues concerning chamber technology testing program in NIF involving: criteria for evaluation/prioritization of experiments, engineering scaling requirements for test article design and material selection and R and D plan prior to NIF testing were addressed in this paper. In order to maximize the benefits of testing program in NIF, the testing in NIF should provide the experimental data relevant to DEMO design choice or to DEMO design predictive capability by utilizing engineering scaling test article designs. Test plans were developed for 2 promising chamber design concepts. Early testing in non-fusion/non-ignition prior to testing in ignition facility serves a critical role in chamber R and D test plans in order to reduce the risks and costs of the more complex experiments in NIF
Validation of proposed diagnostic criteria (the "Budapest Criteria") for Complex Regional Pain Syndrome.

Science.gov (United States)

Harden, R Norman; Bruehl, Stephen; Perez, Roberto S G M; Birklein, Frank; Marinus, Johan; Maihofner, Christian; Lubenow, Timothy; Buvanendran, Asokumar; Mackey, Sean; Graciosa, Joseph; Mogilevski, Mila; Ramsden, Christopher; Chont, Melissa; Vatine, Jean-Jacques

2010-08-01

Current IASP diagnostic criteria for CRPS have low specificity, potentially leading to overdiagnosis. This validation study compared current IASP diagnostic criteria for CRPS to proposed new diagnostic criteria (the "Budapest Criteria") regarding diagnostic accuracy. Structured evaluations of CRPS-related signs and symptoms were conducted in 113 CRPS-I and 47 non-CRPS neuropathic pain patients. Discriminating between diagnostic groups based on presence of signs or symptoms meeting IASP criteria showed high diagnostic sensitivity (1.00), but poor specificity (0.41), replicating prior work. In comparison, the Budapest clinical criteria retained the exceptional sensitivity of the IASP criteria (0.99), but greatly improved upon the specificity (0.68). As designed, the Budapest research criteria resulted in the highest specificity (0.79), again replicating prior work. Analyses indicated that inclusion of four distinct CRPS components in the Budapest Criteria contributed to enhanced specificity. Overall, results corroborate the validity of the Budapest Criteria and suggest they improve upon existing IASP diagnostic criteria for CRPS. Copyright (c) 2010 International Association for the Study of Pain. Published by Elsevier B.V. All rights reserved.
Rock Slope Design Criteria

Science.gov (United States)

2010-06-01

Based on the stratigraphy and the type of slope stability problems, the flat lying, Paleozoic age, sedimentary : rocks of Ohio were divided into three design units: 1) competent rock design unit consisting of sandstones, limestones, : and siltstones ...
Test Information Targeting Strategies for Adaptive Multistage Testing Designs.

Science.gov (United States)

Luecht, Richard M.; Burgin, William

Adaptive multistage testlet (MST) designs appear to be gaining popularity for many large-scale computer-based testing programs. These adaptive MST designs use a modularized configuration of preconstructed testlets and embedded score-routing schemes to prepackage different forms of an adaptive test. The conditional information targeting (CIT)…
Parameters, test criteria and fault assessment in random sampling of waste barrels from non-qualified processes

International Nuclear Information System (INIS)

Martens, B.R.

1989-01-01

In the context of random sampling tests, parameters are checked on the waste barrels and criteria are given on which these tests are based. Also, it is shown how faulty data on the properties of the waste or faulty waste barrels should be treated. To decide the extent of testing, the properties of the waste relevant to final storage are determined based on the conditioning process used. (DG) [de
Evaluation Criteria for the Educational Web-Information System

Science.gov (United States)

Seok, Soonhwa; Meyen, Edward; Poggio, John C.; Semon, Sarah; Tillberg-Webb, Heather

2008-01-01

This article addresses how evaluation criteria improve educational Web-information system design, and the tangible and intangible benefits of using evaluation criteria, when implemented in an educational Web-information system design. The evaluation criteria were developed by the authors through a content validation study applicable to…
System engineering approach in the EU Test Blanket Systems Design Integration

International Nuclear Information System (INIS)

Panayotov, D.; Sardain, P.; Boccaccini, L.V.; Salavy, J.-F.; Cismondi, F.; Jourd'Heuil, L.

2011-01-01

The complexity of the Test Blanket Systems demands diverse and comprehensive integration activities. Test Blanket Modules - Consortia of Associates (TBM-CA) applies the system engineering methods in all stages of the Test Blanket System (TBS) design integration. Completed so far integration engineering tasks cover among others status and initial set of TBS operating parameters; list of codes, standards and regulations related to TBS; planning of the TBS interfaces and baseline documentation. Most of the attention is devoted to the establishment the Helium-Cooled Lithium Lead (HCLL) and Helium-Cooled Pebble Bed Lead (HCPB) TBS configuration baseline, TBS break down into sub-systems, identification, definition and management of the internal and external interfaces, development of the TBS plant break down structure (PBS), establishment and management of the required TBS baseline documentation infrastructure. Break down of the TBS into sub-systems that is crucial for the further design and interfaces' management has been selected considering several options and using specific evaluation criteria. Process of the TBS interfaces management covers the planning, definition and description, verification and review, non-conformances and deviations, and modification and improvement processes. Process of interfaces review is developed, identifying the actors, input, activities and output of the review. Finally the relations and interactions of system engineering processes with TBM configuration management and TBM-CA Quality Management System are discussed.
Design criteria for the 200-ZP-1 interim remedial measure

International Nuclear Information System (INIS)

Mudge, J.F.; Olson, J.W.

1995-08-01

The Interim Remedial Measure Proposed Plan for the 200-ZP-1 Operable Unit recommended a pump and treat action to contain contaminated groundwater and limit further degradation of groundwater due to elevated concentrations of carbon tetrachloride, chloroform, and trichloroethylene in the 200-ZP-1 Operable Unit. This design criteria document defines the Project. The Project encompasses: site preparation; development of groundwater wells for monitoring, extraction, and injection; extraction and injection equipment; construction of a treatment system with support buildings/utilities; management; engineering design, analysis, and reporting; and operation and maintenance. A groundwater pump and treat system, hereafter the System, will be composed of extraction wells, a piping network, treatment equipment, water storage, and injection wells. Based upon engineering judgment, the selected technology in the proposed plan (DOE-RL 1994a) is air stripping of the organic contaminants followed by vapor-phase adsorption onto granulated activated carbon (GAC); liquid-phase GAC may be required as a polishing step. The Treatment Equipment refers to air stripping towers, adsorption vessels, water pumps, air blowers, instrumentation, and control devices which will be procured as a turn-key system

JSFR design progress related to development of safety design criteria for generation IV sodium-cooled fast reactors. (4) Balance of plant

International Nuclear Information System (INIS)

Chikazawa, Yoshitaka; Katoh, Atsushi; Nabeshima, Kunihiko; Ohtaka, Masahiko; Uzawa, Masayuki; Ikari, Risako; Iwasaki, Mikinori

2015-01-01

In this paper, design study and evaluation related with safety design criteria (SDC) and safety design guideline (SDG) on the balance of plant (BOP) of the demonstration JSFR including fuel handling system, power supply system, component cooling water system, building arrangement are reported. For the fuel handling system, enhancement of storage cooling system has been investigated adding diversified cooling systems. For the power supply, existing emergency power supply system has been reinforced and alternative emergency power supply system is added. For the component cooling system, requirements and relation with safety grade components such investigated. Additionally for the component cooling system, design impact when adding decay heat removal system by sea water has been investigated. For reactor building, over view of evaluation on the external events and design policy for distributed arrangement is reported. Those design study and evaluation provides background information of SDC and SDG. (author)
Design of systems on a chip design and test

CERN Document Server

Reis, Ricardo; Jess, Jochen AG

2007-01-01

Addresses the design challenges associated with generations of the semiconductor technology. This book includes contributions on three different, but complementary axes: core design, computer-aided design tools and test methods. A collection of chapters deal with the heterogeneity aspect of core designs.
40 CFR 64.3 - Monitoring design criteria.

Science.gov (United States)

2010-07-01

... duct). (iv) Established as interdependent between more than one indicator. (b) Performance criteria... collection procedures that will be used (e.g., computerized data acquisition and handling, alarm sensor, or..., noninstrumental measurement of waste feed rate or visible emissions, use of a portable analyzer or an alarm sensor...
Design criteria for XeF2 enabled deterministic transformation of bulk silicon (100) into flexible silicon layer

KAUST Repository

Hussain, Aftab M.

2016-07-15

Isotropic etching of bulk silicon (100) using Xenon Difluoride (XeF2) gas presents a unique opportunity to undercut and release ultra-thin flexible silicon layers with pre-fabricated state-of-the-art Complementary Metal Oxide Semiconductor (CMOS) electronics. In this work, we present design criteria and mechanism with a comprehensive mathematical model for this method. We consider various trench geometries and parametrize important metrics such as etch time, number of cycles and area efficiency in terms of the trench diameter and spacing so that optimization can be done for specific applications. From our theoretical analysis, we conclude that a honeycomb-inspired hexagonal distribution of trenches can produce the most efficient release of ultra-thin flexible silicon layers in terms of the number of etch cycles, while a rectangular distribution of circular trenches provides the most area efficient design. The theoretical results are verified by fabricating and releasing (varying sizes) flexible silicon layers. We observe uniform translation of design criteria into practice for etch distances and number of etch cycles, using reaction efficiency as a fitting parameter.
Design criteria for XeF2 enabled deterministic transformation of bulk silicon (100) into flexible silicon layer

KAUST Repository

Hussain, Aftab M.; Shaikh, Sohail F.; Hussain, Muhammad Mustafa

2016-01-01

Isotropic etching of bulk silicon (100) using Xenon Difluoride (XeF2) gas presents a unique opportunity to undercut and release ultra-thin flexible silicon layers with pre-fabricated state-of-the-art Complementary Metal Oxide Semiconductor (CMOS) electronics. In this work, we present design criteria and mechanism with a comprehensive mathematical model for this method. We consider various trench geometries and parametrize important metrics such as etch time, number of cycles and area efficiency in terms of the trench diameter and spacing so that optimization can be done for specific applications. From our theoretical analysis, we conclude that a honeycomb-inspired hexagonal distribution of trenches can produce the most efficient release of ultra-thin flexible silicon layers in terms of the number of etch cycles, while a rectangular distribution of circular trenches provides the most area efficient design. The theoretical results are verified by fabricating and releasing (varying sizes) flexible silicon layers. We observe uniform translation of design criteria into practice for etch distances and number of etch cycles, using reaction efficiency as a fitting parameter.
Green Supplier Selection Criteria

DEFF Research Database (Denmark)

Nielsen, Izabela Ewa; Banaeian, Narges; Golinska, Paulina

2014-01-01

Green supplier selection (GSS) criteria arise from an organization inclination to respond to any existing trends in environmental issues related to business management and processes, so GSS is integrating environmental thinking into conventional supplier selection. This research is designed...... to determine prevalent general and environmental supplier selection criteria and develop a framework which can help decision makers to determine and prioritize suitable green supplier selection criteria (general and environmental). In this research we considered several parameters (evaluation objectives......) to establish suitable criteria for GSS such as their production type, requirements, policy and objectives instead of applying common criteria. At first a comprehensive and deep review on prevalent and green supplier selection literatures performed. Then several evaluation objectives defined to assess the green...
Proposed design criteria for a fusion facility electrical ground system

International Nuclear Information System (INIS)

Armellino, C.A.

1983-01-01

Ground grid design considerations for a nuclear fusion reactor facility are no different than any other facility in that the basis for design must be safety first and foremost. Unlike a conventional industrial facility the available fault energy comes not only from the utility source and in-house rotating machinery, but also from energy storage capacitor banks, collapsing magnetic fields and D.C. transmission lines. It is not inconceivable for a fault condition occurrence where all available energy can be discharged. The ground grid must adequately shunt this sudden energy discharge in a way that personnel will not be exposed by step and/or touch to hazardous energy levels that are in excess of maximum tolerable levels for humans. Fault energy discharge rate is a function of the ground grid surge impedance characteristic. Closed loop paths must be avoided in the ground grid design so that during energy discharge no stray magnetic fields or large voltage potentials between remote points can be created by circulating currents. Single point connection of equipment to the ground grid will afford protection to personnel and sensitive equipment by reducing the probability of circulating currents. The overall ground grid system design is best illustrated as a wagon wheel concept with the fusion machine at the center. Radial branches or spokes reach out to the perimeter limits designated by step-and-touch high risk areas based on soil resistivity criteria considerations. Conventional methods for the design of a ground grid with all of its radial branches are still pertinent. The center of the grid could include a deep well single ground rod element the length of which is at least equivalent to the radius of an imaginary sphere that enshrouds the immediate machine area. Special facilities such as screen rooms or other shielded areas are part of the ground grid system by way of connection to radial branches
Design of the TFTR [Tokamak Fusion Test Reactor] maintenance manipulator

International Nuclear Information System (INIS)

Loesser, G. D.; Heitzenroeder, P.; Bohme, G.; Selig, M.

1987-01-01

The Tokamak Fusion Test Reactor (TFTR) plans to generate a total of 3 x 10 21 neutrons during its deuterium-tritium run period in 1900. This will result in high levels of radiation, especially within the TFTR vacuum vessel. The maintenance manipulator's mission is to assist TFTR in meeting Princeton Plasma Physics Laboratory's personnel radiation exposure criteria and in maintaining as-low-as-reasonably-achievable principals by limiting the radiation exposure received by operating and maintenance personnel. The manipulator, which is currently being fabricated and tested by Kernforschungszentrum Karlsruhe, is designed to perform limited, but routine and necessary, functions within the TFTR vacuum torus after activation levels within the torus preclude such functions being performed by personnel. These functions include visual inspection, tile replacement, housekeeping tasks, diagnostic calibrations, and leak detection. To meet its functional objectives, the TFTR maintenance manipulator is required to be operable in TFTR's very high vacuum environment (typically 2 x 10 -8 Torr). It must also be bakeable at 150 degree C and able to withstand the radiation environment
A multi-criteria approach to camera motion design for volume data animation.

Science.gov (United States)

Hsu, Wei-Hsien; Zhang, Yubo; Ma, Kwan-Liu

2013-12-01

We present an integrated camera motion design and path generation system for building volume data animations. Creating animations is an essential task in presenting complex scientific visualizations. Existing visualization systems use an established animation function based on keyframes selected by the user. This approach is limited in providing the optimal in-between views of the data. Alternatively, computer graphics and virtual reality camera motion planning is frequently focused on collision free movement in a virtual walkthrough. For semi-transparent, fuzzy, or blobby volume data the collision free objective becomes insufficient. Here, we provide a set of essential criteria focused on computing camera paths to establish effective animations of volume data. Our dynamic multi-criteria solver coupled with a force-directed routing algorithm enables rapid generation of camera paths. Once users review the resulting animation and evaluate the camera motion, they are able to determine how each criterion impacts path generation. In this paper, we demonstrate how incorporating this animation approach with an interactive volume visualization system reduces the effort in creating context-aware and coherent animations. This frees the user to focus on visualization tasks with the objective of gaining additional insight from the volume data.
Camelot 3: Habitability criteria space research and design studio

Science.gov (United States)

Arroyo, F.; Budet, O.; Garcia, A.; Lee, J.; Lopez, R.; Lugo, R.; Mateo, A.; Mellado, R.; Mendez, H.; Ortiz, N.

1989-01-01

Acknowledging the importance of human beings on a mission to Mars, the University of Puerto Rico studied both psychological and physiological aspects. Different conditions necessary for human health and well-being were considered. As a result, habitability criteria were developed. The criteria are as follows: personal identification; social interaction; unpredictable conditions; contact with nature; mental landscapes; privacy; equalitarian conditions; variety; functionality; sensory stimulation; music and environmental sound; stability and security; comfort; and sense of orientation.
Testing the validity and acceptability of the diagnostic criteria for Hoarding Disorder: a DSM-5 survey.

Science.gov (United States)

Mataix-Cols, D; Fernández de la Cruz, L; Nakao, T; Pertusa, A

2011-12-01

The DSM-5 Obsessive-Compulsive Spectrum Sub-Workgroup is recommending the creation of a new diagnostic category named Hoarding Disorder (HD). The validity and acceptability of the proposed diagnostic criteria have yet to be formally tested. Obsessive-compulsive disorder/hoarding experts and random members of the American Psychiatric Association (APA) were shown eight brief clinical vignettes (four cases meeting criteria for HD, three with hoarding behaviour secondary to other mental disorders, and one with subclinical hoarding behaviour) and asked to decide the most appropriate diagnosis in each case. Participants were also asked about the perceived acceptability of the criteria and whether they supported the inclusion of HD in the main manual. Altogether, 211 experts and 48 APA members completed the survey (30% and 10% response rates, respectively). The sensitivity and specificity of the HD diagnosis and the individual criteria were high (80-90%) across various types of professionals, irrespective of their experience with hoarding cases. About 90% of participants in both samples thought the criteria would be very/somewhat acceptable for professionals and sufferers. Most experts (70%) supported the inclusion of HD in the main manual, whereas only 50% of the APA members did. The proposed criteria for HD have high sensitivity and specificity. The criteria are also deemed acceptable for professionals and sufferers alike. Training of professionals and the development and validation of semi-structured diagnostic instruments should improve diagnostic accuracy even further. A field trial is now needed to confirm these encouraging findings with real patients in real clinical settings.
Regulatory principles, criteria and guidelines for site selection, design, construction and operation of uranium tailings retention systems

International Nuclear Information System (INIS)

Coady, J.R.; Henry, L.C.

1978-01-01

Principles, criteria and guidelines developed by the Atomic Energy Control Board for the management of uranium mill tailings are discussed. The application of these concepts is considered in relation to site selection, design and construction, operation and decommissioning of tailings retention facilities
Design considerations for epithermal pulse reactors

International Nuclear Information System (INIS)

Ostensen, R.W.

1978-01-01

Simplified design criteria were developed for scoping analyses of epithermal pulse reactors for use in LMFBR safety testing. By using these criteria, materials and designs were investigated to determine performance limits of moderately sized reactor cores. Several designs are suggested for further study. These are a gas-cooled core fueled with a heterogeneous mixture of Fe-UO 2 cermet and BeO-UO 2 ceramic fuels, and a heavy-water-cooled core fueled with an Fe-UO 2 cermet
Relevant criteria for testing the quality of turbulence models

DEFF Research Database (Denmark)

Frandsen, Sten Tronæs; Ejsing Jørgensen, Hans; Sørensen, J.D.

2007-01-01

Seeking relevant criteria for testing the quality of turbulence models, the scale of turbulence and the gust factor have been estimated from data and compared with predictions from first-order models of these two quantities. It is found that the mean of the measured length scales is approx. 10......% smaller than the IEC model, for wind turbine hub height levels. The mean is only marginally dependent on trends in time series. It is also found that the coefficient of variation of the measured length scales is about 50%. 3sec and 10sec pre-averaging of wind speed data are relevant for MW-size wind...... turbines when seeking wind characteristics that correspond to one blade and the entire rotor, respectively. For heights exceeding 50-60m the gust factor increases with wind speed. For heights larger the 60-80m, present assumptions on the value of the gust factor are significantly conservative, both for 3...
Engineering Trade-off Considerations Regarding Design-for-Security, Design-for-Verification, and Design-for-Test

Science.gov (United States)

Berg, Melanie; Label, Kenneth

2018-01-01

The United States government has identified that application specific integrated circuit (ASIC) and field programmable gate array (FPGA) hardware are at risk from a variety of adversary attacks. This finding affects system security and trust. Consequently, processes are being developed for system mitigation and countermeasure application. The scope of this tutorial pertains to potential vulnerabilities and countermeasures within the ASIC/FPGA design cycle. The presentation demonstrates how design practices can affect the risk for the adversary to: change circuitry, steal intellectual property, and listen to data operations. An important portion of the design cycle is assuring the design is working as specified or as expected. This is accomplished by exhaustive testing of the target design. Alternatively, it has been shown that well established schemes for test coverage enhancement (design-for-verification (DFV) and design-for-test (DFT)) can create conduits for adversary accessibility. As a result, it is essential to perform a trade between robust test coverage versus reliable design implementation. The goal of this tutorial is to explain the evolution of design practices; review adversary accessibility points due to DFV and DFT circuitry insertion (back door circuitry); and to describe common engineering trade-off considerations for test versus adversary threats.
Functional design criteria for FY 1993-2000 groundwater monitoring wells

International Nuclear Information System (INIS)

Williams, B.A.

1996-01-01

The purpose of this revision is to update the Line Item Project, 93-L-GFW-152 Functional Design Criteria (FDC) to reflect changes approved in change control M-24-91-6, Engineering Change Notices (ECNs), and expand the scope to include subsurface investigations along with the borehole drilling. This revision improves the ability and effectiveness of maintaining RCRA and Operational groundwater compliance by combining borehole and well drilling with subsurface data gathering objectives. The total projected number of wells to be installed under this project has decreased from 200 and the scope has been broadened to include additional subsurface investigation activities that usually occur simultaneously with most traditional borehole drilling and monitoring well installations. This includes borehole hydrogeologic characterization activities, and vadose monitoring. These activities are required under RCRA 40 CFR 264 and 265 and WAC 173-303 for site characterization, groundwater and vadose assessment and well placement
Photovoltaic system criteria documents. Volume 3: Environmental issues and evaluation criteria for photovoltaic applications

Science.gov (United States)

Koenig, John C.; Billitti, Joseph W.; Tallon, John M.

1979-01-01

The environmental issues and evaluation criteria relating to the suitability of sites proposed for photovoltaic (PV) system deployment are identified. The important issues are defined, briefly discussed and then developed into evaluation criteria. System designers are provided with information on the environmental sensitivity of PV systems in realistic applications, background material which indicates the applicability of the siting issues identified, and evaluation criteria are defined to facilitate the selection of sites that maximize PV system operation.
Item calibration in incomplete testing designs

Directory of Open Access Journals (Sweden)

Norman D. Verhelst

2011-01-01

Full Text Available This study discusses the justifiability of item parameter estimation in incomplete testing designs in item response theory. Marginal maximum likelihood (MML as well as conditional maximum likelihood (CML procedures are considered in three commonly used incomplete designs: random incomplete, multistage testing and targeted testing designs. Mislevy and Sheenan (1989 have shown that in incomplete designs the justifiability of MML can be deduced from Rubin's (1976 general theory on inference in the presence of missing data. Their results are recapitulated and extended for more situations. In this study it is shown that for CML estimation the justification must be established in an alternative way, by considering the neglected part of the complete likelihood. The problems with incomplete designs are not generally recognized in practical situations. This is due to the stochastic nature of the incomplete designs which is not taken into account in standard computer algorithms. For that reason, incorrect uses of standard MML- and CML-algorithms are discussed.
Top-level regulatory criteria for the standard MHTGR

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-10-15

The Licensing Plan for the Standard MHTGR (Ref. 1) describes a program to support a U.S. Nuclear Regulatory Commission (NRC) design review and approval. The Plan calls for the submittal of Top-Level Regulatory Criteria to the NRC for concurrence with their completeness and acceptability for the MHTGR program. The Top-Level Regulatory Criteria are defined as the standards for judging licensability that directly specify acceptable limits for protection of the public health and safety and the environment. The criteria proposed herein are for normal plant operation and a broad spectrum of anticipated events, including accidents. The approach taken is to define a set of criteria which are general as opposed to being design specific. Specifically, it is recommended that criteria be met which: 1. Are less prescriptive than current regulation, thereby encouraging maximum flexibility in design approaches. 2. Are measurable. 3. Are not more strict than the criteria for current power plants.
Preliminary radiation criteria and nuclear analysis for ETF

International Nuclear Information System (INIS)

Engholm, B.A.

1980-09-01

Preliminary biological and materials radiation dose criteria for the Engineering Test Facility are described and tabulated. In keeping with the ETF Mission Statement, a key biological dose criterion is a 24-hour shutdown dose rate of 2 mrem/hr on the surface of the outboard bulk shield. Materials dose criteria, which primarily govern the inboard shield design, include 10 9 rads exposure limit to epoxy insulation, 3 x 10 -4 dpa damage to the TF coil copper stabilizer, and a total nuclear heating rate of 5 kW in the inboard TF coils. Nuclear analysis performed during FY 80 was directed primarily at the inboard and outboard bulk shielding, and at radiation streaming in the neutral beam drift ducts. Inboard and outboard shield thicknesses to achieve the biological and materials radiation criteria are 75 cm inboard and 125 cm outboard, the configuration consisting of alternating layers of stainless steel and borated water. The outboard shield also includes a 5 cm layer of lead. NBI duct streaming analyses performed by ORNL and LASL will play a key role in the design of the duct and NBI shielding in FY 81. The NBI aluminum cryopanel nuclear heating rate during the heating cycle is about 1 milliwatt/cm 3 , which is far less than the permissible limit

Barrier potential design criteria in multiple-quantum-well-based solar-cell structures

Science.gov (United States)

Mohaidat, Jihad M.; Shum, Kai; Wang, W. B.; Alfano, R. R.

1994-01-01

The barrier potential design criteria in multiple-quantum-well (MQW)-based solar-cell structures is reported for the purpose of achieving maximum efficiency. The time-dependent short-circuit current density at the collector side of various MQW solar-cell structures under resonant condition was numerically calculated using the time-dependent Schroedinger equation. The energy efficiency of solar cells based on the InAs/Ga(y)In(1-y)As and GaAs/Al(x)Ga(1-x)As MQW structues were compared when carriers are excited at a particular solar-energy band. Using InAs/Ga(y)In(1-y)As MQW structures it is found that a maximum energy efficiency can be achieved if the structure is designed with barrier potential of about 450 meV. The efficiency is found to decline linearly as the barrier potential increases for GaAs/Al(x)Ga(1-x)As MQW-structure-based solar cells.
Neutron absorber qualification and acceptance testing from the designer's perspective

Energy Technology Data Exchange (ETDEWEB)

Bracey, W. [Transnuclear, Inc, Hawthorne, NY (United States); Chiocca, R. [Cogema Logistics, St. Quentin en Yvelines (France)

2004-07-01

Starting in the mid 1990's, the USNRC began to require less than 100% credit for the 10B present in fixed neutron absorbers spent fuel transport packages. The current practice in the US is to use only 75% of the specified 10B in criticality safety calculations unless extensive acceptance testing demonstrates both the presence of the 10B and uniformity of its distribution. In practice, the NRC has accepted no more than 90% credit for 10B in recent years, while other national competent authorities continue to accept 100%. More recently, with the introduction of new neutron absorber materials, particularly aluminum / boron carbide metal matrix composites, the NRC has also expressed expectations for qualification testing, based in large part on Transnuclear's successful application to use a new composite material in the TN-68 storage / transport cask. The difficulty is that adding more boron than is really necessary to a metal has some negative effects on the material, reducing the ductility and the thermal conductivity, and increasing the cost. Excessive testing requirements can have the undesired effect of keeping superior materials out of spent fuel package designs, without a corresponding justification based on public safety. In European countries and especially in France, 100% credit has been accepted up to now with materials controls specified in the Safety Analysis Report (SAR): Manufacturing process approved by qualification testing Materials manufacturing controlled under a Quality Assurance system. During fabrication, acceptance testing directly on products or on representative samples. Acceptance criteria taking into account a statistical uncertainty corresponding to 3{sigma}. The original and current bases for the reduced {sup 10}B credit, the design requirements for neutron absorber materials, and the experience of Transnuclear and Cogema Logistics with neutron absorber testing are examined. Guidelines for qualification and acceptance testing and
Study on seismic design margin based upon inelastic shaking test of the piping and support system

International Nuclear Information System (INIS)

Ishiguro, Takami; Eto, Kazutoshi; Ikeda, Kazutoyo; Yoshii, Toshiaki; Kondo, Masami; Tai, Koichi

2009-01-01

In Japan, according to the revised Regulatory Guide for Aseismic Design of Nuclear Power Reactor Facilities, September 2006, criteria of design basis earthquakes of Nuclear Power Reactor Facilities become more severe. Then, evaluating seismic design margin took on a great importance and it has been profoundly discussed. Since seismic safety is one of the major key issues of nuclear power plant safety, it has been demonstrated that nuclear piping system possesses large safety margins by various durability test reports for piping in ultimate conditions. Though the knowledge of safety margin has been accumulated from these reports, there still remain some technical uncertainties about the phenomenon when both piping and support structures show inelastic behavior in extremely high seismic excitation level. In order to obtain the influences of inelastic behavior of the support structures to the whole piping system response when both piping and support structures show inelastic behavior, we examined seismic proving tests and we conducted simulation analyses for the piping system which focused on the inelastic behavior of the support to the whole piping system response. This paper introduces major results of the seismic shaking tests of the piping and support system and the simulation analyses of these tests. (author)
Optimal design of constant-stress accelerated degradation tests using the M-optimality criterion

International Nuclear Information System (INIS)

Wang, Han; Zhao, Yu; Ma, Xiaobing; Wang, Hongyu

2017-01-01

In this paper, we propose the M-optimality criterion for designing constant-stress accelerated degradation tests (ADTs). The newly proposed criterion concentrates on the degradation mechanism equivalence rather than evaluation precision or prediction accuracy which is usually considered in traditional optimization criteria. Subject to the constraints of total sample number, test termination time as well as the stress region, an optimum constant-stress ADT plan is derived by determining the combination of stress levels and the number of samples allocated to each stress level, when the degradation path comes from inverse Gaussian (IG) process model with covariates and random effects. A numerical example is presented to verify the robustness of our proposed optimum plan and compare its efficiency with other test plans. Results show that, with a slightly relaxed requirement of evaluation precision and prediction accuracy, our proposed optimum plan reduces the dispersion of the estimated acceleration factor between the usage stress level and a higher accelerated stress level, which makes an important contribution to reliability demonstration and assessment tests. - Highlights: • We establish the necessary conditions for degradation mechanism equivalence of ADTs. • We propose the M-optimality criterion for designing constant-stress ADT plans. • The M-optimality plan reduces the dispersion of the estimated accelerated factors. • An electrical connector with its stress relaxation data is used for illustration.
A3 Subscale Diffuser Test Article Design

Science.gov (United States)

Saunders, G. P.

2009-01-01

This paper gives a detailed description of the design of the A3 Subscale Diffuser Test (SDT) Article Design. The subscale diffuser is a geometrically accurate scale model of the A3 altitude rocket facility. It was designed and built to support the SDT risk mitigation project located at the E3 facility at Stennis Space Center, MS (SSC) supporting the design and construction of the A3 facility at SSC. The subscale test article is outfitted with a large array of instrumentation to support the design verification of the A3 facility. The mechanical design of the subscale diffuser and test instrumentation are described here
NSSS supplier's response to differing safety criteria

Energy Technology Data Exchange (ETDEWEB)

Cremades, J; Filkin, R; Franke, T [Westinghouse Electric Nuclear Energy Systems Europe (WENESE), Brussels (Belgium)

1980-11-01

The limited progress achieved to date in harmonizing national criteria has led to the development of designs which include the most common national requirements. Progress towards harmonization of safety criteria can be accelerated by expanding the IAEA leadership and co-ordination activities, and implementing an integrated approach to criteria development. National and International safety criteria are examined.
Criteria for operator review of workplace changes

International Nuclear Information System (INIS)

Davey, E.

2000-01-01

A set of criteria for reviewing workplace changes has been developed for use by plant Operations staff. The criteria were developed to provide Operations staff with a practical framework for structuring assessments and subsequent review comments with regard to control room modifications and innovations that impact their work environment. The criteria were assembled from design, operations and human factors engineering principles, and system review experiences with plant Operations staff over the past ten years. Operations staff at several CANDU stations helped shape the emphasis for initial criteria definition and have assisted with criteria refinement through trial applications. Use of the criteria is expected to lead to more effective and task relevant equipment evaluations by Operations staff, and ultimately lead to system modifications and innovations that better serve plant operation needs. The paper begins with a discussion of the rationale for criteria development and the attributes of 'good' design. The balance of the paper outlines the project objectives, describes the approach applied in assembling, structuring, and refining the review criteria, and illustrates the application of the criteria in the review of a proposed control room innovation. (author)
Design and Testing of Digital Microfluidic Biochips

CERN Document Server

Zhao, Yang

2013-01-01

This book provides a comprehensive methodology for automated design, test and diagnosis, and use of robust, low-cost, and manufacturable digital microfluidic systems. It focuses on the development of a comprehensive CAD optimization framework for digital microfluidic biochips that unifies different design problems. With the increase in system complexity and integration levels, biochip designers can utilize the design methods described in this book to evaluate different design alternatives, and carry out design-space exploration to obtain the best design point. Describes practical design automation tools that address different design problems (e.g., synthesis, droplet routing, control-pin mapping, testing and diagnosis, and error recovery) in a unified manner; Applies test pattern generation and error-recovery techniques for digital microfluidics-based biochips; Uses real bioassays as evaluation examples, e.g., multiplexed in vitro human physiological fluids diagnostics, PCR, protein crystallization.
Design, Automation, and Test in Europe

DEFF Research Database (Denmark)

Systems in CMOS and Beyond; - Physical Design and Validation; - Test and Verification. The winners of the prestigious EDAA Lifetime Achievement Award as well as oher recognized experts in their field wrote an introduction to each section, summarizing the history in their domain and indicating how......The Design, Automation, and Test in Europe (DATE) conference celebrated in 2007 its tenth anniversary. As a tribute to the chip and system-level design and design technology community, this book presents a compilation of the three most influential papers of each year. This provides an excellent...
Design criteria for XeF{sub 2} enabled deterministic transformation of bulk silicon (100) into flexible silicon layer

Energy Technology Data Exchange (ETDEWEB)

Hussain, Aftab M.; Shaikh, Sohail F.; Hussain, Muhammad M., E-mail: muhammadmustafa.hussain@kaust.edu.sa [Integrated Nanotechnology Laboratory (INL) and Integrated Disruptive Electronics Applications (IDEA) Laboratory, Computer Electrical Mathematical Science and Engineering Division, King Abdullah University of Science and Technology - KAUST, Thuwal 23955-6900 (Saudi Arabia)

2016-07-15

Isotropic etching of bulk silicon (100) using Xenon Difluoride (XeF{sub 2}) gas presents a unique opportunity to undercut and release ultra-thin flexible silicon layers with pre-fabricated state-of-the-art Complementary Metal Oxide Semiconductor (CMOS) electronics. In this work, we present design criteria and mechanism with a comprehensive mathematical model for this method. We consider various trench geometries and parametrize important metrics such as etch time, number of cycles and area efficiency in terms of the trench diameter and spacing so that optimization can be done for specific applications. From our theoretical analysis, we conclude that a honeycomb-inspired hexagonal distribution of trenches can produce the most efficient release of ultra-thin flexible silicon layers in terms of the number of etch cycles, while a rectangular distribution of circular trenches provides the most area efficient design. The theoretical results are verified by fabricating and releasing (varying sizes) flexible silicon layers. We observe uniform translation of design criteria into practice for etch distances and number of etch cycles, using reaction efficiency as a fitting parameter.
Definition of design criteria of mechanical transfer: an interaction between engineering and health areas.

Science.gov (United States)

Luz, Taciana Ramos; Echternacht, Eliza Helena de Oliveira

2012-01-01

This study aims to analyze the factors that justify the low use of a mechanical transfer in the context of a long-term institution. It is a device intended for internal transportation of individuals who have mobility problems. The analysis involves researchers from the fields of health and engineering in order to generate design criteria that consider the needs of caregivers and patients of this institution. To understand the reality of this site and their specificities, was used Ergonomic Work Analysis.
The role of advanced nuclear power technologies in developing countries: Criteria and design requirements

International Nuclear Information System (INIS)

1990-02-01

The document includes the papers presented at the following two technical committee meetings organized by the IAEA: Technical Committee Meeting and Workshop on Criteria for the Introduction of Advanced Nuclear Power Technologies for Specific Applications in Developing Countries, Vienna, 27-30 June 1988 (14 papers) and Technical Committee Meeting and Workshop on Design Requirements for the Application of Advanced Concepts in Developing Countries, Vienna, 6-9 December 1988 (16 papers). A separate abstract was prepared for each of these papers
Review of public comments on proposed seismic design criteria

International Nuclear Information System (INIS)

Philippacopoulos, A.J.; Shaukat, S.K.; Chokshi, N.C.; Bagchi, G.; Nuclear Regulatory Commission, Washington, DC; Nuclear Regulatory Commission, Washington, DC

1989-01-01

During the first quarter of 1988, the Nuclear Regulatory Commission (NRC) prepared a proposed Revision 2 to the NUREG-0800 Standard Review Plan (SRP) Sections 2.5.2 (Vibratory Ground Motion), 3.7.1 (Seismic Design Parameters), 3.7.2 (Seismic Systems Analysis) and 3.7.3 (Seismic Subsystem Analysis). The proposed Revision 2 to the SRP was a result of many years' work carried out by the NRC and the nuclear industry on the Unresolved Safety Issue (USI) A-40: ''Seismic Design Criteria.'' The background material related to NRC's efforts for resolving the A-40 issue is described in NUREG-1233. In June 1988, the proposed Revision 2 of the SRP was issued by NRC for public review and comments. Comments were received from Sargent and Lundy Engineers, Westinghouse Electric Corporation, Stevenson and Associates, Duke Power Company, General Electric Company and Electric Power Research Institute. In September 1988, Brookhaven National Laboratory (BNL) and its consultants (C.J. Costantino, R.P. Kennedy, J. Stevenson, M. Shinozuka and A.S. Veletsos) were requested to carry out a review of the comments received from the above six organizations. The objective of this review was to assist the NRC staff with the evaluation and resolution of the public comments. This review was initiated during October 1988 and it was completed on January 1989. As a result of this review, a set of modifications to the above mentioned sections of the SRP were recommended by BNL and its consultants. This paper summarizes the recommended modifications. 4 refs
Basic considerations for the preparation of performance testing materials as related to performance evaluation acceptance criteria

International Nuclear Information System (INIS)

McCurdy, D.E.; Morton, J.S.

2001-01-01

The preparation of performance testing (PT) materials for environmental and radiobioassay applications involves the use of natural matrix materials containing the analyte of interest, the addition (spiking) of the analyte to a desired matrix (followed by blending for certain matrices) or a combination of the two. The distribution of the sample analyte concentration in a batch of PT samples will reflect the degree of heterogeneity of the analyte in the PT material and/or the reproducibility of the sample preparation process. Commercial and government implemented radioanalytical performance evaluation programs have a variety of acceptable performance criteria. The performance criteria should take into consideration many parameters related to the preparation of the PT materials including the within and between sample analyte heterogeneity, the accuracy of the quantification of an analyte in the PT material and to what 'known' value will a laboratory's result be compared. How sample preparation parameters affect the successful participation in performance evaluation (PE) programs having an acceptance criteria established as a percent difference from a 'known' value or in PE programs using other acceptance criteria, such as the guidance provided in ANSI N42.22 and N13.30 is discussed. (author)
Time-Dependent Deformation Modelling for a Chopped-Glass Fiber Composite for Automotive Durability Design Criteria

Energy Technology Data Exchange (ETDEWEB)

Ren, W

2001-08-24

Time-dependent deformation behavior of a polymeric composite with chopped-glass-fiber reinforcement was investigated for automotive applications, The material under stress was exposed to representative automobile service environments. Results show that environment has substantial effects on time-dependent deformation behavior of the material. The data were analyzed and experimentally-based models developed for the time-dependent deformation behavior as a basis for automotive structural durability design criteria.
An analysis of the qualification criteria for small radioactive material shipping packages

International Nuclear Information System (INIS)

McClure, J.D.

1983-05-01

The RAM package design certification process has two important elements, testing and acceptance. These terms sound very similar but they have specific meanings. Qualification testing in the context of this study is the imposition of simulated accident test conditions upon the candidate package design. (Normal transportation environments may also be included.) Following qualification testing, the acceptance criteria provide the performance levels which, if demonstrated, indicate the ability of the RAM package to sustain the severity of the qualification testing sequence and yet maintain specified levels of package integrity. This study has used Severities of Transportation Accidents as a data base to examine the regulatory test criteria which are required to be met by small packages containing Type B quantities of radioactive material (RAM). The basic findings indicate that the present regulatory test standards provide significantly higher levels of protection for the surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It should also be noted that various risk assessment studies have shown that the risk to the public due to severe transport accidents by surface and air transport modes is very low. A key element in this study was the quantification of the severity of the transportation accident environment and the severity of the present qualification test standards (called qualification test standards in this document) so that a direct comparison could be made between them to assess the effectiveness of the existing qualification test standards. The manner in which this was accomplished is described
An analysis of the qualification criteria for small radioactive material shipping packages

Energy Technology Data Exchange (ETDEWEB)

McClure, J.D.

1983-05-01

The RAM package design certification process has two important elements, testing and acceptance. These terms sound very similar but they have specific meanings. Qualification testing in the context of this study is the imposition of simulated accident test conditions upon the candidate package design. (Normal transportation environments may also be included.) Following qualification testing, the acceptance criteria provide the performance levels which, if demonstrated, indicate the ability of the RAM package to sustain the severity of the qualification testing sequence and yet maintain specified levels of package integrity. This study has used Severities of Transportation Accidents as a data base to examine the regulatory test criteria which are required to be met by small packages containing Type B quantities of radioactive material (RAM). The basic findings indicate that the present regulatory test standards provide significantly higher levels of protection for the surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It should also be noted that various risk assessment studies have shown that the risk to the public due to severe transport accidents by surface and air transport modes is very low. A key element in this study was the quantification of the severity of the transportation accident environment and the severity of the present qualification test standards (called qualification test standards in this document) so that a direct comparison could be made between them to assess the effectiveness of the existing qualification test standards. The manner in which this was accomplished is described.
Design and validation of standardized clinical and functional remission criteria in schizophrenia

Science.gov (United States)

Mosolov, Sergey N; Potapov, Andrey V; Ushakov, Uriy V; Shafarenko, Aleksey A; Kostyukova, Anastasiya B

2014-01-01

Background International Remission Criteria (IRC) for schizophrenia were developed recently by a group of internationally known experts. The IRC detect only 10%–30% of cases and do not cover the diversity of forms and social functioning. Our aim was to design a more applicable tool and validate its use – the Standardized Clinical and Functional Remission Criteria (SCFRC). Methods We used a 6-month follow-up study of 203 outpatients from two Moscow centers and another further sample of stable patients from a 1-year controlled trial of atypical versus typical medication. Diagnosis was confirmed by International Classification of Diseases Version 10 (ICD10) criteria and the Mini-International Neuropsychiatric Interview (MINI). Patients were assessed by the Positive and Negative Syndrome Scale, including intensity threshold, and further classified using the Russian domestic remission criteria and the level of social and personal functioning, according to the Personal and Social Performance Scale (PSP). The SCFRC were formulated and were validated by a data reanalysis on the first population sample and on a second independent sample (104 patients) and in an open-label prospective randomized 12-month comparative study of risperidone long-acting injectable (RLAI) versus olanzapine. Results Only 64 of the 203 outpatients (31.5%) initially met the IRC, and 53 patients (26.1%) met the IRC after 6 months, without a change in treatment. Patients who were in remission had episodic and progressive deficit (39.6%), or remittent (15%) paranoid schizophrenia, or schizoaffective disorder (17%). In addition, 105 patients of 139 (51.7%), who did not meet symptomatic IRC, remained stable within the period. Reanalysis of data revealed that 65.5% of the patients met the SCFRC. In the controlled trial, 70% of patients in the RLAI group met the SCFRC and only 19% the IRC. In the routine treatment group, 55.9% met the SCFRC and only 5.7% the IRC. Results of the further independent
MITG post-test analysis and design improvements

International Nuclear Information System (INIS)

Schock, A.

1983-01-01

The design, performance analysis, and key attributes of the Modular Isotopic Thermoelectric Generator (MITG) were described in a 1981 IECEC paper; and the design, fabrication, and testing of prototypical MITG test assemblies were described in preceding papers in these proceedings. Each test assembly simulated a typical modular slice of the flight generator. The present paper describes a detailed thermal-stress analysis, which identified the causes of stress-related problems observed during the tests. It then describes how additional analyses were used to evaluate design changes to alleviate those problems. Additional design improvements are discussed in the next paper in these proceedings, which also describes revised fabrication procedures and updated performance estimates for the generator
Design and validation of standardized clinical and functional remission criteria in schizophrenia

Directory of Open Access Journals (Sweden)

Mosolov SN

2014-01-01

Full Text Available Sergey N Mosolov,1 Andrey V Potapov,1 Uriy V Ushakov,2 Aleksey A Shafarenko,1 Anastasiya B Kostyukova11Department of Mental Disorders Therapy, Moscow Research Institute of Psychiatry, Moscow, Russia; 2Moscow Psychiatric Outpatient Services #21, Moscow, RussiaBackground: International Remission Criteria (IRC for schizophrenia were developed recently by a group of internationally known experts. The IRC detect only 10%–30% of cases and do not cover the diversity of forms and social functioning. Our aim was to design a more applicable tool and validate its use – the Standardized Clinical and Functional Remission Criteria (SCFRC.Methods: We used a 6-month follow-up study of 203 outpatients from two Moscow centers and another further sample of stable patients from a 1-year controlled trial of atypical versus typical medication. Diagnosis was confirmed by International Classification of Diseases Version 10 (ICD10 criteria and the Mini-International Neuropsychiatric Interview (MINI. Patients were assessed by the Positive and Negative Syndrome Scale, including intensity threshold, and further classified using the Russian domestic remission criteria and the level of social and personal functioning, according to the Personal and Social Performance Scale (PSP. The SCFRC were formulated and were validated by a data reanalysis on the first population sample and on a second independent sample (104 patients and in an open-label prospective randomized 12-month comparative study of risperidone long-acting injectable (RLAI versus olanzapine.Results: Only 64 of the 203 outpatients (31.5% initially met the IRC, and 53 patients (26.1% met the IRC after 6 months, without a change in treatment. Patients who were in remission had episodic and progressive deficit (39.6%, or remittent (15% paranoid schizophrenia, or schizoaffective disorder (17%. In addition, 105 patients of 139 (51.7%, who did not meet symptomatic IRC, remained stable within the period. Reanalysis of

JSFR design progress related to development of safety design criteria for Generation IV sodium-cooled fast reactors. (1) Overview

International Nuclear Information System (INIS)

Kamide, Hideki; Ando, Masato; Ito, Takaya

2015-01-01

JAEA, JAPC and MFBR have been conducting design study for the Japan Sodium-cooled Fast Reactor (JSFR), which is a design concept aiming at future commercial use as sustainable electric power source. As the result of the design study and R and D activity related the innovative technologies incorporated in the design in the Fast Reactor Cycle Technology Development (FaCT) project up to 2010, basic design concept of JSFR was established and its development process to the commercialization including construction and operation of a demonstration version of JSFR was outlined. JSFR is a looptype next generation sodium-cooled fast reactor (SFR), which is aiming at achieving development targets of Generation IV reactors concerning sustainability, safety and reliability, economics and proliferation resistance and physical protection by introducing the innovative technologies such as shortened high-chromium steel piping. The output power is assumed for the design study as 1,500 MWe for the commercial version and 750 MWe for the demonstration version. In FaCT phase I up to 2010, in order to evaluate feasibility to achieve the development targets, the design study has been conducted on the main components and systems. Since 2011, in order to contribute to the development of safety design criteria (SDC) and safety design guideline (SDG), which include the lessons learned from the TEPCO's Fukushima Dai-ichi nuclear power plants accident, in the frame work of Generation IV International Forum (GIF), the design study is focusing on the design measures against severe external events such as earthquake and tsunami. At the same time, the design study is going into detail and paying much attention to the maintenance and repair to make surer its feasibility. This paper summarizes the design concept of the demonstration version of JSFR in which progress of design work was incorporated for the safety issues on SDC and SDG of a SFR. (author)
NET test blanket design and remote maintenance

International Nuclear Information System (INIS)

Holloway, C.; Hubert, P.

1991-01-01

The NET machine has three horizontal ports reserved for testing tritium breeding blanket designs during the physics phase and possibly five during the technology phase. The design of the ports and test blankets are modular to accept a range of blanket options, provide radiation shielding and allow routine replacement. Radiation levels during replacement or maintenance require that all operations must be carried out remotely. The paper describes the problems overcome in providing a port design which includes attachment to the vacuum vessel with double vacuum seals, an integrated cooled first wall and support guides for the test blanket module. The method selected to remotely replace the test module whilst controlling the spread of contamination is also adressed. The paper concludes that the provisions of a test blanket facility based on the NET machine design is feasible. (orig.)
Development of small reactor safety criteria in Canada

International Nuclear Information System (INIS)

Ernst, P.C.; French, P.M.; Axford, D.J.; Snell, V.G.

1990-01-01

A number of new small reactor designs have been proposed in Canada over the last several years and some have reached the stage where licensing discussions have been initiated with the Atomic Energy Control Board (AECB). An inter-organizational Small Reactor Criteria (SRC) working group was formed in 1988 to propose safety and licensing criteria for these small reactors. Two levels of criteria are proposed. The first level forms a safety philosophy and the second is a set of criteria for specific reactor applications. The safety philosophy consists of three basic safety objectives together with evaluation criteria, and fourteen fundamental principles measured by specific criteria, which must be implemented to meet the safety objectives. Two of the fourteen principles are prime: defence in depth, and safety culture; the other twelve principles can be seen as deriving from them. A benefit of this approach is that the concepts of defence in depth and safety culture become well-defined. The objectives and principles are presented in the paper and their criteria are summarized. The second level of criteria, under development, will form a safety application set and will provide small reactor criteria in a number of general areas, such as regulatory process and safety assessment, as well as for specific reactor life-cycle activities, from siting through to decommissioning. The criteria are largely deterministic. However, the frequencies and consequences of postulated accidents are assessed against numerical criteria to assist in judging the acceptability of plant design, operation, and proposed siting. All criteria proposed are designed to be testable in some evidentiary fashion, readily enabling an assessment of compliance for a given proposal
Displacement Based Seismic Design Criteria

International Nuclear Information System (INIS)

Costello, J.F.; Hofmayer, C.; Park, Y.J.

1999-01-01

The USNRC has initiated a project to determine if any of the likely revisions to traditional earthquake engineering practice are relevant to seismic design of the specialized structures, systems and components of nuclear power plants and of such significance to suggest that a change in design practice might be warranted. As part of the initial phase of this study, a literature survey was conducted on the recent changes in seismic design codes/standards, on-going activities of code-writing organizations/communities, and published documents on displacement-based design methods. This paper provides a summary of recent changes in building codes and on-going activities for future codes. It also discusses some technical issues for further consideration
Most Scottish neurologists do not apply the 2010 McDonald criteria when diagnosing multiple sclerosis.

Science.gov (United States)

Lumley, R; Davenport, R; Williams, A

2015-03-01

The diagnostic criteria for multiple sclerosis have evolved over time and currently the 2010 McDonald criteria are the most widely accepted. These criteria allow the diagnosis of multiple sclerosis to be made at the clinically isolated syndrome stage provided certain criteria are met on a single magnetic resonance brain scan. Our hypothesis was that neurologists in Scotland did not use these criteria routinely. We sent a SurveyMonkey questionnaire to all Scottish neurologists (consultants and trainees) regarding the diagnosis of multiple sclerosis. Our questionnaire response rate was 65/99 (66%). Most Scottish neurologists were aware of the criteria and 31/58 (53%) felt that they were using these routinely. However, in a clinical vignette designed to test the application of these criteria, only 5/57 (9%) of neurologists appeared to use them. Scottish neurologists' use of the 2010 McDonald criteria for diagnosis of multiple sclerosis varies from practitioners' perception of their use of these criteria.
Testing the quality of images for permanent magnet desktop MRI systems using specially designed phantoms.

Science.gov (United States)

Qiu, Jianfeng; Wang, Guozhu; Min, Jiao; Wang, Xiaoyan; Wang, Pengcheng

2013-12-21

Our aim was to measure the performance of desktop magnetic resonance imaging (MRI) systems using specially designed phantoms, by testing imaging parameters and analysing the imaging quality. We designed multifunction phantoms with diameters of 18 and 60 mm for desktop MRI scanners in accordance with the American Association of Physicists in Medicine (AAPM) report no. 28. We scanned the phantoms with three permanent magnet 0.5 T desktop MRI systems, measured the MRI image parameters, and analysed imaging quality by comparing the data with the AAPM criteria and Chinese national standards. Image parameters included: resonance frequency, high contrast spatial resolution, low contrast object detectability, slice thickness, geometrical distortion, signal-to-noise ratio (SNR), and image uniformity. The image parameters of three desktop MRI machines could be measured using our specially designed phantoms, and most parameters were in line with MRI quality control criterion, including: resonance frequency, high contrast spatial resolution, low contrast object detectability, slice thickness, geometrical distortion, image uniformity and slice position accuracy. However, SNR was significantly lower than in some references. The imaging test and quality control are necessary for desktop MRI systems, and should be performed with the applicable phantom and corresponding standards.
Testing the quality of images for permanent magnet desktop MRI systems using specially designed phantoms

International Nuclear Information System (INIS)

Qiu, Jianfeng; Wang, Guozhu; Min, Jiao; Wang, Xiaoyan; Wang, Pengcheng

2013-01-01

Our aim was to measure the performance of desktop magnetic resonance imaging (MRI) systems using specially designed phantoms, by testing imaging parameters and analysing the imaging quality. We designed multifunction phantoms with diameters of 18 and 60 mm for desktop MRI scanners in accordance with the American Association of Physicists in Medicine (AAPM) report no. 28. We scanned the phantoms with three permanent magnet 0.5 T desktop MRI systems, measured the MRI image parameters, and analysed imaging quality by comparing the data with the AAPM criteria and Chinese national standards. Image parameters included: resonance frequency, high contrast spatial resolution, low contrast object detectability, slice thickness, geometrical distortion, signal-to-noise ratio (SNR), and image uniformity. The image parameters of three desktop MRI machines could be measured using our specially designed phantoms, and most parameters were in line with MRI quality control criterion, including: resonance frequency, high contrast spatial resolution, low contrast object detectability, slice thickness, geometrical distortion, image uniformity and slice position accuracy. However, SNR was significantly lower than in some references. The imaging test and quality control are necessary for desktop MRI systems, and should be performed with the applicable phantom and corresponding standards. (paper)
Fracture criteria of reactor graphite under multiaxial stresses

International Nuclear Information System (INIS)

Sato, S.; Kawamata, K.; Kurumada, A.; Oku, T.

1987-01-01

New fracture criteria for graphite under multiaxial stresses are presented for designing core and support materials of a high temperature gas cooled reactor. Different kinds of fracture strength tests are carried out for a near isotropic graphite IG-11. Results show that, under the stress state in which tensile stresses are predominant, the maximum principal stress theory is seen as applicable for brittle fracture. Under the stress state in which compressive stresses are predominant there may be two fracture modes for brittle fracture, namely, slipping fracture and mode II fracture. For the former fracture mode the maximum shear stress criterion is suitable, but for the latter fracture mode a new mode II fracture criterion including a restraint effect for cracks is verified to be applicable. Also a statistical correction for brittle fracture criteria under multiaxial stresses is discussed. By considering the allowable stress values for safe design, the specified minimum ultimate strengths corresponding to a survival probability of 99% at the 95% confidence level are presented. (orig./HP)
Design of viewing windows for controlled-atmosphere chambers

International Nuclear Information System (INIS)

Robinson, J.N.

1980-03-01

A guide to the design of safe viewing windows is presented. Design criteria, the properties of materials, the problems of structural design in unreliable materials such as glass, the mathematics of reliability and redundance, and problems associated with testing windows are discussed, and formulas are presented for the design of windows. Criteria adopted at ORNL for controlled-atmosphere chambers are presented, a program for surveying and upgrading the safety of existing facilities is described, and the results of this program are reported
Parametric Study on Ultimate Failure Criteria of Elbow Piping Components in Seismically Isolated NPP

Energy Technology Data Exchange (ETDEWEB)

Hahm, Dae Gi; Ki, Min Kyu [KAERI, Daejeon (Korea, Republic of); Jeon, Bub Gyu; Kim, Nam Sik [Pusan National University, Busan (Korea, Republic of)

2016-05-15

It is well known that the interface pipes between isolated and non-isolated structures will become the most critical in the seismically isolated NPPs. Therefore, seismic performance of such interface pipes should be evaluated comprehensively especially in terms of the seismic fragility capacity. To evaluate the seismic capacity of interface pipes in the isolated NPP, firstly, we should define the failure mode and failure criteria of critical pipe components. Hence, in this study, we performed the dynamic tests of elbow components which were installed in a seismically isolated NPP, and evaluated the ultimate failure mode and failure criteria by using the test results. To do this, we manufactured 25 critical elbow component specimens and performed cyclic loading tests under the internal pressure condition. The failure mode and failure criteria of a pipe component will be varied by the design parameters such as the internal pressure, pipe diameter, loading type, and loading amplitude. From the tests, we assessed the effects of the variation parameters onto the failure criteria. For the tests, we generated the seismic input protocol of relative displacement between the ends of elbow component. In this paper, elbow in piping system was defined as a fragile element and numerical model was updated by component test. Failure mode of piping component under seismic load was defined by the dynamic tests of ultimate pipe capacity. For the interface piping system, the seismic capacity should be carefully estimated since that the required displacement absorption capacity will be increased significantly by the adoption of the seismic isolation system. In this study, the dynamic tests were performed for the elbow components which were installed in an actual NPPs, and the ultimate failure mode and failure criteria were also evaluated by using the test results.
BRCA1 and BRCA2 mutational profile and prevalence in hereditary breast and ovarian cancer (HBOC probands from Southern Brazil: Are international testing criteria appropriate for this specific population?

Directory of Open Access Journals (Sweden)

Bárbara Alemar

Full Text Available Germline pathogenic variants in BRCA1 and BRCA2 (BRCA are the main cause of Hereditary Breast and Ovarian Cancer syndrome (HBOC.In this study we evaluated the mutational profile and prevalence of BRCA pathogenic/likely pathogenic variants among probands fulfilling the NCCN HBOC testing criteria. We characterized the clinical profile of these individuals and explored the performance of international testing criteria.A pathogenic/likely pathogenic variant was detected in 19.1% of 418 probands, including seven novel frameshift variants. Variants of uncertain significance were found in 5.7% of individuals. We evaluated 50 testing criteria and mutation probability algorithms. There was a significant odds-ratio (OR for mutation prediction (p ≤ 0.05 for 25 criteria; 14 of these had p ≤ 0.001. Using a cutoff point of four criteria, the sensitivity is 83.8%, and the specificity is 53.5% for being a carrier. The prevalence of pathogenic/likely pathogenic variants for each criterion ranged from 22.1% to 55.6%, and criteria with the highest ORs were those related to triple-negative breast cancer or ovarian cancer.This is the largest study of comprehensive BRCA testing among Brazilians to date, and the first to analyze clinical criteria for genetic testing. Several criteria that are not included in the NCCN achieved a higher predictive value. Identification of the most informative criteria for each population will assist in the development of a rational approach to genetic testing, and will enable the prioritization of high-risk individuals as a first step towards offering testing in low-income countries.
Investigation of the utility of colorectal function tests and Rome II criteria in dyssynergic defecation (Anismus).

Science.gov (United States)

Rao, S S C; Mudipalli, R S; Stessman, M; Zimmerman, B

2004-10-01

Although 30-50% of constipated patients exhibit dyssynergia, an optimal method of diagnosis is unclear. Recently, consensus criteria have been proposed but their utility is unknown. To examine the diagnostic yield of colorectal tests, reproducibility of manometry and utility of Rome II criteria. A total of 100 patients with difficult defecation were prospectively evaluated with anorectal manometry, balloon expulsion, colonic transit and defecography. Fifty-three patients had repeat manometry. During attempted defecation, 30 showed normal and 70 one of three abnormal manometric patterns. Forty-six patients fulfilled Rome criteria and showed paradoxical anal contraction (type I) or impaired anal relaxation (type III) with adequate propulsion. However, 24 (34%) showed impaired propulsion (type II). Forty-five (64%) had slow transit, 42 (60%) impaired balloon expulsion and 26 (37%) abnormal defecography. Defecography provided no additional discriminant utility. Evidence of dyssynergia was reproducible in 51 of 53 patients. Symptoms alone could not differentiate dyssynergic subtypes or patients. Dyssynergic patients exhibited three patterns that were reproducible: paradoxical contraction, impaired propulsion and impaired relaxation. Although useful, Rome II criteria may be insufficient to identify or subclassify dyssynergic defecation. Symptoms together with abnormal manometry, abnormal balloon expulsion or colonic marker retention are necessary to optimally identify patients with difficult defecation.
Overview of the IFMIF test cell design

International Nuclear Information System (INIS)

Moeslang, A.; Daum, E.; Jitsukawa, S.; Noda, K.; Viola, R.

1996-01-01

The Conceptual Design Activity (CDA) for the International Fusion Materials Irradiation Facility (IFMIF) has entered its second and final year, and an outline design has been developed. Initial evaluations of the potential of this high flux, high intensity D-Li source have shown that the main materials testing needs can be fulfilled. According to these needs, Vertical Test Assemblies will accommodate test modules for the high flux (0.5 liter, 20 dpa/a, 250-1000 C), the medium flux (6 liter, 1-20 dpa/a, 250-1000 C), the low flux (7.5 liter, 0.1-1 dpa/a), and the very low flux (> 100 liter, 0.01-0.1 dpa/a) regions. Detailed test matrices have been defined for the high and medium flux regions, showing that on the basis of small specimen test technologies, a database for an engineering design of an advanced fusion reactor (DEMO) can be established for a variety of structural materials and ceramic breeders. The design concepts for the Test Cell, including test assemblies, remote handling equipment and Hot Cell Facilities with capacity for investigating all irradiation specimens at the IFMIF site are described
Evolving fuzzy rules for relaxed-criteria negotiation.

Science.gov (United States)

Sim, Kwang Mong

2008-12-01

In the literature on automated negotiation, very few negotiation agents are designed with the flexibility to slightly relax their negotiation criteria to reach a consensus more rapidly and with more certainty. Furthermore, these relaxed-criteria negotiation agents were not equipped with the ability to enhance their performance by learning and evolving their relaxed-criteria negotiation rules. The impetus of this work is designing market-driven negotiation agents (MDAs) that not only have the flexibility of relaxing bargaining criteria using fuzzy rules, but can also evolve their structures by learning new relaxed-criteria fuzzy rules to improve their negotiation outcomes as they participate in negotiations in more e-markets. To this end, an evolutionary algorithm for adapting and evolving relaxed-criteria fuzzy rules was developed. Implementing the idea in a testbed, two kinds of experiments for evaluating and comparing EvEMDAs (MDAs with relaxed-criteria rules that are evolved using the evolutionary algorithm) and EMDAs (MDAs with relaxed-criteria rules that are manually constructed) were carried out through stochastic simulations. Empirical results show that: 1) EvEMDAs generally outperformed EMDAs in different types of e-markets and 2) the negotiation outcomes of EvEMDAs generally improved as they negotiated in more e-markets.
Criteria for maintenance and repair - LMFBR steam generators

International Nuclear Information System (INIS)

Essebaggers, J.

1975-01-01

The maintenance and repair criteria will be reviewed with respect to the designs presently under construction for the SNR-300 plant. This criteria shall be based upon the philosophy that safety and reliability are of the highest importance at all operating modes, while availability shall be maximized. To maximize the safety of the steam generator, measures have been taken to reduce the possibilities of failure by simplicity in design, choice of material, methods of fabrication and high quality assurance of critical parts of the pressure boundaries. The maintenance and repair program shall meet the same criteria or the intent of these criteria as applied for the original product. (author)
Engine testing the design, building, modification and use of powertrain test facilities

CERN Document Server

MARTYR, A J

2012-01-01

Engine Testing is a unique, well-organized and comprehensive collection of the different aspects of engine and vehicle testing equipment and infrastructure for anyone involved in facility design and management, physical testing and the maintenance, upgrading and trouble shooting of testing equipment. Designed so that its chapters can all stand alone to be read in sequence or out of order as needed, Engine Testing is also an ideal resource for automotive engineers required to perform testing functions whose jobs do not involve engine testing on a regular basis. This recognized standard refer
Design of clinical trials involving multiple hypothesis tests with a common control.

Science.gov (United States)

Schou, I Manjula; Marschner, Ian C

2017-07-01

Randomized clinical trials comparing several treatments to a common control are often reported in the medical literature. For example, multiple experimental treatments may be compared with placebo, or in combination therapy trials, a combination therapy may be compared with each of its constituent monotherapies. Such trials are typically designed using a balanced approach in which equal numbers of individuals are randomized to each arm, however, this can result in an inefficient use of resources. We provide a unified framework and new theoretical results for optimal design of such single-control multiple-comparator studies. We consider variance optimal designs based on D-, A-, and E-optimality criteria, using a general model that allows for heteroscedasticity and a range of effect measures that include both continuous and binary outcomes. We demonstrate the sensitivity of these designs to the type of optimality criterion by showing that the optimal allocation ratios are systematically ordered according to the optimality criterion. Given this sensitivity to the optimality criterion, we argue that power optimality is a more suitable approach when designing clinical trials where testing is the objective. Weighted variance optimal designs are also discussed, which, like power optimal designs, allow the treatment difference to play a major role in determining allocation ratios. We illustrate our methods using two real clinical trial examples taken from the medical literature. Some recommendations on the use of optimal designs in single-control multiple-comparator trials are also provided. © 2016 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.
A NSSS supplier's response to differing safety criteria

International Nuclear Information System (INIS)

Cremades, J.; Filkin, R.; Franke, Th.

1980-01-01

The limited progress achieved to date in harmonizing national criteria has led to the development of designs which include the most common national requirements. Progress towards harmonization of safety criteria can be accelerated by expanding the IAEA leadership and co-ordination activities, and implementing an integrated approach to criteria development. National and International safety criteria are examined. (author)
Mechanical testing - designers need: a view at component design and operations stages

International Nuclear Information System (INIS)

Shrivastava, S.K.

2007-01-01

Mechanical design of any component requires knowledge of values of various material properties which designer(s) make(s) use in designing the component. In design of nuclear power plant components, it assumes even greater importance in view of degree of precision and accuracy with which the values of various properties are required. This is in turn demands, high accuracy in testing machines and measuring methods. In this paper, attempt has been made to bring out that even from conventional tension test, how designer today looks for availability of engineering stress-strain diagram preferably through digitally acquired data points during the test from which he can derive values of Ramberg-Osgood parameters for use in fracture mechanics based analysis. Attempt has been also made to provide account of some of important fracture mechanics related tests which have been evolved in last two decades and designers need for evolution of simple test techniques to measure many more fracture mechanics related parameters as well as cater to constraints such as shape and size of material available from the components. Nuclear power plant has been primarily kept in view and ASME. Section III NB, ASME Section XI and relevant ASTM Standards have been taken as standard references. Further pressure retaining materials of pressure vessels/Reactor Pressure Vessels have been kept in view. (author)
Climate-conscious architecture. Design and wind testing method for climates in change

Energy Technology Data Exchange (ETDEWEB)

Kuismanen, K.

2008-07-01

The main objective of this research was to develop practical tools with which it is possible to improve the environment, micro-climate and energy economy of buildings and plans in different climate zones, and take the climate change into account. The parts of the study are: State of art study into existing know-how about climate and planning. Study of the effects of climate change on the built environment. Development of simple micro-climate, nature and built environment analysis methods. Defining the criteria of an acceptable micro-climatic environment. Development of the wind test blower. Presenting ways to interpret test results and draw conclusions. Development of planning and design guidelines for different climate zones. An important part of the research is the development of the CASE wind test instrument, different wind simulation techniques, and the methods of observing the results. Bioclimatic planning and architectural design guidelines for different climate zones are produced. The analyse tools developed give a qualitative overall view, which can be deepened towards a quantitative analyse with wind testing measurements and roughness calculations. No mechanical rules are suggested, but complementary viewpoints and practices introduced to a normal planning process as well as improvement of consultative knowledge. The 'method' is that there is no strict mechanical method, but a deeper understanding of bioclimatic matters. Climate-conscious planning with the developed CASE method, make it possible to design a better micro-climate for new or old built-up areas. Winds can be used in to ventilate exhaust fumes and other pollutants, which improves the quality of air and the healthiness of the urban environment. The analyses and scale-model tests make it possible to shield cold windy areas and to diminish the cooling effect of wind on facades. According to studies in Scandinavian countries this will bring energy savings of 5-15 per cent. The method can

Multiobjective optimal design of runner blade using efficiency and draft tube pulsation criteria

International Nuclear Information System (INIS)

Pilev, I M; Sotnikov, A A; Rigin, V E; Semenova, A V; Cherny, S G; Chirkov, D V; Bannikov, D V; Skorospelov, V A

2012-01-01

In the present work new criteria of optimal design method for turbine runner [1] are proposed. Firstly, based on the efficient method which couples direct simulation of 3D turbulent flow and engineering semi empirical formulas, the combined method is built for hydraulic energy losses estimation in the whole turbine water passage and the efficiency criterion is formulated. Secondly, the criterion of dynamic loads minimization is developed for those caused by vortex rope precession downstream of the runner. This criterion is based on the finding that the monotonic increase of meridional velocity component in the direction to runner hub, downstream of its blades, provides for decreasing the intensity of vortex rope and thereafter, minimization of pressure pulsation amplitude. The developed algorithm was applied to optimal design of 640 MW Francis turbine runner. It can ensure high efficiency at best efficiency operating point as well as diminished pressure pulsations at full load regime.
Water NSTF Design, Instrumentation, and Test Planning

Energy Technology Data Exchange (ETDEWEB)

Lisowski, Darius D.; Gerardi, Craig D.; Hu, Rui; Kilsdonk, Dennis J.; Bremer, Nathan C.; Lomperski, Stephen W.; Kraus, Adam R.; Bucknor, Matthew D.; Lv, Qiuping; Farmer, Mitchell T.

2017-08-01

The following report serves as a formal introduction to the water-based Natural convection Shutdown heat removal Test Facility (NSTF) program at Argonne. Since 2005, this US Department of Energy (DOE) sponsored program has conducted large scale experimental testing to generate high-quality and traceable validation data for guiding design decisions of the Reactor Cavity Cooling System (RCCS) concept for advanced reactor designs. The most recent facility iteration, and focus of this report, is the operation of a 1/2 scale model of a water-RCCS concept. Several features of the NSTF prototype align with the conceptual design that has been publicly released for the AREVA 625 MWt SC-HTGR. The design of the NSTF also retains all aspects common to a fundamental boiling water thermosiphon, and thus is well poised to provide necessary experimental data to advance basic understanding of natural circulation phenomena and contribute to computer code validation. Overall, the NSTF program operates to support the DOE vision of aiding US vendors in design choices of future reactor concepts, advancing the maturity of codes for licensing, and ultimately developing safe and reliable reactor technologies. In this report, the top-level program objectives, testing requirements, and unique considerations for the water cooled test assembly are discussed, and presented in sufficient depth to support defining the program’s overall scope and purpose. A discussion of the proposed 6-year testing program is then introduced, which outlines the specific strategy and testing plan for facility operations. The proposed testing plan has been developed to meet the toplevel objective of conducting high-quality test operations that span across a broad range of single- and two-phase operating conditions. Details of characterization, baseline test cases, accident scenario, and parametric variations are provided, including discussions of later-stage test cases that examine the influence of geometric
On the hydrostatic test for nuclear vessels

International Nuclear Information System (INIS)

Palmero, A.

1979-01-01

A comparison of the pressure test requirements, namely specified values of pressure and temperature, for nuclear vessels designed and constructed according to the ASME Code and Spanish Rules is presented. Also the relationship of the design criteria and the pressure test requirements is indicated with a particular emphasis on the test temperature in order to avoid brittle behaviour of the materials. (author)
Design parameters and testing techniques for criticality accident detection systems used in various nuclear establishments - a review

International Nuclear Information System (INIS)

Janardhanan, S.; Krishnamony, S.; Krishnamurthi, T.N.; Gopalan, C.S.

1981-01-01

Accidental criticality excursion is a potential hazard in operations involving fissile material. In this review paper, design criteria for criticality detection systems, associated requirements for reliable functioning of the instrument and recent advances in the field are discussed. Systems based on integrated dose and rate of change of dose rate concepts are explained. A criticality accident simulator using a pneumatically driven 60 Co source for testing the detector is described. The paper also discusses the relative advantages of gamma and neutron sensing devices. (author)
Design parameters and testing techniques for criticality accident detection systems used in various nuclear establishments - a review

Energy Technology Data Exchange (ETDEWEB)

Janardhanan, S.; Krishnamony, S.; Krishnamurthi, T.N.; Gopalan, C.S. (Bhabha Atomic Research Centre, Bombay (India). Health Physics Div.)

Accidental criticality excursion is a potential hazard in operations involving fissile material. In this review paper, design criteria for criticality detection systems, associated requirements for reliable functioning of the instrument and recent advances in the field are discussed. Systems based on integrated dose and rate of change of dose rate concepts are explained. A criticality accident simulator using a pneumatically driven /sup 60/Co source for testing the detector is described. The paper also discusses the relative advantages of gamma and neutron sensing devices.
Education Criteria for Performance Excellence, 2002.

Science.gov (United States)

National Inst. of Standards and Technology, Gaithersburg, MD.

The education criteria presented in this guide are designed to help organizations use an integrated approach to organizational performance management that results in delivery of ever-improving value to students and stakeholders. Implementation of the criteria will contribute to improvement of education quality, improvement of overall…
Hybrid Computerized Adaptive Testing: From Group Sequential Design to Fully Sequential Design

Science.gov (United States)

Wang, Shiyu; Lin, Haiyan; Chang, Hua-Hua; Douglas, Jeff

2016-01-01

Computerized adaptive testing (CAT) and multistage testing (MST) have become two of the most popular modes in large-scale computer-based sequential testing. Though most designs of CAT and MST exhibit strength and weakness in recent large-scale implementations, there is no simple answer to the question of which design is better because different…
Prototype spent-fuel canister design, analysis, and test

International Nuclear Information System (INIS)

Leisher, W.B.; Eakes, R.G.; Duffey, T.A.

1982-03-01

Sandia National Laboratories was asked by the US Energy Research and Development Administration (now US Department of Energy) to design the spent fuel shipping cask system for the Clinch River Breeder Reactor Plant (CRBRP). As a part of this task, a canister which holds liquid sodium and the spent fuel assembly was designed, analyzed, and tested. The canister body survived the regulatory Type-B 9.1-m (30-ft) drop test with no apparent leakage. However, the commercially available metal seal used in this design leaked after the tests. This report describes the design approach, analysis, and prototype canister testing. Recommended work for completing the design, when funding is available, is included
Proposal for agar disk diffusion interpretive criteria for susceptibility testing of bovine mastitis pathogens using cefoperazone 30μg disks.

Science.gov (United States)

Feßler, Andrea T; Kaspar, Heike; Lindeman, Cynthia J; Peters, Thomas; Watts, Jeffrey L; Schwarz, Stefan

2017-02-01

Cefoperazone is a third generation cephalosporin which is commonly used for bovine mastitis therapy. Bacterial pathogens involved in bovine mastitis are frequently tested for their susceptibility to cefoperazone. So far, the cefoperazone susceptibility testing using 30μg disks has been hampered by the lack of quality control (QC) ranges as well as the lack of interpretive criteria. In 2014, QC ranges for 30 μg cefoperazone disks have been established for Staphylococcus aureus ATCC ® 25923 and Escherichia coli ATCC ® 25922. As a next step, interpretive criteria for the susceptibility testing of bovine mastitis pathogens should be developed. For this, 637 bovine mastitis pathogens (including 112 S. aureus, 121 coagulase-negative staphylococci (CoNS), 103 E. coli, 101 Streptococcus agalactiae, 100 Streptococcus dysgalactiae and 100 Streptococcus uberis) were investigated by agar disk diffusion according to the document Vet01-A4 of the Clinical and Laboratory Standards Institute (CLSI) using 30μg cefoperazone disks and the results were compared to the corresponding MIC values as determined by broth microdilution also according to the aforementioned CLSI document. Based on the results obtained and taking into account the achievable milk concentration of cefoperazone after regular dosing, the following interpretive criteria were proposed as a guidance for mastitis diagnostic laboratories: for staphylococci and E. coli ≥23mm (susceptible), 18-22mm (intermediate) and ≤17mm (resistant) and for streptococci ≥18mm (susceptible), and ≤17mm (non-susceptible). These proposed interpretive criteria shall contribute to a harmonization of cefoperazone susceptibility testing of bovine mastitis pathogens. Copyright © 2016 Elsevier B.V. All rights reserved.
Functional Testing of Wireless Sensor Node Designs

DEFF Research Database (Denmark)

Virk, Kashif M.; Madsen, Jan

2007-01-01

Wireless sensor networks are networked embedded computer systems with stringent power, performance, cost and form-factor requirements along with numerous other constraints related to their pervasiveness and ubiquitousness. Therefore, only a systematic design methdology coupled with an efficient...... test approach can enable their conformance to design and deployment specifications. We discuss off-line, hierarchical, functional testing of complete wireless sensor nodes containing configurable logic through a combination of FPGA-based board test and Software-Based Self-Test (SBST) techniques...
Time-Dependent Deformation Modelling for a Chopped-Glass Fiber Composite for Automotive Durability Design Criteria; FINAL

International Nuclear Information System (INIS)

Ren, W

2001-01-01

Time-dependent deformation behavior of a polymeric composite with chopped-glass-fiber reinforcement was investigated for automotive applications, The material under stress was exposed to representative automobile service environments. Results show that environment has substantial effects on time-dependent deformation behavior of the material. The data were analyzed and experimentally-based models developed for the time-dependent deformation behavior as a basis for automotive structural durability design criteria
Functional design criteria for project W-252, phase II liquid effluent treatment and disposal. Revision 2

International Nuclear Information System (INIS)

Hatch, C.E.

1995-05-01

This document is the Functional Design Criteria for Project W-252. Project W-252 provides the scope to provide BAT/AKART (best available technology...) to 200 Liquid Effluent Phase II streams (B-Plant). This revision (Rev. 2) incorporates a major descoping of the project. The descoping was done to reflect a combination of budget cutting measures allowed by a less stringent regulatory posture toward the Phase II streams
Aspirational Model Teaching Criteria for Psychology

Science.gov (United States)

Richmond, Aaron S.; Boysen, Guy A.; Gurung, Regan A. R.; Tazeau, Yvette N.; Meyers, Steven A.; Sciutto, Mark J.

2014-01-01

In 2011, the Society for the Teaching of Psychology commissioned a presidential task force to document teaching criteria for model psychology teachers in undergraduate education. The resulting list of criteria reflects activities related to face-to-face course interaction and online teaching, training, and education; course design; implementation…
Safety Design Criteria and Approaches to Safety Substantiation of the BN-1200

International Nuclear Information System (INIS)

Ashurko, I.

2013-01-01

Russian experience in SFR area: Activities on development of safety design criteria for SFRs of the 4th generation is carried out within the GIF framework. Although this reactor technology is considered as innovative that is relevant to the 4th generation, however, it has already a certain history. In this relation, it seems to be useful to analyze the corresponding experience that is available in various countries. 4 SFRs have been successfully operated in the USSR and in the Russian Federation: • Experimental reactor BR-5/10; • Research reactor BOR-60; • Prototype BN-350 power reactor; • Commercial BN-600 power unit at the Beloyarsk NPP. Thus, Russia gained a considerable experience of design, construction and operation of SFRs. In particular, a certain experience has been acquired on safety substantiation of reactors of this type and their licensing. Now BOR-60 and BN-600 continue their operation, BN-800 power unit is under construction, development of the commercial BN-1200 power unit, that is considered as the 4th generation reactor, has been started. Due to limited number of operating SFRs in the world, successful Russian experience in this area should be taken into account for further development and improvement of SFR SDC developed by the GIF Task Force. In particular, participation of SFR designers in this activities would be fruitful and useful
RAMI strategies in the IFMIF Test Facilities design

Energy Technology Data Exchange (ETDEWEB)

Abal, Javier, E-mail: javier.abal@upc.edu [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Dies, Javier [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Arroyo, José Manuel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); Bargalló, Enric [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Casal, Natalia; García, Ángela [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); Martínez, Gonzalo; Tapia, Carlos; De Blas, Alfredo [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Mollá, Joaquín; Ibarra, Ángel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain)

2013-10-15

Highlights: • We have implemented fault tolerant design strategies so that the strong availability requirements are met. • The evolution to the present design of the signal and cooling lines inside the TTC has also been compared. • The RAMI analyses have demonstrated a strong capability in being a complementary tool in the design of IFMIF Test Facilities. -- Abstract: In this paper, a RAMI analysis of the different stages in Test Facilities (TF) design is described. The comparison between the availability results has been a milestone not only to evaluate the major unavailability contributors in the updates but also to implement fault tolerant design strategies when possible. These strategies encompass a wide range of design activities: from the definition of degraded modes of operation in the Test Facilities to specific modifications in the test modules in order to guarantee their fail safe operation.
RAMI strategies in the IFMIF Test Facilities design

International Nuclear Information System (INIS)

Abal, Javier; Dies, Javier; Arroyo, José Manuel; Bargalló, Enric; Casal, Natalia; García, Ángela; Martínez, Gonzalo; Tapia, Carlos; De Blas, Alfredo; Mollá, Joaquín; Ibarra, Ángel

2013-01-01

Highlights: • We have implemented fault tolerant design strategies so that the strong availability requirements are met. • The evolution to the present design of the signal and cooling lines inside the TTC has also been compared. • The RAMI analyses have demonstrated a strong capability in being a complementary tool in the design of IFMIF Test Facilities. -- Abstract: In this paper, a RAMI analysis of the different stages in Test Facilities (TF) design is described. The comparison between the availability results has been a milestone not only to evaluate the major unavailability contributors in the updates but also to implement fault tolerant design strategies when possible. These strategies encompass a wide range of design activities: from the definition of degraded modes of operation in the Test Facilities to specific modifications in the test modules in order to guarantee their fail safe operation
Design description and validation results for the IFMIF High Flux Test Module as outcome of the EVEDA phase

Directory of Open Access Journals (Sweden)

F. Arbeiter

2016-12-01

Full Text Available During the Engineering Validation and Engineering Design Activities (EVEDA phase (2007-2014 of the International Fusion Materials Irradiation Facility (IFMIF, an advanced engineering design of the High Flux Test Module (HFTM has been developed with the objective to facilitate the controlled irradiation of steel samples in the high flux area directly behind the IFMIF neutron source. The development process addressed included manufacturing techniques, CAD, neutronic, thermal-hydraulic and mechanical analyses complemented by a series of validation activities. Validation included manufacturing of 1:1 parts and mockups, test of prototypes in the FLEX and HELOKA-LP helium loops of KIT for verification of the thermal and mechanical properties, and irradiation of specimen filled capsule prototypes in the BR2 test reactor. The prototyping activities were backed by several R&D studies addressing focused issues like handling of liquid NaK (as filling medium and insertion of Small Specimen Test Technique (SSTT specimens into the irradiation capsules. This paper provides an up-todate design description of the HFTM irradiation device, and reports on the achieved performance criteria related to the requirements. Results of the validation activities are accounted for and the most important issues for further development are identified.
Safety design criteria for the next generation Sodium-cooled fast reactors based on lessons learned from the Fukushima NPS accident

International Nuclear Information System (INIS)

Sakai, Takaaki

2012-01-01

In this presentation, architecture of the safety design criteria as requirements for SFR system and the activities on safety research works to establish safety evaluation methods for the next generation SFRs are summarized with the basis on lessons learned from the Fukushima NPS accident. Nuclear safety is a grovel issue which should be achieved by the international cooperation. In respect of the development for the next generation reactor, it is necessary to build the harmonized safety criteria and evaluation methods to establish the next level of safety
Hypothesis Designs for Three-Hypothesis Test Problems

OpenAIRE

Yan Li; Xiaolong Pu

2010-01-01

As a helpful guide for applications, the alternative hypotheses of the three-hypothesis test problems are designed under the required error probabilities and average sample number in this paper. The asymptotic formulas and the proposed numerical quadrature formulas are adopted, respectively, to obtain the hypothesis designs and the corresponding sequential test schemes under the Koopman-Darmois distributions. The example of the normal mean test shows that our methods are qu...
Allergic bronchopulmonary aspergillosis in Italian cystic fibrosis patients: Prevalence and percentage of positive tests in the employed diagnostic criteria

International Nuclear Information System (INIS)

Taccetti, Giovanni; Procopio, Elena; Marianelli, Lore; Campana, Silvia

2000-01-01

The prevalence of allergic bronchopulmonary aspergillosis (ABPA) in cystic fibrosis (CF) patients is difficult to determine because the data in the literature are not homogeneous or comparable. ABPA and CF have similar clinical symptoms which make diagnosis difficult and underestimate the real dimensions of the problem. We conducted an epidemiological study on 3089 Italian CF patients to determine the prevalence of ABPA in Italy and verify the percentage of positive tests in the employed diagnostic criteria. Our results indicate that the prevalence of ABPA in Italian CF patients is 6.18%, mainly in adolescents and young adults. ABPA is diagnosed using clinical symptoms (presence of episodic bronchial obstructions or typical radiographic features) and on the basis of other criteria which can only be partially fulfilled in paediatric patients. Among the diagnostic tests the most sensitive are the total IgE (84.5%), specific IgE anti-Aspergillus fumigatus (81.6%) and the prick test (68.3%). In the absence of clinical symptoms and gold standard diagnostic tests, serological positivity and/or the skin test are not sufficient evidence to confirm the presence of ABPA

Repository operational criteria comparative analysis

International Nuclear Information System (INIS)

Hageman, J.P.; Chowdhury, A.H.

1994-06-01

The objective of the ''Repository Operational Criteria (ROC) Feasibility Studies'' (or ROC task) was to conduct comprehensive and integrated analyses of repository design, construction, and operations criteria in 10 CFR Part 60 regulations considering the interfaces among the components of the regulations and impacts of any potential changes to those regulations. The ROC task addresses regulatory criteria and uncertainties related to the preclosure aspects of the geologic repository. Those parts of 10 CFR Part 60 that require routine guidance or minor changes to the rule were addressed in Hageman and Chowdhury, 1992. The ROC task shows a possible need for further regulatory clarity, by major changes to the rule, related to the design bases and siting of a geologic repository operations area and radiological emergency planning in order to assure defense-in-depth. The analyses, presented in this report, resulted in the development and refinement of regulatory concepts and their supporting rationale for recommendations for potential major changes to 10 CFR Pan 0 regulations
Testing some of Benjamin Graham’s Stock Selection Criteria: A Case of the FTSE Bursa Malaysia EMAS Index from Year 2000 to 2009

Directory of Open Access Journals (Sweden)

Desmond Chang

2011-01-01

Full Text Available Benjamin Graham, also known as the “father of value investing” proposed that investment in the stock exchange can be a safe endeavor while receiving gains that outperform the market if the investor makes carefully thought out purchases. This study aims to determine if the use of some of Benjamin Graham’s stock selection criteria is able to generate returns that are significantly greater than the returns in the stock exchange of Malaysia, particularly, the comprehensive FTSE Bursa Malaysia EMAS Index. This study collected secondary data regarding fundamentals of companies listed in the FTSE Bursa Malaysia EMAS Index from the year 2000 to 2009. Five criteria were set up in this research based on one or a combination of price-to-earnings ratio, price-to-book value, current ratio and dividend yield. The listed companies were screened using those criteria. An equally weighted portfolio was created using the screened companies and their one-year and two-year returns calculated. The returns were compared to the market return. Hypotheses of this research were tested using t-test statistic to determine the significance of the data. This research found that most of the screening criteria used generated returns that were higher than the market return in almost every year they were tested in. Benjamin Graham’s stock selection criteria although have been conceived over 80 years ago is still applicable today in the Malaysian market. Further research can be conducted with different criteria with varying holding periods and in different markets.
Development of Design Criteria for Fluid Induced Structural Vibrations in Steam Generators and Heat Exchangers

International Nuclear Information System (INIS)

Uvan Catton; Dhir, Vijay K.; Deepanjan Mitra; Omar Alquaddoomi; Pierangelo Adinolfi

2004-01-01

Flow-induced vibration in heat exchangers has been a major cause of concern in the nuclear industry for several decades. Many incidents of failure of heat exchangers due to apparent flow-induced vibration have been reported through the USNRC incident reporting system. Almost all heat exchangers have to deal with this problem during their operation. The phenomenon has been studied since the 1970s and the database of experimental studies on flow-induced vibration is constantly updated with new findings and improved design criteria for heat exchangers
EID - prototype design and user test 2004

International Nuclear Information System (INIS)

Welch, Robin; Friberg, Maarten; Nystad, Espen; Teigen, Arild; Veland, Oeystein

2005-08-01

programme is to gain insight into how this methodology can contribute to the design of operator displays in the nuclear industry. To do this, it was decided to design a limited number of displays on the FRESH simulator and conduct a user test to examine whether operators would be able to use and accept this type of design. The FRESH EID displays intend to show information and relationships in a graphical form that would require substantially more mental resources to utilize if using the conventional displays. This HWR presents the background for EID, the analysis process, the displays that have been designed, the user test and the outcome of the user test. This first attempt at developing and evaluating an EID has provided both valuable practical lessons learned and promising results for further work. (Author)
DECADE design and testing status

International Nuclear Information System (INIS)

Sincerny, P.; Childers, K.; Goyer, J.; Kortbawi, D.; Roth, I.; Stallings, C.; Dempsey, J.; Schlitt, L.

1996-01-01

DECADE is a very high power generator that will be built at Arnold Engineering Development Center in Tullahoma, Tennessee, by the Defense Special Weapons Agency. The full facility consists of 16 modules. Two full power modules (DM1 and DM2) have been built to verify the DECADE design at Physics International. Each module consists of a 570 kJ Marx generator that pulse charges a water transfer capacitor. The transfer capacitor discharges into a water output line through an array of 6 parallel triggered gas switches. The water output line then pulse charges the inductive store/opening switch pulse compression stage. When the opening switch opens, the inductive store discharges into an electron beam bremsstrahlung diode load. The initial testing of the DM1 module has been completed. The electrical design of the module will be presented, including circuit modeling results. The test data from a module will be compared to the modeling results. This test data, including reproducibility and timing accuracy, was used to predict the output from the full system of 16 modules and a subset of 4 unit modules (DECADE Quad). One option under consideration is to deploy a DECADE Quad at the testing center in Tennessee prior to the full 16 module system. The design sketch of the DECADE Quad and the predicted output based on the modeling and the demonstrated module performance is given. (author). 11 figs., 11 refs
DECADE design and testing status

Energy Technology Data Exchange (ETDEWEB)

Sincerny, P; Childers, K; Goyer, J; Kortbawi, D; Roth, I; Stallings, C; Dempsey, J [Physics International Company, San Leandro, CA (United States); Schlitt, L [Leland Schlitt Consulting Services, Livermore, CA (United States)

1997-12-31

DECADE is a very high power generator that will be built at Arnold Engineering Development Center in Tullahoma, Tennessee, by the Defense Special Weapons Agency. The full facility consists of 16 modules. Two full power modules (DM1 and DM2) have been built to verify the DECADE design at Physics International. Each module consists of a 570 kJ Marx generator that pulse charges a water transfer capacitor. The transfer capacitor discharges into a water output line through an array of 6 parallel triggered gas switches. The water output line then pulse charges the inductive store/opening switch pulse compression stage. When the opening switch opens, the inductive store discharges into an electron beam bremsstrahlung diode load. The initial testing of the DM1 module has been completed. The electrical design of the module will be presented, including circuit modeling results. The test data from a module will be compared to the modeling results. This test data, including reproducibility and timing accuracy, was used to predict the output from the full system of 16 modules and a subset of 4 unit modules (DECADE Quad). One option under consideration is to deploy a DECADE Quad at the testing center in Tennessee prior to the full 16 module system. The design sketch of the DECADE Quad and the predicted output based on the modeling and the demonstrated module performance is given. (author). 11 figs., 11 refs.
Pulse Jet Mixing Tests With Noncohesive Solids

Energy Technology Data Exchange (ETDEWEB)

Meyer, Perry A.; Bamberger, Judith A.; Enderlin, Carl W.; Fort, James A.; Wells, Beric E.; Sundaram, S. K.; Scott, Paul A.; Minette, Michael J.; Smith, Gary L.; Burns, Carolyn A.; Greenwood, Margaret S.; Morgen, Gerald P.; Baer, Ellen BK; Snyder, Sandra F.; White, Michael; Piepel, Gregory F.; Amidan, Brett G.; Heredia-Langner, Alejandro; Bailey, Sharon A.; Bower, John C.; Denslow, Kayte M.; Eakin, David E.; Elmore, Monte R.; Gauglitz, Phillip A.; Guzman, Anthony D.; Hatchell, Brian K.; Hopkins, Derek F.; Hurley, David E.; Johnson, Michael D.; Kirihara, Leslie J.; Lawler, Bruce D.; Loveland, Jesse S.; Mullen, O Dennis; Pekour, Mikhail S.; Peters, Timothy J.; Robinson, Peter J.; Russcher, Michael S.; Sande, Susan; Santoso, Christian; Shoemaker, Steven V.; Silva, Steve M.; Smith, Devin E.; Su, Yin-Fong; Toth, James J.; Wiberg, John D.; Yu, Xiao-Ying; Zuljevic, Nino

2009-05-11

This report summarizes results from pulse jet mixing (PJM) tests with noncohesive solids in Newtonian liquid conducted during FY 2007 and 2008 to support the design of mixing systems for the Hanford Waste Treatment and Immobilization Plant (WTP). Tests were conducted at three geometric scales using noncohesive simulants. The test data were used to independently develop mixing models that can be used to predict full-scale WTP vessel performance and to rate current WTP mixing system designs against two specific performance requirements. One requirement is to ensure that all solids have been disturbed during the mixing action, which is important to release gas from the solids. The second requirement is to maintain a suspended solids concentration below 20 weight percent at the pump inlet. The models predict the height to which solids will be lifted by the PJM action, and the minimum velocity needed to ensure all solids have been lifted from the floor. From the cloud height estimate we can calculate the concentration of solids at the pump inlet. The velocity needed to lift the solids is slightly more demanding than "disturbing" the solids, and is used as a surrogate for this metric. We applied the models to assess WTP mixing vessel performance with respect to the two perform¬ance requirements. Each mixing vessel was evaluated against these two criteria for two defined waste conditions. One of the wastes was defined by design limits and one was derived from Hanford waste characterization reports. The assessment predicts that three vessel types will satisfy the design criteria for all conditions evaluated. Seven vessel types will not satisfy the performance criteria used for any of the conditions evaluated. The remaining three vessel types provide varying assessments when the different particle characteristics are evaluated. The assessment predicts that three vessel types will satisfy the design criteria for all conditions evaluated. Seven vessel types will not satisfy
Design requirements for the supercritical water oxidation test bed

International Nuclear Information System (INIS)

Svoboda, J.M.; Valentich, D.J.

1994-05-01

This report describes the design requirements for the supercritical water oxidation (SCWO) test bed that will be located at the Idaho National Engineering Laboratory (INEL). The test bed will process a maximum of 50 gph of waste plus the required volume of cooling water. The test bed will evaluate the performance of a number of SCWO reactor designs. The goal of the project is to select a reactor that can be scaled up for use in a full-size waste treatment facility to process US Department of Energy mixed wastes. EG ampersand G Idaho, Inc. will design and construct the SCWO test bed at the Water Reactor Research Test Facility (WRRTF), located in the northern region of the INEL. Private industry partners will develop and provide SCWO reactors to interface with the test bed. A number of reactor designs will be tested, including a transpiring wall, tube, and vessel-type reactor. The initial SCWO reactor evaluated will be a transpiring wall design. This design requirements report identifies parameters needed to proceed with preliminary and final design work for the SCWO test bed. A flow sheet and Process and Instrumentation Diagrams define the overall process and conditions of service and delineate equipment, piping, and instrumentation sizes and configuration Codes and standards that govern the safe engineering and design of systems and guidance that locates and interfaces test bed hardware are provided. Detailed technical requirements are addressed for design of piping, valves, instrumentation and control, vessels, tanks, pumps, electrical systems, and structural steel. The approach for conducting the preliminary and final designs and environmental and quality issues influencing the design are provided
Design and Development of the Space Shuttle Tail Service Masts

Science.gov (United States)

Dandage, S. R.; Herman, N. A.; Godfrey, S. E.; Uda, R. T.

1977-01-01

The successful launch of a space shuttle vehicle depends on the proper operation of two tail service masts (TSMs). Reliable TSM operation is assured through a comprehensive design, development, and testing program. The results of the concept verification test (CVT) and the resulting impact on prototype TSM design are presented. The design criteria are outlined, and the proposed prototype TSM tests are described.
Regulation on control systems tests

International Nuclear Information System (INIS)

Grau, J.; Navarro, J.M.

1978-01-01

Requirements under regulation applicable to the testing of control systems and controlled equipments in the case of USA nuclear projects are examined. They are reviewed, in particular, the following standards and criteria: 10 Code of Federal Regulations 50, Appendix A, General Design Criteria 20 and 21; IEEE Standards 279 and 308; IEEE Standard 338; US Regulatory Guides 1.22 and 1.118.(J.E.de C.)
Design criteria for a high energy Compton Camera and possible application to targeted cancer therapy

Science.gov (United States)

Conka Nurdan, T.; Nurdan, K.; Brill, A. B.; Walenta, A. H.

2015-07-01

The proposed research focuses on the design criteria for a Compton Camera with high spatial resolution and sensitivity, operating at high gamma energies and its possible application for molecular imaging. This application is mainly on the detection and visualization of the pharmacokinetics of tumor targeting substances specific for particular cancer sites. Expected high resolution (animals with a human tumor xenograft which is one of the first steps in evaluating the potential utility of a candidate gene. The additional benefit of high sensitivity detection will be improved cancer treatment strategies in patients based on the use of specific molecules binding to cancer sites for early detection of tumors and identifying metastasis, monitoring drug delivery and radionuclide therapy for optimum cell killing at the tumor site. This new technology can provide high resolution, high sensitivity imaging of a wide range of gamma energies and will significantly extend the range of radiotracers that can be investigated and used clinically. The small and compact construction of the proposed camera system allows flexible application which will be particularly useful for monitoring residual tumor around the resection site during surgery. It is also envisaged as able to test the performance of new drug/gene-based therapies in vitro and in vivo for tumor targeting efficacy using automatic large scale screening methods.
Test requirements for the integral effect test to simulate Korean PWR plants

Energy Technology Data Exchange (ETDEWEB)

Song, Chul Hwa; Park, C. K.; Lee, S. J.; Kwon, T. S.; Yun, B. J.; Chung, M. K

2001-02-01

In this report, the test requirements are described for the design of the integral effect test facility to simulate Korean PWR plants. Since the integral effect test facility should be designed so as to simulate various thermal hydraulic phenomena, as closely as possible, to be occurred in real plants during operation or anticipated transients, the design and operational characteristics of the reference plants (Korean Standard Nuclear Plant and Korean Next Generation Reactor)were analyzed in order to draw major components, systems, and functions to be satisfied or simulated in the test facility. The test matrix is set up by considering major safety concerns of interest and the test objectives to confirm and enhance the safety of the plants. And the analysis and prioritization of the test matrix leads to the general design requirements of the test facility. Based on the general design requirements, the design criteria is set up for the basic and detailed design of the test facility. And finally it is drawn the design requirements specific to the fluid system and measurement system of the test facility. The test requirements in this report will be used as a guideline to the scaling analysis and basic design of the test facility. The test matrix specified in this report can be modified in the stage of main testing by considering the needs of experiments and circumstances at that time.
Test requirements for the integral effect test to simulate Korean PWR plants

International Nuclear Information System (INIS)

Song, Chul Hwa; Park, C. K.; Lee, S. J.; Kwon, T. S.; Yun, B. J.; Chung, M. K.

2001-02-01

In this report, the test requirements are described for the design of the integral effect test facility to simulate Korean PWR plants. Since the integral effect test facility should be designed so as to simulate various thermal hydraulic phenomena, as closely as possible, to be occurred in real plants during operation or anticipated transients, the design and operational characteristics of the reference plants (Korean Standard Nuclear Plant and Korean Next Generation Reactor)were analyzed in order to draw major components, systems, and functions to be satisfied or simulated in the test facility. The test matrix is set up by considering major safety concerns of interest and the test objectives to confirm and enhance the safety of the plants. And the analysis and prioritization of the test matrix leads to the general design requirements of the test facility. Based on the general design requirements, the design criteria is set up for the basic and detailed design of the test facility. And finally it is drawn the design requirements specific to the fluid system and measurement system of the test facility. The test requirements in this report will be used as a guideline to the scaling analysis and basic design of the test facility. The test matrix specified in this report can be modified in the stage of main testing by considering the needs of experiments and circumstances at that time
Conceptual design of the integral test loop (I): Reactor coolant system and secondary system

Energy Technology Data Exchange (ETDEWEB)

Song, Chul Hwa; Lee, Seong Je; Kwon, Tae Soon; Moon, Sang Ki [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-10-01

This report describes the conceptual design of the primary coolant system and the secondary system of the Integral Test Loop (ITL) which simulates overall thermal hydraulic phenomena of the primary system of a nuclear power plant during postulated accidents or transients. The design basis for the primary coolant system and secondary system is as follows ; Reference plant: Korean Standard Nuclear Plant (KSNP), Height ratio : 1/1, Volume ratio : 1/200, Power scale : Max. 15% of the scaled nominal power, Temperature, Pressure : Real plant conditions. The primary coolant system includes a reactor vessel, which contains a core simulator, a steam generator, a reactor coolant pump simulator, a pressurizer and piping, which consists of two hot legs, four cold legs and four intermediate legs. The secondary system consists of s steam discharge system, a feedwater supply system and a steam condensing system. This conceptual design report describes general configuration of the reference plant, and major function and operation of each system of the plant. Also described is the design philosophy of each component and system of the ITL, and specified are the design criteria and technical specifications of each component and system of the ITL in the report. 17 refs., 43 figs., 51 tabs. (Author)
PA171 Containers on a Wood Pallet with Metal Top Adapter, Air Pressure Tests During MIL-STD-1660 Tests

National Research Council Canada - National Science Library

2004-01-01

... (PM-MAS) to conduct Air Pressure Tests during MIL-STD-1660, "Design Criteria for Ammunition Unit Loads" testing on the PA171 containers on a wood pallet with metal top adapter as manufactured by Alliant Tech...
Development and testing of new upper-limb prosthetic devices: research designs for usability testing.

Science.gov (United States)

Resnik, Linda

2011-01-01

The purposes of this article are to describe usability testing and introduce designs and methods of usability testing research as it relates to upper-limb prosthetics. This article defines usability, describes usability research, discusses research approaches to and designs for usability testing, and highlights a variety of methodological considerations, including sampling, sample size requirements, and usability metrics. Usability testing is compared with other types of study designs used in prosthetic research.
Preconceptual design for the electrostatic enclosure

International Nuclear Information System (INIS)

Meyer, L.C.

1992-09-01

This report presents a preconceptual design (design criteria and assumptions) for electrostatic enclosures to be used during buried transuranic waste recovery operations. These electrostatic enclosures (along with the application of dust control products) will provide an in-depth contamination control strategy. As part of this preconceptual design, options for electrostatic curtain design are given including both hardwall and fabric enclosures. Ventilation systems, doors, air locks, electrostatic curtains, and supporting systems also are discussed. In addition to the conceptual design, engineering scale tests are proposed to be run at the Test Reactor Area. The planned engineering scale tests will give final material specifications for full-scale retrieval demonstrations
Criteria for designing an interim waste storage facility

International Nuclear Information System (INIS)

Vicente, Roberto

2011-01-01

The long-lived radioactive wastes with activity above clearance levels generated by radioisotope users in Brazil are collected into centralized waste storage facilities under overview of the National Commission on Nuclear Energy (CNEN). One of these centers is the Radioactive Waste Management Department (GRR) at the Nuclear and Energy Research Institute (IPEN), in Sao Paulo, which since 1978 also manages the wastes generated by IPEN itself. Present inventory of stored wastes includes about 160 tons of treated wastes, distributed in 1290 steel, 200-liters drums, and 52 steel, 1.6 m 3 -boxes, with an estimated total activity of 0.8 TBq. Radionuclides present in these wastes are fission and activation products, transuranium elements, and isotopes from the uranium and thorium decay series. The capacity and quality of the storage rooms at GRR evolved along the last decades to meet the requirements set forth by the Brazilian regulatory authorities.From a mere outdoor concrete platform over which drums were simply stacked and covered with canvas to the present day building, a great progress was made in the storage method. In this paper we present the results of a study in the criteria that were meant to guide the design of the storage building, many of which were eventually adopted in the final concept, and are now built-in features of the facility. We also present some landmarks in the GRR's activities related to waste management in general and waste storage in particular, until the treated wastes of IPEN found their way into the recently licensed new storage facility. (author)
Detail design of test loop for FIV in fuel bundle and preliminary test

Energy Technology Data Exchange (ETDEWEB)

Sim, Woo Gunl; Lee, Wan Young; Kim, Sung Won [Hannam University, Taejeon (Korea)

2002-04-01

It is urgent to develop the analytical model for the structural/mechanical integrity of fuel rod. In general, it is not easy to develop a pure analytical model. Occasionally, experimental results have been utilized for the model.Because of this reason, it is required to design proper test loop. Using the optimized test loop, With the optimized test loop, the dynamic behaviour of the rod will be evaluated and the critical flow velocity, which the rod loses the stability in, will be measured for the design of the rod. To verify the integrity of the fuel rod, it is required to evaluate the dynamic behaviour and the critical flow velocity with the test loop. The test results will be utilized to the design of the rod. Generally, the rod has a ground vibration due to turbulence in wide range of flow velocity and the amplitude of vibration becomes larger by the resonance, in a range of the velocity where occurs vortex. The rod loses stability in critical flow velocity caused by fluid-elastic instability. For the purpose of the present work to perform the conceptional design of the test loop, it is necessary (1) to understand the mechanism of the flow-induced vibration and the related experimental coefficients, (2) to evaluate the existing test loops for improving the loop with design parameters and (3) to decide the design specifications of the major equipments of the loop. 35 refs., 14 figs., 4 tabs. (Author)
Ancillary testing, diagnostic/classification criteria and severity grading in Behçet disease.

Science.gov (United States)

Okada, Annabelle A; Stanford, Miles; Tabbara, Khalid

2012-12-01

Since there is no pathognomonic clinical sign or laboratory test to distinguish Behçet disease from other uveitic entities, the diagnosis must be made based on characteristic ocular and systemic findings in the absence of evidence of other disease that can explain the findings. Ancillary tests, including ocular and brain imaging studies, are used to assess the severity of intraocular inflammation and systemic manifestations of Behçet disease, to identify latent infections and other medical conditions that might worsen with systemic treatment, and to monitor for adverse effects of drugs used. There are two diagnostic or classification criteria in general use by the uveitis community, one from Japan and one from an international group; both rely on a minimum number and/or combination of clinical findings to identify Behçet disease. Finally, several grading schemes have been proposed to assess severity of ocular disease and response to treatment.

A Psychological Measurement of Student Testing Design Preferences.

Science.gov (United States)

Shukla, P. K.; Bruno, James

An analytical technique from the field of market research called conjoint analysis was applied to a psychological measurement of student testing design preferences. Past concerns with testing design are reviewed, and a newer approach to testing is identified--the modified confidence weighted-admissible probability measurement (MCW-APM) test…
Design and Testing of an Educational Water Tunnel

Science.gov (United States)

Kosaraju, Srinivas

2017-11-01

A new water tunnel is designed and tested for educational and research purposes at Northern Arizona University. The university currently owns an educational wind tunnel with a test section of 12in X 12in X 24in. However, due to limited size of test section and range of Reynolds numbers, its application is currently limited to very few experiments. In an effort to expand the educational and research capabilities, a student team is tasked to design, build and test a water tunnel as a Capstone Senior Design project. The water tunnel is designed to have a test section of 8in X 8in X 36in. and be able to test up to Re = 50E3. Multiple numerical models are used to optimize the flow field inside the test section before building the physical apparatus. The water tunnel is designed to accommodate multiple experiments for drag and lift studies. The built-in die system can deliver up to three different colors to study the streamlines and vortex shedding from the surfaces. During the first phase, a low discharge pump is used to achieve Re = 4E3 to test laminar flows. In the second phase, a high discharge pump will be used to achieve targeted Re = 50E3 to study turbulent flows.
The Healy Clean Coal Project: Design verification tests

International Nuclear Information System (INIS)

Guidetti, R.H.; Sheppard, D.B.; Ubhayakar, S.K.; Weede, J.J.; McCrohan, D.V.; Rosendahl, S.M.

1993-01-01

As part of the Healy Clean Coal Project, TRW Inc., the supplier of the advanced slagging coal combustors, has successfully completed design verification tests on the major components of the combustion system at its Southern California test facility. These tests, which included the firing of a full-scale precombustor with a new non-storage direct coal feed system, supported the design of the Healy combustion system and its auxiliaries performed under Phase 1 of the project. Two 350 million BTU/hr combustion systems have been designed and are now ready for fabrication and erection, as part of Phase 2 of the project. These systems, along with a back-end Spray Dryer Absorber system, designed and supplied by Joy Technologies, will be integrated with a Foster Wheeler boiler for the 50 MWe power plant at Healy, Alaska. This paper describes the design verification tests and the current status of the project
Computer-Aided Test Flow in Core-Based Design

NARCIS (Netherlands)

Zivkovic, V.; Tangelder, R.J.W.T.; Kerkhoff, Hans G.

2000-01-01

This paper copes with the test-pattern generation and fault coverage determination in the core based design. The basic core-test strategy that one has to apply in the core-based design is stated in this work. A Computer-Aided Test (CAT) flow is proposed resulting in accurate fault coverage of
Regulatory Safety Issues in the Structural Design Criteria of ASME Section III Subsection NH and for Very High Temperatures for VHTR & GEN IV

Energy Technology Data Exchange (ETDEWEB)

William J. O’Donnell; Donald S. Griffin

2007-05-07

The objective of this task is to identify issues relevant to ASME Section III, Subsection NH [1], and related Code Cases that must be resolved for licensing purposes for VHTGRs (Very High Temperature Gas Reactor concepts such as those of PBMR, Areva, and GA); and to identify the material models, design criteria, and analysis methods that need to be added to the ASME Code to cover the unresolved safety issues. Subsection NH was originally developed to provide structural design criteria and limits for elevated-temperature design of Liquid Metal Fast Breeder Reactor (LMFBR) systems and some gas-cooled systems. The U.S. Nuclear Regulatory Commission (NRC) and its Advisory Committee for Reactor Safeguards (ACRS) reviewed the design limits and procedures in the process of reviewing the Clinch River Breeder Reactor (CRBR) for a construction permit in the late 1970s and early 1980s, and identified issues that needed resolution. In the years since then, the NRC and various contractors have evaluated the applicability of the ASME Code and Code Cases to high-temperature reactor designs such as the VHTGRs, and identified issues that need to be resolved to provide a regulatory basis for licensing. This Report describes: (1) NRC and ACRS safety concerns raised during the licensing process of CRBR , (2) how some of these issues are addressed by the current Subsection NH of the ASME Code; and (3) the material models, design criteria, and analysis methods that need to be added to the ASME Code and Code Cases to cover unresolved regulatory issues for very high temperature service.
Severe Accident Test Station Design Document

Energy Technology Data Exchange (ETDEWEB)

Snead, Mary A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Yan, Yong [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Howell, Michael [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Keiser, James R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Terrani, Kurt A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2015-09-01

The purpose of the ORNL severe accident test station (SATS) is to provide a platform for evaluation of advanced fuels under projected beyond design basis accident (BDBA) conditions. The SATS delivers the capability to map the behavior of advanced fuels concepts under accident scenarios across various temperature and pressure profiles, steam and steam-hydrogen gas mixtures, and thermal shock. The overall facility will include parallel capabilities for examination of fuels and irradiated materials (in-cell) and non-irradiated materials (out-of-cell) at BDBA conditions as well as design basis accident (DBA) or loss of coolant accident (LOCA) conditions. Also, a supporting analytical infrastructure to provide the data-needs for the fuel-modeling components of the Fuel Cycle Research and Development (FCRD) program will be put in place in a parallel manner. This design report contains the information for the first, second and third phases of design and construction of the SATS. The first phase consisted of the design and construction of an out-of-cell BDBA module intended for examination of non-irradiated materials. The second phase of this work was to construct the BDBA in-cell module to test irradiated fuels and materials as well as the module for DBA (i.e. LOCA) testing out-of-cell, The third phase was to build the in-cell DBA module. The details of the design constraints and requirements for the in-cell facility have been closely captured during the deployment of the out-of-cell SATS modules to ensure effective future implementation of the in-cell modules.
Severe Accident Test Station Design Document

International Nuclear Information System (INIS)

Snead, Mary A.; Yan, Yong; Howell, Michael; Keiser, James R.; Terrani, Kurt A.

2015-01-01

The purpose of the ORNL severe accident test station (SATS) is to provide a platform for evaluation of advanced fuels under projected beyond design basis accident (BDBA) conditions. The SATS delivers the capability to map the behavior of advanced fuels concepts under accident scenarios across various temperature and pressure profiles, steam and steam-hydrogen gas mixtures, and thermal shock. The overall facility will include parallel capabilities for examination of fuels and irradiated materials (in-cell) and non-irradiated materials (out-of-cell) at BDBA conditions as well as design basis accident (DBA) or loss of coolant accident (LOCA) conditions. Also, a supporting analytical infrastructure to provide the data-needs for the fuel-modeling components of the Fuel Cycle Research and Development (FCRD) program will be put in place in a parallel manner. This design report contains the information for the first, second and third phases of design and construction of the SATS. The first phase consisted of the design and construction of an out-of-cell BDBA module intended for examination of non-irradiated materials. The second phase of this work was to construct the BDBA in-cell module to test irradiated fuels and materials as well as the module for DBA (i.e. LOCA) testing out-of-cell, The third phase was to build the in-cell DBA module. The details of the design constraints and requirements for the in-cell facility have been closely captured during the deployment of the out-of-cell SATS modules to ensure effective future implementation of the in-cell modules.
Implementation Support of Security Design Patterns Using Test Templates

Directory of Open Access Journals (Sweden)

Masatoshi Yoshizawa

2016-06-01

Full Text Available Security patterns are intended to support software developers as the patterns encapsulate security expert knowledge. However, these patterns may be inappropriately applied because most developers are not security experts, leading to threats and vulnerabilities. Here we propose a support method for security design patterns in the implementation phase of software development. Our method creates a test template from a security design pattern, consisting of an “aspect test template” to observe the internal processing and a “test case template”. Providing design information creates a test from the test template with a tool. Because our test template is reusable, it can easily perform a test to validate a security design pattern. In an experiment involving four students majoring in information sciences, we confirm that our method can realize an effective test, verify pattern applications, and support pattern implementation.
Safety and reliability criteria

International Nuclear Information System (INIS)

O'Neil, R.

1978-01-01

Nuclear power plants and, in particular, reactor pressure boundary components have unique reliability requirements, in that usually no significant redundancy is possible, and a single failure can give rise to possible widespread core damage and fission product release. Reliability may be required for availability or safety reasons, but in the case of the pressure boundary and certain other systems safety may dominate. Possible Safety and Reliability (S and R) criteria are proposed which would produce acceptable reactor design. Without some S and R requirement the designer has no way of knowing how far he must go in analysing his system or component, or whether his proposed solution is likely to gain acceptance. The paper shows how reliability targets for given components and systems can be individually considered against the derived S and R criteria at the design and construction stage. Since in the case of nuclear pressure boundary components there is often very little direct experience on which to base reliability studies, relevant non-nuclear experience is examined. (author)
Computer-Aided Test Flow in Core-Based Design

OpenAIRE

Zivkovic, V.; Tangelder, R.J.W.T.; Kerkhoff, Hans G.

2000-01-01

This paper copes with the test-pattern generation and fault coverage determination in the core based design. The basic core-test strategy that one has to apply in the core-based design is stated in this work. A Computer-Aided Test (CAT) flow is proposed resulting in accurate fault coverage of embedded cores. The CAT now is applied to a few cores within the Philips Core Test Pilot IC project
Rock mechanics methods and in situ heater tests for design of a nuclear waste repository in basalt

International Nuclear Information System (INIS)

Board, M.P.

1978-01-01

Methods of integrating data from the Near-Surface Test Facility into the overall Waste Isolation Program are examined. Discussions are presented dealing primarily with the application of numerical models to the design of a waste repository. The various types of models currently available are discussed with reference to design in basalt and the breakdown of the problem of repository design is summarized. It is shown that the most efficient method for analyzing repository design is to break the problem down into several problems which are based on physical scale. These include the area directly surrounding a single waste canister (the very near field), the area including many canisters and canister emplacement rooms (the near field), and the area including the entire repository and the rock mass to the free surface (the far field). The methods by which numerical models are used for design are discussed. Flow charts are used to show the basic input data required, the calculational processes used, and the preliminary criteria for judgment of suitable repository performance. It is shown that the ultimate design of the allowable gross thermal loading density, and, thus, the layout of the underground workings is highly dependent upon the rock mass properties supplied as base line input data to the numerical models. Of the many input properties required, the thermal conductivity, the thermal expansion coefficient, and elastic moduli of the rock mass have, perhaps, the greatest effect on the calculation of induced temperatures, stresses, and displacements and, thus, repository design. To ensure that the design continues with confidence, field (in situ) values of input data must be obtained. The role of the Near-Surface Test Facility in situ testing in obtaining these basic required data is discussed
Design and Construction of a Hydroturbine Test Facility

Science.gov (United States)

Ayli, Ece; Kavurmaci, Berat; Cetinturk, Huseyin; Kaplan, Alper; Celebioglu, Kutay; Aradag, Selin; Tascioglu, Yigit; ETU Hydro Research Center Team

2014-11-01

Hydropower is one of the clean, renewable, flexible and efficient energy resources. Most of the developing countries invest on this cost-effective energy source. Hydroturbines for hydroelectric power plants are tailor-made. Each turbine is designed and constructed according to the properties, namely the head and flow rate values of the specific water source. Therefore, a center (ETU Hydro-Center for Hydro Energy Research) for the design, manufacturing and performance tests of hydraulic turbines is established at TOBB University of Economics and Technology to promote research in this area. CFD aided hydraulic and structural design, geometry optimization, manufacturing and performance tests of hydraulic turbines are the areas of expertise of this center. In this paper, technical details of the design and construction of this one of a kind test facility in Turkey, is explained. All the necessary standards of IEC (International Electrotechnical Commission) are met since the test facility will act as a certificated test center for hydraulic turbines.
Empirical evidence of design-related bias in studies of diagnostic tests

NARCIS (Netherlands)

Lijmer, J. G.; Mol, B. W.; Heisterkamp, S.; Bonsel, G. J.; Prins, M. H.; van der Meulen, J. H.; Bossuyt, P. M.

1999-01-01

CONTEXT: The literature contains a large number of potential biases in the evaluation of diagnostic tests. Strict application of appropriate methodological criteria would invalidate the clinical application of most study results. OBJECTIVE: To empirically determine the quantitative effect of study
Design of a fusion engineering test facility

International Nuclear Information System (INIS)

Sager, P.H.

1980-01-01

The fusion Engineering Test Facility (ETF) is being designed to provide for engineering testing capability in a program leading to the demonstration of fusion as a viable energy option. It will combine power-reactor-type components and subsystems into an integrated tokamak system and provide a test bed to test blanket modules in a fusion environment. Because of the uncertainties in impurity control two basic designs are being developed: a design with a bundle divertor (Design 1) and one with a poloidal divertor (Design 2). The two designs are similar where possible, the latter having somewhat larger toroidal field (TF) coils to accommodate removal of the larger torus sectors required for the single-null poloidal divertor. Both designs have a major radius of 5.4 m, a minor radius of 1.3 m, and a D-shaped plasma with an elongation of 1.6. Ten TF coils are incorporated in both designs, producing a toroidal field of 5.5 T on-axis. The ohmic heating and equilibrium field (EF) coils supply sufficient volt-seconds to produce a flat-top burn of 100 s and a duty cycle of 135 s, including a start of 12 s, a burn termination of 10 s, and a pumpdown of 13 s. The total fusion power during burn is 750 MW, giving a neutron wall loading of 1.5 MW/m 2 . In Design 1 of the poloidal field (PF) coils except the fast-response EF coils are located outside the FT coils and are superconducting. The fast-response coils are located inside the TF coil bore near the torus and are normal conducting so that they can be easily replaced.In Design 2 all of the PF coils are located outside the TF coils and are superconducting. Ignition is achieved with 60 MW of neutral beam injection at 150 keV. Five megawatts of radio frequency heating (electron cyclotron resonance heating) is used to assist in the startup and limit the breakdown requirement to 25 V
MFTF-α + T shield design

International Nuclear Information System (INIS)

Gohar, Y.

1985-01-01

MFTF-α+T is a DT upgrade option of the Tandem Mirror Fusion Test Facility (MFTF-B) to study better plasma performance, and test tritium breeding blankets in an actual fusion reactor environment. The central cell insert, designated DT axicell, has a 2-MW/m 2 neutron wall loading at the first wall for blanket testing. This upgrade is completely shielded to protect the reactor components, the workers, and the general public from the radiation environment during operation and after shutdown. The shield design for this upgrade is the subject of this paper including the design criteria and the tradeoff studies to reduce the shield cost
Receiver Test Selection Criteria

Science.gov (United States)

2015-03-12

The DOT requests that GPS manufacturers submit receivers for test in the following TWG categories: - Aviation (non-certified), cellular, general location/navigation, high precision, timing, networks, and space-based receivers - Each receiver should b...
NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

Energy Technology Data Exchange (ETDEWEB)

None

1982-07-01

This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.
NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

International Nuclear Information System (INIS)

1982-07-01

This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules
Pilot test of ANSI draft standard N13.29 environmental dosimetry -- Performance criteria for testing

International Nuclear Information System (INIS)

Klemic, G.; Shebell, P.; Monetti, M.; Raccah, F.; Sengupta, S.

1998-09-01

American National Standards Institute Draft N13.29 describes performance tests for environmental radiation dosimetry providers. If approved it would be the first step toward applying the types of performance testing now required in personnel dosimetry to environmental radiation monitoring. The objective of this study was to pilot test the draft standard, before it undergoes final balloting, on a small group of dosimetry providers that were selected to provide a mix of facility types, thermoluminescent dosimeter designs and monitoring program applications. The first phase of the pilot test involved exposing dosimeters to laboratory photon, beta, and x-ray sources at routine and accident dose levels. In the second phase, dosimeters were subjected to ninety days of simulated environmental conditions in an environmental chamber that cycled through extremes of temperature and humidity. Two out of seven participants passed all categories of the laboratory testing phase, and all seven passed the environmental test phase. While some relatively minor deficiencies were uncovered in the course of the pilot test, the results show that draft N13.29 describes useful tests that could be appropriate for environmental dosimetry providers. An appendix to this report contains recommendations that should be addressed by the N13.29 working group before draft N13.29 is submitted for balloting
Graphical Tests for Power Comparison of Competing Designs.

Science.gov (United States)

Hofmann, H; Follett, L; Majumder, M; Cook, D

2012-12-01

Lineups have been established as tools for visual testing similar to standard statistical inference tests, allowing us to evaluate the validity of graphical findings in an objective manner. In simulation studies lineups have been shown as being efficient: the power of visual tests is comparable to classical tests while being much less stringent in terms of distributional assumptions made. This makes lineups versatile, yet powerful, tools in situations where conditions for regular statistical tests are not or cannot be met. In this paper we introduce lineups as a tool for evaluating the power of competing graphical designs. We highlight some of the theoretical properties and then show results from two studies evaluating competing designs: both studies are designed to go to the limits of our perceptual abilities to highlight differences between designs. We use both accuracy and speed of evaluation as measures of a successful design. The first study compares the choice of coordinate system: polar versus cartesian coordinates. The results show strong support in favor of cartesian coordinates in finding fast and accurate answers to spotting patterns. The second study is aimed at finding shift differences between distributions. Both studies are motivated by data problems that we have recently encountered, and explore using simulated data to evaluate the plot designs under controlled conditions. Amazon Mechanical Turk (MTurk) is used to conduct the studies. The lineups provide an effective mechanism for objectively evaluating plot designs.

TESTING MULTI-CRITERIA DECISION ANALYSIS FOR MORE TRANSPARENT RESOURCE-ALLOCATION DECISION MAKING IN COLOMBIA.

Science.gov (United States)

Castro Jaramillo, Hector Eduardo; Goetghebeur, Mireille; Moreno-Mattar, Ornella

2016-01-01

In 2012, Colombia experienced an important institutional transformation after the establishment of the Health Technology Assessment Institute (IETS), the disbandment of the Regulatory Commission for Health and the reassignment of reimbursement decision-making powers to the Ministry of Health and Social Protection (MoHSP). These dynamic changes provided the opportunity to test Multi-Criteria Decision Analysis (MCDA) for systematic and more transparent resource-allocation decision-making. During 2012 and 2013, the MCDA framework Evidence and Value: Impact on Decision Making (EVIDEM) was tested in Colombia. This consisted of a preparatory stage in which the investigators conducted literature searches and produced HTA reports for four interventions of interest, followed by a panel session with decision makers. This method was contrasted with a current approach used in Colombia for updating the publicly financed benefits package (POS), where narrative health technology assessment (HTA) reports are presented alongside comprehensive budget impact analyses (BIAs). Disease severity, size of population, and efficacy ranked at the top among fifteen preselected relevant criteria. MCDA estimates of technologies of interest ranged between 71 to 90 percent of maximum value. The ranking of technologies was sensitive to the methods used. Participants considered that a two-step approach including an MCDA template, complemented by a detailed BIA would be the best approach to assist decision-making in this context. Participants agreed that systematic priority setting should take place in Colombia. This work may serve as the basis to the MoHSP on its interest of setting up a systematic and more transparent process for resource-allocation decision-making.
Optimization Criteria In Design Of Seismic Isolated Building

International Nuclear Information System (INIS)

Clemente, Paolo; Buffarini, Giacomo

2008-01-01

Use of new anti-seismic techniques is certainly suitable for buildings of strategic importance and, in general, in the case of very high risk. For ordinary buildings, instead, the cost of base isolation system should be balanced by an equivalent saving in the structure. The comparison criteria have been first defined, then a large numerical investigation has been carried out to analyze the effectiveness and the economic suitability of seismic isolation in concrete buildings
Integral Design workshops: organization, structure and testing

OpenAIRE

Zeiler, W Wim; Savanovic, P Perica

2010-01-01

The purpose of this paper is to achieve an understanding of design activities in the context of building design. The starting point is an overview of design research and design methodology. From the insights gained by this analysis of design in this specific context, we present an 'organization structure and design' workshop approach for collaborative multi-discipline design management. The workshops set-up, used to implement and to test the approach, are presented as well as the experiences ...
Regulatory compliance in the design of packages used to transport radioactive materials

International Nuclear Information System (INIS)

Raske, D.T.

1993-01-01

Shipments of radioactive materials within the regulatory jurisdiction of the US Department of Energy (DOE) must meet the package design requirements contained in Title 10 of the Code of Federal Regulations, Part 71, and DOE Order 5480.3. These regulations do not provide design criteria requirements, but only detail the approval standards, structural performance criteria, and package integrity requirements that must be met during transport. The DOE recommended design criterion for high-level Category I radioactive packagings is Section III, Division 1, of the ASME Boiler and Pressure Vessel Code. However, alternative design criteria may be used if all the design requirements are satisfied. The purpose of this paper is to review alternatives to the Code criteria and discuss their applicability to the design of containment vessels in packages for high-level radioactive materials. Issues such as design qualification by physical testing, the use of scale models, and problems encountered using a non-ASME design approach are addressed
10 CFR 60.133 - Additional design criteria for the underground facility.

Science.gov (United States)

2010-01-01

... specific site conditions identified through in situ monitoring, testing, or excavation. (c) Retrieval of... maintained. (2) Openings in the underground facility shall be designed to reduce the potential for... creating a preferential pathway for groundwater to contact the waste packages or radionuclide migration to...
Review of RIA and LOCA criteria for WWER fuel

International Nuclear Information System (INIS)

Hozer, Z.

2006-01-01

The RIA and LOCA fuel safety criteria are under revision in the international community of fuel suppliers, authorities and research organizations. The main criteria will be reviewed in the paper for WWER fuel. Experimental data on the fuel failure behaviour under reactivity-initiated accident (RIA) conditions produced in the last decade in French and Japanese test reactors indicated low failure enthalpy for high burnup fuel compared to fresh fuel. However the high burnup was not the only phenomenon influencing the fuel failure. The oxide scale on the external surface of the fuel rod, hydrogen content of the Zr cladding and the local hydriding seemed also be responsible for the failure at low enthalpy. Furthermore differences have been found between Western design fuel and Russian type WWER fuel. The burnup dependence of fuel failure for WWER fuel was found much less, probably due to the low oxidation during normal operational conditions compared to other PWRs. The recently published Vitanza and KAERI correlations for RIA failure enthalpy have been applied to 23 WWER tests. Experimental data from Russian IGR and BIGR reactors have been used. The calculations have shown that both burnup and cladding oxidation effects must be considered, however the pulse width dependence of failure enthalpy has not been confirmed. During loss of coolant accidents (LOCA) the peak cladding temperature and local oxidation criteria have to be met. The oxidation criterion is under discussion today in many laboratories. The AEKI carried out several experimental series with Zr1%Nb cladding used in WWER reactors. The paper will describe the main results of the tests and present the limit for ductile-brittle transition derived from ring compression test. The behaviour of Zr1%Nb (E110) and Zircaloy-4 claddings under LOCA conditions will be compared as well. (author)
Review of design criteria for Criticality Accident Alarm System (CAAS) used in Fuel Reprocessing Facility

International Nuclear Information System (INIS)

Chandrasekaran, S.; Basu, Pew; Sivasubramaniyan, K.; Venkatraman, B.

2016-01-01

Though fuel cycle facilities handling fissile materials are designed with careful criticality safety analysis, the criticality accident cannot be ruled out completely. Criticality Accident Alarm System (CAAS) is being installed as part of criticality safety management in fuel cycle facilities. CAAS system being used in India, is ECIL make, ionization chamber based gamma detector, which houses three identical detectors and works on 2/3 logic. As per ISO 7753 and ANSI/ANS-8.3, the CAAS must be designed to be capable of detecting any minimum accident occurs which could be of concern. Based on this, alarm limit used in CAAS is: 4 R/h (fast transient excursion) and 3 mR in 0.5 sec (slow excursion). In case of reprocessing facilities wherein process tanks located in heavy shielding, identification of CAAS installation locations require detailed radiation transport calculations. A study has been taken to estimate the gamma dose rate from thick concrete hot cells in order to determine the locations of CAAS to meet the present design criteria of alarm limit
Fuel safety criteria and review by OECD / CSNI task force

International Nuclear Information System (INIS)

Van Doesburg, W.

1999-01-01

Full text of publication follows: with the advent of advanced fuel and core designs, and the implementation of more accurate (best estimate or statistical) design and analysis methods, there is a general feeling that safety margins have been or are being reduced. Historically, fuel safety margins were defined by adding conservatism to the safety limits, which in turn were also fixed in a conservative manner, here, the expression 'conservatism' expresses the fact that bounding or limiting numbers were chosen for model parameters, plant and fuel design data, and fuel operating history values. Unfortunately, as these conservatisms were not quantified (or quantifiable), the amount of safety available or the reduction thereof is difficult to substantiate. For the regulator, it is important to know the margin available with the utilities' request for approval of new fuel or methods; likewise, for the utility and vendor it is important to know what margins exist and what they are based on, to identify in which direction they can make further progress and optimize fuel and fuel cycle cost. Naturally, each party involved will have to decide on how much margin should be in place, to establish operational criteria and ensure that these can actually be met during operation. To assess the margins issue, safety criteria themselves need to be reviewed first. Most - if not all - of the currently existing safety criteria were established during the 60's and early 70's, and verified against experiments with fuel available at that time - mostly at zero exposure. Of course, verification was performed as designs progressed in later years, primarily with the aim to be able to prove that safety criteria were adequate as long as the said conservatisms would be retained, and not with the aim to reestablish limits. The mandate to the OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria (TFFSC) is to assess the adequacy of existing fuel safety criteria, in view of the 'new design' elements (new
Creating Ribo-T: (Design, Build, Test)n.

Science.gov (United States)

Carlson, Erik D

2015-11-20

Engineering biology is especially challenging given our relatively poor ability to rationally design within life's complex design landscape. Thus, moving through the engineering "design, build, test" cycle multiple times accumulates system knowledge and hopefully yields a successful design. Here I discuss the engineering process behind our recently published work creating a ribosome with tethered subunits, Ribo-T.
The Examination of The Main Transportation Arteries of Konya In Terms of Landscape Architecture Design Criteria

Directory of Open Access Journals (Sweden)

Sertaç Güngör

2017-04-01

Full Text Available Ensuring comfort of use and security of pedestrians, which are the main users of urban green spaces, and the determination of their needs are important since local authorities are guiding for new pedestrian zone studies in the Konya city. Because of the problems caused by the upper structure, the necessary care is not given in terms of transportation comfort, pedestrian safety, vehicle security, plant design and ergonomic / antropemetric standards. The pedestrian way and refuge landscape designs have an important position and amount among open green areas on the scale of Konya. However, it was identified that the applications conducted were inadequate in terms of aesthetic and functional characteristics and were not suitable for the urban landscape design principles, in general, and the standards of urban afforestation of the streets. In this study, the current situation of 3 main streets of Konya used most intensely was examined in terms of landscape design criteria and some suggestions were made by attempting to identify the improvement works that should be performed by the public authorities.
Advanced Mechanical Testing of Sandwich Materials

DEFF Research Database (Denmark)

Hayman, Brian; Berggreen, Christian; Jenstrup, Claus

2008-01-01

An advanced digital optical system has been used to measure surface strains on sandwich face and core specimens tested in a project concerned with improved criteria for designing sandwich X-joints. The face sheet specimens were of glass reinforced polyester and were tested in tension. The core sp...
Suppression criteria of parasitic mode oscillations in a gyrotron beam tunnel

Science.gov (United States)

Kumar, Nitin; Singh, Udaybir; Singh, T. P.; Sinha, A. K.

2011-02-01

This paper presents the design criteria of the parasitic mode oscillations suppression for a periodic, ceramic, and copper loaded gyrotron beam tunnel. In such a type of beam tunnel, the suppression of parasitic mode oscillations is an important design problem. A method of beam-wave coupling coefficient and its mathematical formulation are presented. The developed design criteria are used in the beam tunnel design of a 42 GHz gyrotron to be developed for the Indian TOKAMAK system. The role of the thickness and the radius of the beam tunnel copper rings to obtain the developed design criteria are also discussed. The commercially available electromagnetic code CST and the electron trajectory code EGUN are used for the simulations.
Suppression criteria of parasitic mode oscillations in a gyrotron beam tunnel

International Nuclear Information System (INIS)

Kumar, Nitin; Singh, Udaybir; Sinha, A. K.; Singh, T. P.

2011-01-01

This paper presents the design criteria of the parasitic mode oscillations suppression for a periodic, ceramic, and copper loaded gyrotron beam tunnel. In such a type of beam tunnel, the suppression of parasitic mode oscillations is an important design problem. A method of beam-wave coupling coefficient and its mathematical formulation are presented. The developed design criteria are used in the beam tunnel design of a 42 GHz gyrotron to be developed for the Indian TOKAMAK system. The role of the thickness and the radius of the beam tunnel copper rings to obtain the developed design criteria are also discussed. The commercially available electromagnetic code CST and the electron trajectory code EGUN are used for the simulations.
ASSESSMENT OF THE RELEVANCE OF DISPLACEMENT BASED DESIGN METHODS/CRITERIA TO NUCLEAR PLANT STRUCTURES

International Nuclear Information System (INIS)

HOFMAYER, C.; MILLER, C.; WANG, Y.; COSTELLO, J.

2001-01-01

Revisions to the USNRC Regulatory Guides and Standard Review Plan Sections devoted to earthquake engineering practice are currently in process. The intent is to reflect changes in engineering practice that have evolved in the twenty years that have passed since those criteria were originally published. Additionally, field observations of the effects of the Northridge (1994) and Kobe (1995) earthquakes have inspired some reassessment in the technical community about certain aspects of design practice. In particular, questions have arisen about the effectiveness of basing earthquake resistant designs on resistance to seismic forces and, then evaluating tolerability of the expected displacements. Therefore, a research effort was undertaken to examine the implications for NRC's seismic practice of the move, in the earthquake engineering community, toward using expected displacement rather than force (or stress) as the basis for assessing design adequacy. The results of the NRC sponsored research on this subject are reported in this paper. A slow trend toward the utilization of displacement based methods for design was noted. However, there is a more rapid trend toward the use of displacement based methods for seismic evaluation of existing facilities. A document known as FEMA 273, has been developed and is being used as the basis for the design of modifications to enhance the seismic capability of existing non-nuclear facilities. The research concluded that displacement based methods, such as given in FEMA 273, may be useful for seismic margin studies of existing nuclear power stations. They are unlikely to be useful for the basic design of new stations since nuclear power stations are designed to remain elastic during a seismic event. They could, however, be useful for estimating the margins associated with that design
Development of in-pile test and evaluation technology

Energy Technology Data Exchange (ETDEWEB)

Kang, Yung Hwan; Park, Jong Man; Joo, Kee Nam; Park, Duk Keun; Park, Se Jin; Oh, Jong Myung; Kim, Tae Ryong; Park Jin Suk; Lee, Jae Han [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1994-08-01

To develop the in-pile test and evaluation technologies using KMRR, basic design of instrumented capsule and auxiliary system for material irradiation test and the related studies are performed. First, reactor and test hole characteristics are summarized, and conceptual design requirements of capsule to KMRR are reviewed. And fundamental principles and criteria for the instrumented capsule design are summarized. Basic design and analysis of instrumented capsule are performed, and design of capsule supporting system are also performed and structural integrity of the system is analyzed. Based on the prior studies, test mock-ups are designed and manufactured, and thermohydraulic and vibration tests are prepared. And, as in-pile test evaluation technologies, KMRR neutron dosimetry and mechanical tests related to material irradiation are investigated. 67 figs, 30 tabs, 41 refs. (Author).
Strain-based plastic instability acceptance criteria for ferritic steel safety class 1 nuclear components under level D

International Nuclear Information System (INIS)

Kim, Ji Su; Lee, Han Sang; Kim, Yun Jae; Kim, Jong Sung; Kim, Jin Won

2015-01-01

This paper proposes strain-based acceptance criteria for assessing plastic instability of the safety class 1 nuclear components made of ferritic steel during level D service loads. The strain-based criteria were proposed with two approaches: (1) a section average approach and (2) a critical location approach. Both approaches were based on the damage initiation point corresponding to the maximum load-carrying capability point instead of the fracture point via tensile tests and finite element analysis (FEA) for the notched specimen under uni-axial tensile loading. The two proposed criteria were reviewed from the viewpoint of design practice and philosophy to select a more appropriate criterion. As a result of the review, it was found that the section average approach is more appropriate than the critical location approach from the viewpoint of design practice and philosophy. Finally, the criterion based on the section average approach was applied to a simplified reactor pressure vessel (RPV) outlet nozzle subject to SSE loads. The application shows that the strain-based acceptance criteria can consider cumulative damages caused by the sequential loads unlike the stress-based acceptance criteria and can reduce the over conservatism of the stress-based acceptance criteria, which often occurs for level D service loads.
Strain-based plastic instability acceptance criteria for ferritic steel safety class 1 nuclear components under level D

Energy Technology Data Exchange (ETDEWEB)

Kim, Ji Su; Lee, Han Sang; Kim, Yun Jae [Dept. of Mechanical Engineering, Korea University, Seoul (Korea, Republic of); Kim, Jong Sung [Dept. of Mechanical Engineering, Sunchon National University, Suncheon (Korea, Republic of); Kim, Jin Won [Dept. of Nuclear Engineering, Chosun University, Gwangju (Korea, Republic of)

2015-04-15

This paper proposes strain-based acceptance criteria for assessing plastic instability of the safety class 1 nuclear components made of ferritic steel during level D service loads. The strain-based criteria were proposed with two approaches: (1) a section average approach and (2) a critical location approach. Both approaches were based on the damage initiation point corresponding to the maximum load-carrying capability point instead of the fracture point via tensile tests and finite element analysis (FEA) for the notched specimen under uni-axial tensile loading. The two proposed criteria were reviewed from the viewpoint of design practice and philosophy to select a more appropriate criterion. As a result of the review, it was found that the section average approach is more appropriate than the critical location approach from the viewpoint of design practice and philosophy. Finally, the criterion based on the section average approach was applied to a simplified reactor pressure vessel (RPV) outlet nozzle subject to SSE loads. The application shows that the strain-based acceptance criteria can consider cumulative damages caused by the sequential loads unlike the stress-based acceptance criteria and can reduce the over conservatism of the stress-based acceptance criteria, which often occurs for level D service loads.
Evaluation of proposed German safety criteria for high-temperature gas-cooled reactors

International Nuclear Information System (INIS)

Barsell, A.W.

1980-05-01

This work reviews proposed safety criteria prepared by the German Bundesministerium des Innern (BMI) for future licensing of gas-cooled high-temperature reactor (HTR) concepts in the Federal Republic of Germany. Comparison is made with US General Design Criteria (GDCs) in 10CFR50 Appendix A and with German light water reactor (LWR) criteria. Implications for the HTR design relative to the US design and safety approach are indicated. Both inherent characteristics and design features of the steam cycle, gas turbine, and process heat concepts are taken into account as well as generic design options such as a pebble bed or prismatic core
Investigation of the Stress Intensity Limits of ASME Section III Div.5 for Structure Design Criteria of SFR Fuel Assembly

Energy Technology Data Exchange (ETDEWEB)

Choo, Jin-Yup; Kim, Hyung-Kyu; Cheon, Jin-Sik [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

These affect the mechanical design of the fuel assembly components. And thus, appropriate structural design criteria should also be chosen to incorporate the specific design conditions of the SFR fuel assemblies. Among them, the temperature is one of the most crucial conditions to be concerned because the sodium coolant temperature is normally more than 500ºC which is much higher than that of the LWR (< 350ºC). This implies that a thermal creep should be significantly considered in the SFR fuel assembly mechanical design. In addition to the high temperature condition, an irradiation swelling is also an important behavior that the SFR fuel assembly material should accommodate. To incorporate the temperature and irradiation impacts, the material of the fuel assembly components is presently determined to be made of HT-9, the ferriticmartensitic steel. In this paper, the ASME Sec. III Div. 5 (referred to as ‘Div. 5’ hereinafter), which was developed for a ‘high temperature reactor’, is considered as one of the structural design criteria for the mechanical design of SFR fuel assemblies. In this paper, the stress intensity limits, S{sub m} and S{sub t} of HT-9 were built for the structural criteria of an SFR fuel assembly. S{sub m} is obtained from the ultimate strength. As for S{sub t}, it is more complicated because of its dependency of time duration in addition to temperature. Following the definition of S{sub mt}, the method in the ASME Sec. III Div. 1, Subsec. NH was consulted. We found that the Sm is adopted as S{sub mt} under the temperature about 470ºC which is relatively low temperature range and over 470ºC with relatively short time duration as 1000 hours. And the S{sub t} is adopted as Smt at over 470ºC and long time duration over 34800 hours, and over 520ºC and 10{sup 4} hours too. And at over 570ºC and 1000 hours, and at over 630ºC and 100 hours, S{sub t} is also adopted for S{sub mt}.
Engineering design of vertical test stand cryostat

International Nuclear Information System (INIS)

Suhane, S.K.; Sharma, N.K.; Raghavendra, S.; Joshi, S.C.; Das, S.; Kush, P.K.; Sahni, V.C.; Gupta, P.D.; Sylvester, C.; Rabehl, R.; Ozelis, J.

2011-01-01

Under Indian Institutions and Fermilab collaboration, Raja Ramanna Centre for Advanced Technology and Fermi National Accelerator Laboratory are jointly developing 2K Vertical Test Stand (VTS) cryostats for testing SCRF cavities at 2K. The VTS cryostat has been designed for a large testing aperture of 86.36 cm for testing of 325 MHz Spoke resonators, 650 MHz and 1.3 GHz multi-cell SCRF cavities for Fermilab's Project-X. Units will be installed at Fermilab and RRCAT and used to test cavities for Project-X. A VTS cryostat comprises of liquid helium (LHe) vessel with internal magnetic shield, top insert plate equipped with cavity support stand and radiation shield, liquid nitrogen (LN 2 ) shield and vacuum vessel with external magnetic shield. The engineering design and analysis of VTS cryostat has been carried out using ASME B and PV Code and Finite Element Analysis. Design of internal and external magnetic shields was performed to limit the magnetic field inside LHe vessel at the cavity surface 2 shield has been performed to check the effectiveness of LN 2 cooling and for compliance with ASME piping code allowable stresses.

Regulatory Safety Issues in the Structural Design Criteria of ASME Section III Subsection NH and for Very High Temperatures for VHTR and GEN IV

International Nuclear Information System (INIS)

O'Donnell, William J.; Griffin, Donald S.

2007-01-01

The objective of this task is to identify issues relevant to ASME Section III, Subsection NH [1], and related Code Cases that must be resolved for licensing purposes for VHTGRs (Very High Temperature Gas Reactor concepts such as those of PBMR, Areva, and GA); and to identify the material models, design criteria, and analysis methods that need to be added to the ASME Code to cover the unresolved safety issues. Subsection NH was originally developed to provide structural design criteria and limits for elevated-temperature design of Liquid Metal Fast Breeder Reactor (LMFBR) systems and some gas-cooled systems. The U.S. Nuclear Regulatory Commission (NRC) and its Advisory Committee for Reactor Safeguards (ACRS) reviewed the design limits and procedures in the process of reviewing the Clinch River Breeder Reactor (CRBR) for a construction permit in the late 1970s and early 1980s, and identified issues that needed resolution. In the years since then, the NRC and various contractors have evaluated the applicability of the ASME Code and Code Cases to high-temperature reactor designs such as the VHTGRs, and identified issues that need to be resolved to provide a regulatory basis for licensing. This Report describes: (1) NRC and ACRS safety concerns raised during the licensing process of CRBR , (2) how some of these issues are addressed by the current Subsection NH of the ASME Code; and (3) the material models, design criteria, and analysis methods that need to be added to the ASME Code and Code Cases to cover unresolved regulatory issues for very high temperature service.
Technical basis for acceptance criteria on the susceptibility of digital systems to electromagnetic interference

International Nuclear Information System (INIS)

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

1992-01-01

This paper discusses the development of the technical basis for establishing acceptance criteria on the susceptibility of digital systems to electromagnetic interference (EMI). The effort is sponsored by the US Nuclear Regulatory Commission and stems from the safety-related issues that need to be addressed with the application of digital instrumentation and controls systems in nuclear power plants. Designers of digital circuits are incorporating increasingly higher clock frequencies and lower logic voltage levels, thereby leading to the risk of susceptibility when spurious interference is misinterpreted as legitimate logic. Development of the technical basis for acceptance criteria centers around establishing good engineering practices to ensure that sufficient levels of electromagnetic compatibility (EMC) are maintained between the nuclear power plant's electronic and electromechanical systems. First, good EMC design and installation practices are needed to control the emissions from interference sources and their impact on other nearby circuits and systems. Then, a test and evaluation program is needed to outline the EMI tests to be performed, the associated test methods to be followed, and adequate test limits to ensure that the circuit or system under test meets the recommended guidelines. Test and evaluation should be followed by periodic maintenance to assess whether the recommended EMI control practices continue to be adhered to as part of the routine operation of the nuclear power plant. By following these steps, the probability of encountering safety-related problems associated with EMI will be greatly reduced
Acceptance test procedure for Project W-280

International Nuclear Information System (INIS)

Stites, C.G.

1994-01-01

This Document is the Acceptance Test Procedure for 200 Area C and SY Tank Farm Lighting Upgrade. This Acceptance Test Procedure has been prepared to demonstrate that the Tank Farm Lighting Systems function correctly as required by project criteria and as intended by design
Composite Monopack for 120mm Mortar, With Plastic Pallet Adapters on a 42" x 53" Wooden Pallet, MIL-STD-1660 Tests, "Design Criteria for Ammunition Unit Loads", and Extreme Temperature Tests

National Research Council Canada - National Science Library

Dugan, Jeffery L

2005-01-01

... (AMSRD-AAR-AIL-P) to conduct MIL-STD-1660 Tests to determine if the composite monopack for the 120MM mortar, with plastic pallet adapters on a 42" x 53" wooden pallet, designed by US Army ARDEC and manufactured...
76 FR 82323 - Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units

Science.gov (United States)

2011-12-30

... Filtration and Adsorption Units AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide... for Air Filtration and Adsorption Units of Postaccident Engineered-Safety-Feature Atmosphere Cleanup... testing of air filtration and iodine adsorption units of engineered-safety-feature (ESF) atmosphere...
Automation of vibroacoustic data bank for random vibration criteria development. [for the space shuttle and launch vehicles

Science.gov (United States)

Ferebee, R. C.

1982-01-01

A computerized data bank system was developed for utilization of large amounts of vibration and acoustic data to formulate component random vibration design and test criteria. This system consists of a computer, graphics tablet, and a dry-silver hard copier which are all desk-top type hardware and occupy minimal space. The data bank contains data from the Saturn V and Titan III flight and static test programs. The vibration and acoustic data are stored in the form of power spectral density and one-third octave band plots over the frequency range from 20 to 2000 Hz. The data was stored by digitizing each spectral plot by tracing with the graphics tablet. The digitized data was statistically analyzed and the resulting 97.5% probability levels were stored on tape along with the appropriate structural parameters. Standard extrapolation procedures were programmed for prediction of component random vibration test criteria for new launch vehicle and payload configurations. This automated vibroacoustic data bank system greatly enhances the speed and accuracy of formulating vibration test criteria. In the future, the data bank will be expanded to include all data acquired from the space shuttle flight test program.
Design criteria for a data base management system for a PACS at Georgetown University Hospital

International Nuclear Information System (INIS)

Fahey, F.H.; Wang, P.C.; Mun, S.K.; Choyke, P.L.; Benson, H.R.; Duerinckx, A.; Elliott, L.P.

1986-01-01

A major goal of a radiologic picture archival and communication system (PACS) is to increase the availability of the data to the users who require access to them. This is done by providing the data in a digital form which can be readily communicated and archived. In this manner, the PACS can be seen as a specific example of a data base managements system (DBMS). The PACS/DBMS should organize the data base in such a way as to provide its users with the data they require in a timely and efficient manner. The ability to integrate the variety of data into common data base should lead to a more complete and relevant representation of the available information. A PACS/DBMS is not only unique in the types of data contained in the data base and its different users but also in the volume of data that are entered into the system and transferred within the system each day. Consideration of these characteristics leads to the definition of functional criteria for the PACS/DBMS. This report discusses the criteria that will be used in the design of a DBMS for a PACS at Georgetown University Hospital. (Auth.)
Honeycomb technology materials, design, manufacturing, applications and testing

CERN Document Server

Bitzer, Tom

1997-01-01

Honeycomb Technology is a guide to honeycomb cores and honeycomb sandwich panels, from the manufacturing methods by which they are produced, to the different types of design, applications for usage and methods of testing the materials. It explains the different types of honeycomb cores available and provides tabulated data of their properties. The author has been involved in the testing and design of honeycomb cores and sandwich panels for nearly 30 years. Honeycomb Technology reflects this by emphasizing a `hands-on' approach and discusses procedures for designing sandwich panels, explaining the necessary equations. Also included is a section on how to design honeycomb energy absorbers and one full chapter discussing honeycomb core and sandwich panel testing. Honeycomb Technology will be of interest to engineers in the aircraft, aerospace and building industries. It will also be of great use to engineering students interested in basic sandwich panel design.
Floorball game skills (evaluation criteria)

OpenAIRE

Chlumský, Marek

2013-01-01

Title: Playing skills in floorball (evaluation criteria). Target: To create a list of playing skills which an ideal player should demonstrate. Find and verify the evaluation criteria of these skills and inspire trainers to develop these skills in the best way. Methods: Informal interviews, individually structured interviews, analysis and verification of data, pilot testing. Results: Defined playing skills in floorball, developed scale of values of floorball playing skills, creation of exercis...
Design and test of a high pressure centrifugal compressor

International Nuclear Information System (INIS)

Choi, Jae Ho; Han, Chak Heui; Paeng, Ki Seok; Chen, Seung Bae; Kim, Yong Ryun

2005-01-01

This paper presents an aerodynamic design, flow analysis and performance test of a pressure ratio 4:1 centrifugal compressor for gas turbine engine. The compressor is made up of a centrifugal impeller, a two-stage diffuser consisted of radial and axial types. The impeller has a 45 degree backswept angle and the design running tip clearance is 5% of impeller exit height. Three-dimensional numerical analysis is performed to analyze the flows in the impeller, diffuser and deswirler considering the impeller tip clearance. Test module and rig facilities for the compressor stage performance test are designed and fabricated. The overall compressor stage performances as well as the static pressure fields on the impeller and diffuser are measured. Two diffusers of wedge and airfoil types are tested with an impeller. The calculation and test results show that flow fields downstream the deswirler at the design and off-design points are highly nonuniform and the airfoil diffuser has the better aerodynamic characteristics than those of wedge diffuser
MULTI-CRITERIA APPROACH FOR DESIGNING SUSTAINABLE DRAINAGE IN MALANG RESIDENTIAL AREA INDONESIA

Directory of Open Access Journals (Sweden)

HAPSARI Ratih Indri

2016-07-01

Full Text Available Environmentally sound approach for sustainable urban drainage could promote infiltration and lower the risk of flooding. This study presents the framework to evaluate the drainage alternatives considering multiple aspects including water quantity, life cycle cost and amenity. This approach is verified through application at a residential area in Malang city Indonesia. Different combinations of drainage components comprising of drainage channels, infiltration wells and biopore absorption holes are assessed regarding runoff reduction, present value of life cycle cost, and willingness to pay for the convenience. The first part describes the effective designs of sustainable drainage components in the houses as well as in the public spaces of the housing. The second part of this study describes the use of analytic hierarchy process for weight assignment of sustainability criteria and multiple benefit calculation. The study recommends infiltration wells and biopore absorption holes together with drainage channels as the best management practice of sustainable drainage system based on its overall sustainability index.
NWTS conceptual reference repository description (CRRD). Volume III. Criteria, bases, special studies, and codes

International Nuclear Information System (INIS)

1981-05-01

This volume documents the criteria, design bases, and special studies and provides the backup for the design presented in Volume II. The criteria presented here were developed by ONWI as a draft version for consideration in this conceptual report. Since these criteria were developed subsequent to preparation of the reports used as a basis for the CRRD, not all of the criteria could be fully considered in preparation of the CRRD. However, they were used as guidelines wherever possible. The criteria for terminal storage of waste are still in development. The chapter on the design bases identifies the important design considerations and provides the justification for their selection. The design bases were developed not so much to give exact values for parameters as to identify the parameters that are significant to the design. They also serve as a common basis for coordinating analysis and design studies unitl the next design phase is completed. Some of the design bases presented here were taken directly from the Stearns-Roger NWTS-R1 Conceptual Design Report. The special studies document technical aspects of the design that are of particular importance or that furnish additional information pertaining to the design
E-4 Test Facility Design Status

Science.gov (United States)

Ryan, Harry; Canady, Randy; Sewell, Dale; Rahman, Shamim; Gilbrech, Rick

2001-01-01

Combined-cycle propulsion technology is a strong candidate for meeting NASA space transportation goals. Extensive ground testing of integrated air-breathing/rocket system (e.g., components, subsystems and engine systems) across all propulsion operational modes (e.g., ramjet, scramjet) will be needed to demonstrate this propulsion technology. Ground testing will occur at various test centers based on each center's expertise. Testing at the NASA John C. Stennis Space Center will be primarily concentrated on combined-cycle power pack and engine systems at sea level conditions at a dedicated test facility, E-4. This paper highlights the status of the SSC E-4 test Facility design.
Using partial safety factors in wind turbine design and testing

Energy Technology Data Exchange (ETDEWEB)

Musial, W.D. [National Renewable Energy Lab., Golden, CO (United States)

1997-12-31

This paper describes the relationship between wind turbine design and testing in terms of the certification process. An overview of the current status of international certification is given along with a description of limit-state design basics. Wind turbine rotor blades are used to illustrate the principles discussed. These concepts are related to both International Electrotechnical Commission and Germanischer Lloyd design standards, and are covered using schematic representations of statistical load and material strength distributions. Wherever possible, interpretations of the partial safety factors are given with descriptions of their intended meaning. Under some circumstances, the authors` interpretations may be subjective. Next, the test-load factors are described in concept and then related to the design factors. Using technical arguments, it is shown that some of the design factors for both load and materials must be used in the test loading, but some should not be used. In addition, some test factors not used in the design may be necessary for an accurate test of the design. The results show that if the design assumptions do not clearly state the effects and uncertainties that are covered by the design`s partial safety factors, outside parties such as test labs or certification agencies could impose their own meaning on these factors.
Designing a Software Test Automation Framework

Directory of Open Access Journals (Sweden)

Sabina AMARICAI

2014-01-01

Full Text Available Testing is an art and science that should ultimately lead to lower cost businesses through increasing control and reducing risk. Testing specialists should thoroughly understand the system or application from both the technical and the business perspective, and then design, build and implement the minimum-cost, maximum-coverage validation framework. Test Automation is an important ingredient for testing large scale applications. In this paper we discuss several test automation frameworks, their advantages and disadvantages. We also propose a custom automation framework model that is suited for applications with very complex business requirements and numerous interfaces.
The application of strength and power related field tests in older adults : criteria, current status and a future perspective

NARCIS (Netherlands)

Regterschot, G. Ruben H.; Morat, Tobias; Folkersma, Marjanne; Zijlstra, Wiebren

2015-01-01

Leg muscle strength (LMS) and leg muscle power (LMP) are determinants of aspects of functional status and important parameters for measuring intervention effects in older adults. Field tests are often used for the evaluation of LMS and LMP in older persons. However, criteria important for the
Transferability of habitat suitability criteria for fishes in warmwater streams

Science.gov (United States)

Freeman, Mary C.; Bowen, Z.H.; Crance, J.H.

1997-01-01

We developed habitat suitability criteria and tested their transferability for nine fishes inhabiting unregulated Piedmont and Coastal Plain streams in Alabama. Cr iteria for optimal habitat were defined as ranges of depth, velocity, substrate type and cover type for which a species' suitability index (proportional abundance divided by proportional habitat availability, scaled from 0 to 1) equalled or exceeded 0.4. We evaluated the transferability of criteria between study sites by testing the null hypothesis that species occurrence in a sample was independent of whether or not the sample was taken in optimal habitat. We also tested criteria transference to a large, flow-regulated river sampled during low flow periods. Depth, velocity and most substrate criteria developed for the bronze darter Percina palmaris successfully transferred between unregulated streams and to the flow-regulated river samples. All criteria developed for a pair of closely related, allopatric darter species, Etheostoma chuckwachattee and E. jordani, transferred sucessfully when applied between species (in the unregulated sites) and to the regulated river samples. In contrast, criteria for the Alabama shiner Cyprinella callistia failed nearly all tests of transferability. Criteria for E. stigmaeum, P. nigrofasciata, an undescribed Percina species, and a pair of related, allopatric Cyprinella species transferred inconsistently. The species with good criteria transference had high suitability indices for shallow depths, fast current velocities and coarse substrates, characteristic of riffle species. We suggest that microhabitat criteria for riffle fishes are more likely to provide a transferable measure of habitat quality than criteria for fishes that, although restricted to fluvial habitats, commonly occupy a variety of pool and riffle habitats.
Assessment of current structural design methodology for high-temperature reactors based on failure tests

International Nuclear Information System (INIS)

Corum, J.M.; Sartory, W.K.

1985-01-01

A mature design methodology, consisting of inelastic analysis methods, provided in Department of Energy guidelines, and failure criteria, contained in ASME Code Case N-47, exists in the United States for high-temperature reactor components. The objective of this paper is to assess the adequacy of this overall methodology by comparing predicted inelastic deformations and lifetimes with observed results from structural failure tests and from an actual service failure. Comparisons are presented for three types of structural situations: (1) nozzle-to-spherical shell specimens, where stresses at structural discontinuities lead to cracking, (2) welded structures, where metallurgical discontinuities play a key role in failures, and (3) thermal shock loadings of cylinders and pipes, where thermal discontinuities can lead to failure. The comparison between predicted and measured inelastic responses are generally reasonalbly good; quantities are sometimes overpredicted somewhat, and, sometimes underpredicted. However, even seemingly small discrepancies can have a significant effect on structural life, and lifetimes are not always as closely predicted. For a few cases, the lifetimes are substantially overpredicted, which raises questions regarding the adequacy of existing design margins
Design criteria for mobile phones: a teenagers perspective.

CSIR Research Space (South Africa)

Batchelor, J

2009-09-01

Full Text Available on mobile phones without blindly following criteria as observed - because there was no anchor they had to set the benchmarks for themselves. A student went even further, reflecting on long-term prospects of the project, remarking: “It is a project...-suited to mobile phones, due to obvious limitations of screen size and resolution, audio and memory restrictions. Low cost and affordable mobile phones in Africa are developing a new conduit for learning, and are gradually influencing the way we view...
Design of an accelerated test to determine the attack of the sulphates on concrete structures, and the suggest alternative to design a container

International Nuclear Information System (INIS)

Malanca, Rodrigo Sebastian

2003-01-01

This work at demonstrating one of the accelerated tests in the frame of the Norm ASTM E-632-82, in order to evaluate the life of service for Reinforced Concrete Structures with High Performance.These will be used as barriers of engineering in containers for Radioactive Wastes.The results of the evaluation are necessary for the probabilistic and deterministic analysis, which are required to obtain licentiate for the emplacement and construction of this type of installations.Since concrete is the principal material used in this type of containers, its properties, in particular, its durability must be evaluated taking into accounts both, intrinsic factors and the extrinsic factors.Within the intrinsic factors we can mention your formulation, including design of armors of steel, production, treated and structural design.As extrinsic factors, weather and environmental, soil characteristic and service operation must be considered.It is important to emphasize that within the criteria used in the conceptual design of these types of repositories, the structures that act of barrier must not alter their insulation properties during all the period of service, which may be several hundreds of years.Although it is not possible to guarantee that repository's performance will not be altered throughout its time of service, the fact to obtain results of accelerated tests and the long term, it will enable us to estimate the durability of such structures, across the support of mathematical suitable models.The different stages which should be taken into account for the development of the evaluation tests, determining the relevant parameters to be considered in them and results obtained so far, are showing in this work

Some links on this page may take you to non-federal websites. Their policies may differ from this site.